Sample records for fired power stations

  1. Fire protection concept for power stations

    Zitzmann, H.

    The author shows how a systematic approach permits the design of a fire-protected power station. The special conditions of an individual power station are here treated as marginal conditions. The article describes how the concept is realized in the completed power station, taking account of the information provided by fire statistics. (orig.) [de

  2. Fire safety in nuclear power stations

    Kench, R.L.


    This is the first of a three-part report on the fire hazards in nuclear power stations and some of the precautions necessary. This part lists the United Kingdom reactors, outlines how they work, the fuels used, the use of moderators and coolants and the control systems. Although the risk of fire is no higher than in fossil-fuel stations the consequences can be more serious. The radioactive materials used mean that there is biological shielding round the core, limitations on waste emissions allowed and limited access to some zones. Reliable shut-down systems are needed. Care in the use of water to fight fires must be exercised -it can act as a moderator and cause an otherwise safe core to go critical. The Wigner effect in graphite moderated reactors is explained. Fires in graphite can be extinguished by carbon dioxide. Argon, chlorine and sodium silicate can also be effective. In sodium cooled reactors fires can be allowed to burn themselves out, or TEC and argon could be used to extinguish the flame. (UK)

  3. Fire Stations

    Department of Homeland Security — Fire Stations in the United States Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their...

  4. Sodium fires and nuclear power station safety

    Ivanenko, V.N.; Zubin, A.; Drobyshev, A.V.


    The danger of sodium aerosol release at a design basis accident (DBA) of a sodium-cooled fast reactor that involves coolant leakage and burning, is being analyzed. It has been shown that radioactive and toxic releases at DBA do not exceed permissible values. Some means of sodium fire fighting are described. (author)

  5. Challenges to fire protection measures at Hamaoka Nuclear Power Station

    Narama, Takeshi


    New regulatory standards for fire protection at nuclear power plants have been established by the Nuclear Regulation Authority. This paper introduces the measures taken by the Hamaoka Nuclear Power Station for the following four items, which were especially big changes. (1) To install a combination of sensors of different types or instruments with equivalent functions so as to be able to emit unique signals to inform a fire in the early stage. (2) To conduct 'UL vertical burn test' as the demonstration test for self-extinguishing performance as the condition for flame-retardant cable. (3) To install automatic fire-extinguishers or fixed fire-extinguishing devices of manual type at the spots where fire-fighting is difficult due to the filling of smoke in a fire or the effect of radiation. (4) To separate the system for purpose of ensuring safety function to attain the high-temperature shutdown and cold-temperature shutdown of a reactor whatever fire may happen at the nuclear facilities. The examples of the installation of fire-extinguishers as the measures for the above Item (3) are as follows; (A) as for the devices containing oil, a foam-extinguishing agent is released against each target device from the nozzle, and (B) for large vertical pump motors indoors and relatively small pump motors, IA type automatic foam extinguishing systems are installed. (A.O.)

  6. Fire fighting at Chernobyl and fire protection at UK nuclear power stations

    Bindon, F.J.L.


    The fire fighting measures undertaken by the fire crews at the Chernobyl reactor accident are described. This information highlights the need to develop engineering equipment which will give a far greater degree of personnel protection to fire crews and others in radiological accidents. The British position on fire protection at nuclear power stations is outlined. The general levels of radiation exposure which would be used as a guide to persons in the vicinity of a radiation accident are also given. (UK)

  7. Natural radionuclides near a coal-fired power station

    Smith-Briggs, J L


    An experiment was carried out to measure the specific activity of Pb-210 and Po-210 in livers from cattle that had grazed in a field near Didcot coal-fired power station. Livers from cattle in the Cotswold region were measured for comparison. The specific activities of Pb-210 and Po-210 in soil and grass samples from both areas were also measured at 3-monthly intervals over a year. No statistically significant increases were observed in the Pb-210 and Po-210 levels in liver, soil or grass samples which could be attributed to the operation of the power station.

  8. Bioremediation for coal-fired power stations using macroalgae.

    Roberts, David A; Paul, Nicholas A; Bird, Michael I; de Nys, Rocky


    Macroalgae are a productive resource that can be cultured in metal-contaminated waste water for bioremediation but there have been no demonstrations of this biotechnology integrated with industry. Coal-fired power production is a water-limited industry that requires novel approaches to waste water treatment and recycling. In this study, a freshwater macroalga (genus Oedogonium) was cultivated in contaminated ash water amended with flue gas (containing 20% CO₂) at an Australian coal-fired power station. The continuous process of macroalgal growth and intracellular metal sequestration reduced the concentrations of all metals in the treated ash water. Predictive modelling shows that the power station could feasibly achieve zero discharge of most regulated metals (Al, As, Cd, Cr, Cu, Ni, and Zn) in waste water by using the ash water dam for bioremediation with algal cultivation ponds rather than storage of ash water. Slow pyrolysis of the cultivated algae immobilised the accumulated metals in a recalcitrant C-rich biochar. While the algal biochar had higher total metal concentrations than the algae feedstock, the biochar had very low concentrations of leachable metals and therefore has potential for use as an ameliorant for low-fertility soils. This study demonstrates a bioremediation technology at a large scale for a water-limited industry that could be implemented at new or existing power stations, or during the decommissioning of older power stations. Copyright © 2015 Elsevier Ltd. All rights reserved.

  9. The fire course and consequences to be drawn from the fire in the Browns Ferry nuclear power station

    Hoffmeister, N.


    After a short description of the fire course and the fire fighting measures during the cable fire at Browns Ferry nuclear power station, the effects on the safety system are given in chronological order, and consequences are drawn for a general fire protection programme for nuclear power plants. In this context, the licensing guideline of the NRC for fire protection in nuclear power plants is mentioned, which took particular account of the consequences to be drawn from the Browns Ferry fire. (ORU) [de

  10. Using plasma-fuel systems at Eurasian coal-fired thermal power stations

    Karpenko, E. I.; Karpenko, Yu. E.; Messerle, V. E.; Ustimenko, A. B.


    The development of plasma technology for igniting solid fuels at coal-fired thermal power stations in Russia, Kazakhstan, China, and other Eurasian countries is briefly reviewed. Basic layouts and technical and economic characteristics of plasma-fuel systems installed in different coal-fired boiles are considered together with some results from using these systems at coal-fired thermal power stations.

  11. Natural radionuclides near a coal-fired power station

    Smith-Briggs, J.L.


    A previous assessment of the radiological consequences of the emission of natural radionuclides from coal-fired power stations had indicated that 210 Pb was the main contributor to the maximum individual dose. This dose arose from the consumption of foodstuffs particularly cattle liver contaminated by deposited fly ash. Uncertainty surrounded some of the factors used in the assessment, and a limited environmental monitoring programme was recommended to improve it. An experiment has been performed to measure the specific activities of 210 Pb and 210 Po in livers from cattle that had grazed in a field near Didcot power station. Livers from cattle in the Cotswold region have been measured for comparison. The specific activities of 210 Pb and 210 Po in soil and grass samples from both areas have also been measured at three-monthly intervals over a year. No statistically significant increases were observed in the 210 Pb and 210 Po levels in liver, soil or grass samples which could be attributed to the operation of the power station. Transfer coefficients for 210 Pb from forage to liver were about two orders of magnitude less than that used in the original assessment, and the transfer coefficients for 210 Po about a factor a two less. (orig.)

  12. Costs of producing electricity from nuclear, coal-fired and oil-fired power stations


    The Board publishes generation costs per kW h incurred at recently commissioned power stations so that the costs and performance of nuclear and conventional stations of roughly the same date of construction can be compared. The term 'conventional power station' is used to describe coal-fired and oil-fired steam power stations. The Board has now decided: (A) to supplement the past method of calculating costs at main stations commissioned between 1965 and 1977 by giving the associated figures for interest during construction, for research, and for training; (B) to give similar figures for the contemporary stations Hinkley Point B and the first half of Drax, (C) to provide estimates of generating costs of stations under construction; (D) to set out explicitly the relationship of this method of calculation to that employed in taking investment decisions on future stations. In this way the figures for stations in commission and under construction are arrived at more in line with the general principles of evaluating investment proposals. The present document provides this information. (author)

  13. Hinkley Point 'C' power station public enquiry: proof of evidence on coal fired power station sites

    Fothergill, S.; Witt, S.


    The Coalfield Communities Campaign (CCC) has argued that if a new base-load power station is required it should be coal-fired rather than nuclear, and that it should use UK coal. Proposals for new power stations at both Hinkley Point and at Fawley have encountered very considerable local and regional opposition, and this is increasingly likely to be the case at many other sites especially in Southern England. In contrast the CCC has sought to demonstrate that its member authorities would generally welcome the development of new coal-fired capacity on appropriate sites within their areas. In particular, this proof establishes that there is a prima facie case for considering three sites - Thorpe Marsh, Hams Hall and Uskmouth - as potential locations for a new large coal-fired power station as an alternative to Hinkley Point C. The relevant local authorities have expressed their willingness to co-operate in more detailed planning or technical investigations to secure a coal-fired power station on these sites. The CCC considers this to be a major and unprecedented offer to the CEGB and its successor bodies, which could greatly speed the development of new power staion capacity and be of considerable economic and social benefit to coalfield communities.

  14. Probabilistic fire risk assessment for Koeberg Nuclear Power Station Unit 1

    Grobbelaar, J.F.; Foster, N.A.S.; Luesse, L.J.


    A probabilistic fire risk assessment was done for Koeberg Nuclear Power Station Unit 1. Areas where fires are likely to start were identified. Equipment important to safety, as well as their power and/or control cable routes were identified in each fire confinement sector. Fire confinement sectors where internal initiating events could be caused by fire were identified. Detection failure and suppression failure fault trees and event trees were constructed. The core damage frequency associated with each fire confinement sector was calculated, and important fire confinement sectors were identified. (author)

  15. Upgrading of fire protection arrangements at Magnox power stations in the United Kingdom

    Zhu, L.H.


    The methodology used in conducting fire hazard assessments at Magnox Reactor power stations operated by Magnox Electric plc is described. The assessments use a deterministic approach. This includes the identification of essential plant and the associated supporting systems required for the safe trip, shutdown and post-trip cooling of the reactor, assessment of the location of the essential plant and the vulnerability of these plant in the presence of a fire, assessment of essential functions against the effects of a fire and identification of improvements to the fire protection arrangements. Practical aspects of fire protection engineering on operating power stations are discussed and examples of improvements in protection described. (author)

  16. Fire protection devices in the controlled region of GKN nuclear power station

    Bernhardt, S.; Grauf, E.


    In the GKN nuclear power station ('Neckar reactor'), an 805 MW PWR reactor whose start-up is scheduled for the near future, fire protection measures have been realized that go far beyond those realized in other German nuclear power stations until now. One of the main reasons is that the authorities have been sensibilized by a fire in the refuelling cavity during construction and by the Browns Ferry fire and are therefore extremely thorough in their examination. Further subsections have been added to the fire prevention sections in order to provide better quenching devices for potential fire sites. (orig./AK) [de

  17. Fire protection equipment in the area of control of the Neckar Community Nuclear Power Station

    Bernhardt, S.; Grauf, E.


    In the Neckar Community Nuclear Power Station - an 805 MW pressurised water reactor shortly to reach the stage of nuclear operation - fire protection measures have been realised to an extent hitherto uncommon in German nuclear power plants. The reason is to be sought from the authorities who have become more sensitive because of a fire in a reactor vessel during the construction stage and the fire at Browns Ferry and have consequently become extremely expert. Apart from the fire regulations hitherto normal further subregulations have been created in order to be able to make better provision of extinguishing devices against fire hazards. (orig.) [de

  18. Structural rehabilitation of a fossil power station after major fire damage

    Freskakis, G.N.; Archer, J.C.; Shipskie, W.P.


    This paper discusses the eruption and course of a fire at a fossil power station. Focus is on the damage to the building and the reinforced concrete pedestal, and the assessments and repairs involved in the restoration. Emphasis is given to the pedestal since, both the response to fire and the repair for such a massive structure are of particular interest

  19. Techno-economic assessments of oxy-fuel technology for South African coal-fired power stations

    Oboirien, BO


    Full Text Available at the technical and economic viability of oxy-fuel technology for CO(sub2) capture for South African coal-fired power stations. This study presents a techno-economic analysis for six coal fired power stations in South Africa. Each of these power stations has a...

  20. Turbine oil fires in the Moabit and Reuter power stations

    Kissmann, G.


    The article describes the fire resulting from turbine oil ignition after a manometer line break, the fire fighting measures, the amount of damage, and secondary damage. Conclusions are drawn for the prevention and fighting of oil fires. (ORU) [de

  1. Mercury emissions from South Africa’s coal-fired power stations

    Belinda L. Garnham


    Full Text Available Mercury is a persistent and toxic substance that can be bio-accumulated in the food chain. Natural and anthropogenic sources contribute to the mercury emitted in the atmosphere. Eskom’s coal-fired power stations in South Africa contributed just under 93% of the total electricity produced in 2015 (Eskom 2016. Trace amounts of mercury can be found in coal, mostly combined with sulphur, and can be released into the atmosphere upon combustion. Coal-fired electricity generation plants are the highest contributors to mercury emissions in South Africa. A major factor affecting the amount of mercury emitted into the atmosphere is the type and efficiency of emission abatement equipment at a power station. Eskom employs particulate emission control technology at all its coal-fired power stations, and new power stations will also have sulphur dioxide abatement technology. A co-beneficial reduction of mercury emissions exists as a result of emission control technology. The amount of mercury emitted from each of Eskom’s coal-fired power stations is calculated, based on the amount of coal burnt and the mercury content in the coal. Emission Reduction Factors (ERF’s from two sources are taken into consideration to reflect the co-benefit received from the emission control technologies at the stations. Between 17 and 23 tons of mercury is calculated to have been emitted from Eskom’s coal-fired power stations in 2015. On completion of Eskom’s emission reduction plan, which includes fabric filter plant retrofits at two and a half stations and a flue gas desulphurisation retrofit at one power station, total mercury emissions from the fleet will potentially be reduced by 6-13% by 2026 relative to the baseline. Mercury emission reduction is perhaps currently not the most pressing air quality problem in South Africa. While the focus should then be on reducing emissions of other pollutants which have a greater impact on human health, mercury emission reduction

  2. Fire-side corrosion in power-station boilers

    Cutler, A J.B.; Flatley, T; Hay, K A


    The steel tubing of a modern power-station boiler operates at up to 650/sup 0/C (a dull red heat) in the very corrosive environment produced by the combustion gases and ash particles. Within the tubes, whose walls are around 5mm thick, 2000 tons of steam are generated per hour at temperatures up to 565/sup 0/C and pressures up to 170 bar. Several forms of metal corrosion may occur on the fireside surface of these tubes and on other boiler components. The designed 20-year operating life of the stainless-steel superheater and reheater tubes can be much reduced at temperatures above 600/sup 0/C by attack from molten salts formed beneath the deposited ash on the upstream tube surfaces. Mild steel evaporator tubes lining the furnace wall may suffer similarly if flame impingement allows the local release of volatile chlorine compounds from coal particles on the tube surface. Uncooled metal components supporting and aligning the boiler tubes may reach 1000/sup 0/C and are particularly susceptible to corrosion. CEGB research effort has been applied to quantify the rate of corrosion and to obtain an understanding of the complex corrosion mechanisms, so that ways of minimizing or preventing their occurrence may be found. These include the optimization of the combustion chemistry, design modifications such as shielding certain vulnerable tubes, and the selection of improved alloys and the use of ''co-extruded'' tubing.

  3. Fire Stations - 2007

    Kansas Data Access and Support Center — Fire Station Locations in Kansas Any location where fire fighters are stationed at or based out of, or where equipment that such personnel use in carrying out their...

  4. Fire Stations - 2009

    Kansas Data Access and Support Center — Fire Stations in Kansas Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their jobs is...

  5. Proof of safer operation of power station plant during a fire by linking in fire simulation and system technical analysis

    Hensel, W.; Beyer, H.; Samman, A.


    In order to attain the basic aims of protection in power station plant, a series of systems, which must be available also in the event of a fire, are provided. The thermal loads for the systems and components which are necessary to attain the aims of protection are ascertained by means of a simulation of the cause of the fire for the specific scenario. Statements on the availability of the systems and components in the specific scenario are derived from the design values used as the basis. (orig.) [de

  6. Environmental impact assessment of coal fired thermal power stations

    Nambi, K.S.V.; Sadasivan, S.; Negi, B.S.; Meenakshy, V.


    Coal fly ash samples collected from various thermal power plants and one lignite ash sample were analysed for various elements such as As, Ca, Ce, Co, Cr, Cu, Eu, Fe, Hf, K, La, Lu, Mn, Na, Ni, Pb, Rb, Se, Si, Sb, Sc, Sm, Sr, Ti, V, Yb and Zn using energy dispersive X-ray fluorescence and instrumental neutron activation analysis methods. The two-step maximum leachability test was also performed on all fly ash samples. 13 refs, 9 tabs

  7. Study on the Concentration Measurement of the Pollution Gases from Coal-Fired Power Station

    Zheng, L J; Li, W


    CO 2 is a main kind of pollution gases discharged from coal-fired power station. The relationship between gas concentration and pressure, temperature is deduced base on the law of Beer-Lambert and the theory of gas line-shape. The tunable diode laser spectral technology is used to analyze the changing regularity of the peak, half-peak width of the absorption curve with pressure and temperature

  8. Heavy metals in Parmelia sulcata collected in the neighborhood of a coal-fired power station

    Freitas, M.C.


    The epiphytic lichen Parmelia sulcata was collected in the neighborhood of a Portuguese coal-fired power station (Sines coal power station) as monitor for heavy metal air pollution. A study of the metal contents variability along 1991 and 1992 was performed. The heavy metals Ag, As, Br, Co, Cr, Fe, Hg, Sb, Se, and Zn were determined by k0-based instrumental neutron activation analysis. The concentrations found in 1991 and 1992 show an accumulating process of Co and Fe (approximately 5%/mo) and of Cr and Sb (approximately 7%/mo). Low accumulation is observed for Ag, Se, and Zn (approximately 2%/mo), and no concentration variation is observed for As, Br, and Hg. It is concluded that the metal accumulation observed is the result of the nearby ash and coal deposits

  9. The Atomic Energy Control Board criteria for identification and evaluation of fire hazards in nuclear power stations

    Morrison, Luke


    This report presents criteria for the identification and evaluation of fire hazards in nuclear power stations. The report presents criteria that are consistent with the existing regulatory approach in Canada, and outlines engineering tools and analytical techniques currently available to deterministically analyse fire. The criteria presented cover the topics which should be included in a fire hazard analysis and provide details of each topic so that the accuracy of an analysis may be evaluated

  10. Lichens as biomonitors around a coal-fired power station in Israel

    Garty, Jacob; Tomer, Sharon; Levin, Tal; Ehr, Haya


    In the present study epiphytic lichens were applied as biomonitors of air pollution to determine the environmental impact of a coal-fired power station. Thalli of the lichen Ramalina lacera (With.) J.R. Laund. growing on carob twigs (Ceratonia siliqua L.) were collected with their substrate in July 2000 in a relatively unpolluted forest near HaZorea, Ramoth Menashe, ortheast Israel, and transplanted to 10 biomonitoring sites in the vicinity of the coal-fired power station Oroth Rabin near the town of Hadera. The lichens were retrieved in January 2001. We examined the following parameters of lichen vitality: (a) potential quantum yield of photosynthesis expressed as fluorescence ratio F v /F m , (b) stress-ethylene production, and (c) electric conductivity expressing integrity of cell membranes. Following an exposure of 7 months, the lichens were retrieved and physiological parameters and data of elemental content were analyzed comparatively. Electric conductivity values correlated positively with B, Fe, Mg, Mn, Na, Pb, S, Sn, nd Ti content. Concentrations of stress-ethylene correlated positively with l, Ba, Pb, S, and V content and negatively with Cu and Sn. F v /F m ratios correlated negatively with S content. Some of the heavy metals reached lower levels than those reported in the relevant literature despite a wind regime that should have blown pollutants toward the biomonitoring sites

  11. Main characteristics of the radioactive enrichment in ashes produced in coal-fired power stations

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


    Under contract with the Spain's 'Nuclear Safety Council', a study is being conducted of the nation's largest nominal output coal-fired power stations. Its purpose is to assess the radiological impact on workers and local populations due to this source of NORM activity. One of the aspects of particular interest is the study of the radioactive enrichment in the combustion wastes relative to the different coals used as fuel (usually local bituminous coal or lignite, or imported coal). These wastes consist of fly ash (mostly fine particles collected in electrostatic precipitators), and bottom ash (larger in size, and collected wet or dry in hoppers below the boilers). In general terms, the enrichment factors measured were between 2 and 18 for the radionuclides 40 K, 226 Ra, 232 Th, and 210 Po. The magnitude of this enrichment factor depended mainly on the ash content of each coal, and hence on the type of coal used as fuel and the specific operation cycle in the different power stations. For the radionuclides 40 K, 226 Ra, and 232 Th, the enrichment was relatively similar in value in the fly and bottom ashes produced by the different types of coal used in the power stations studied. For 210 Po, however, as was expected, the enrichment was much greater in the fly ash than in the bottom ash for each coal analyzed. (author)

  12. Semi-quantitative characterisation of ambient ultrafine aerosols resulting from emissions of coal fired power stations

    Hinkley, J.T.; Bridgman, H.A.; Buhre, B.J.P.; Gupta, R.P.; Nelson, P.F.; Wall, T.F.


    Emissions from coal fired power stations are known to be a significant anthropogenic source of fine atmospheric particles, both through direct primary emissions and secondary formation of sulfate and nitrate from emissions of gaseous precursors. However, there is relatively little information available in the literature regarding the contribution emissions make to the ambient aerosol, particularly in the ultrafine size range. In this study, the contribution of emissions to particles smaller than 0.3 μm in the ambient aerosol was examined at a sampling site 7 km from two large Australian coal fired power stations equipped with fabric filters. A novel approach was employed using conditional sampling based on sulfur dioxide (SO 2 ) as an indicator species, and a relatively new sampler, the TSI Nanometer Aerosol Sampler. Samples were collected on transmission electron microscope (TEM) grids and examined using a combination of TEM imaging and energy dispersive X-ray (EDX) analysis for qualitative chemical analysis. The ultrafine aerosol in low SO 2 conditions was dominated by diesel soot from vehicle emissions, while significant quantities of particles, which were unstable under the electron beam, were observed in the high SO 2 samples. The behaviour of these particles was consistent with literature accounts of sulfate and nitrate species, believed to have been derived from precursor emissions from the power stations. A significant carbon peak was noted in the residues from the evaporated particles, suggesting that some secondary organic aerosol formation may also have been catalysed by these acid seed particles. No primary particulate material was observed in the minus 0.3 μm fraction. The results of this study indicate the contribution of species more commonly associated with gas to particle conversion may be more significant than expected, even close to source

  13. The Atomic Energy Control Board criteria for identification and evaluation of fire hazards in nuclear power stations

    Morrison, L.


    This report presents information for the identification and evaluation of fire hazards in nuclear power stations. The report consists of two volumes. Volume 1 contains background material which outlines tools and analytical techniques currently available to deterministically analyse fire hazards. Volume 2 presents criteria for evaluating fire hazard reports. The criteria are consistent with the existing AECB regulatory approach in Canada and cover the topics which should be included in a fire hazard analysis. This volume also provides details of each topic so that the quality of an analysis may be evaluated

  14. Environmental aspects of airbrone radioactive effluent from a coal-fired power station

    Song Miaofa; Fu Rongchu; Lu Zhizhao


    The authors determined the contents of natural uranium and thorium in coal and tunnel ash samples taken from a large coal-fired power station in the nearby area. The hourly climate data in 1980 are analysed and the atmospheric stability is cataloged by Pasquill-Turner method. Wind direction-atmospheric stability-wind velocity combined probabilities and rain-wind direction probabilities are calculated. The near ground air pollution concentrations, the ground depositions and the distributions of U and Th presented in airborne effluent (fly ash) within an area round the station with a radius of 60 km are also estimated. In the calculations, some factors such as wind velocity in the higher atmosphere, plume rise, still wind and decrease of air pollution concentration by the ground deposition (especially the wet deposition porduced by rain) have been considered. Some corrections necessary for the factors described above are also made. It is shown that the maximum annual average air pollution concentration (U max = 1.95 x 10 -7 mg.m -3 , Th max = 3.45 x 10 -7 mg.m -3 ) appears at the point 1 km away from the source in the fan SE. In the area round the station with a radius shorter than 10 km, the ground deposition is mainly by the wet deposition, but, where the radius longer than 10 km, the dry deposition must be taken into account

  15. Radiological impact of atmospheric releases from a coal-fired power station

    Aigueperse, J.; Chalabreysse, J.; Coulon, R.; Grauby, A.; Uzzan, G.


    As the first stage of a study carried out under contract with the Commission of the European Communities for the comparative assessment of the risks to which the individuals of a regional population are exposed, the paper seeks to evaluate atmospheric releases from a coal-fired thermal power station. The station is of traditional design with an installed capacity of 415MW(e) and uses only lignite-type coal produced from a coal basin situated nearby. Gaseous effluents are released from four stacks. The area close to the station is rural in nature: there are a number of small farms, fairly abundant natural vegetation and some fairly well-populated zones with various industries. The main feature of the weather conditions is the strong prevailing winds in the optimum direction. A radiation measurement campaign involving the main 238 U and 232 Th daughter products was carried out focussing on: (1) the coal burnt in the power station; (2) the solid residues resulting from combustion (fly ash, wet ash); (3) gaseous effluents by means of direct sampling from the two release stacks. The information obtained on the releases has made it possible, with the help of dispersion and transfer models, to evaluate the atmospheric concentration of the different radionuclide released as well as their deposition and presence in the biotope in the plant vicinity. The effective dose equivalents received by persons living in the zone of maximum exposure and consuming food produced in that zone were assessed at approximately 7x10 -5 Sv.a -1 at the end of the plant's operating period. Finally, the main radionuclides were measured at a number of points near the plant with the aim of verifying the model evaluations for a particular situation. (author)

  16. Radiological impact of atmospheric releases from a coal-fired power station

    Aigueperse, J; Chalabreysse, J; Coulon, R; Grauby, A [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Protection; Uzzan, G [Association EURATOM-CEA, Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Protection


    As the first stage of a study carried out under contract with the Commission of the European Communities for the comparative assessment of the risks to which the individuals of a regional population are exposed, the paper seeks to evaluate atmospheric releases from a coal-fired thermal power station. The station is of traditional design with an installed capacity of 415MW(e) and uses only lignite-type coal produced from a coal basin situated nearby. Gaseous effluents are released from four stacks. The area close to the station is rural in nature: there are a number of small farms, fairly abundant natural vegetation and some fairly well-populated zones with various industries. The main feature of the weather conditions is the strong prevailing winds in the optimum direction. A radiation measurement campaign involving the main /sup 238/U and /sup 232/Th daughter products was carried out focussing on: (1) the coal burnt in the power station; (2) the solid residues resulting from combustion (fly ash, wet ash); (3) gaseous effluents by means of direct sampling from the two release stacks. The information obtained on the releases has made it possible, with the help of dispersion and transfer models, to evaluate the atmospheric concentration of the different radionuclide released as well as their deposition and presence in the biotope in the plant vicinity. The effective dose equivalents received by persons living in the zone of maximum exposure and consuming food produced in that zone were assessed at approximately 7x10/sup -5/Sv.a/sup -1/ at the end of the plant's operating period. Finally, the main radionuclides were measured at a number of points near the plant with the aim of verifying the model evaluations for a particular situation.

  17. Measurements of nitrous oxide emissions from P.F. fired power stations

    Sloan, S. A.; Laird, C. K.

    Nitrous oxide (N 2O) was measured in the flue gas from four wall-fired and three corner-fired 500 MW boilers, fitted with either conventional or low-NO x burners, at four C.E.G.B. power stations. Measurements were made both by on-line non-dispersive infra red (NDIR) monitors and by extractive sampling for later laboratory analysis by electron capture gas chromatography (ECD GC). It was found that the on-line and laboratory methods were in good agreement for samples analyzed within 1-3 h of sampling, but that the nitrous oxide concentration in the stored samples had a tendency to increase with time, which was dependent on the concentration of water in the sample. Experiments with synthetic mixtures showed that the increase in nitrous oxide concentration was consistent with the overall reaction2NO+SO 2→N 2O+SO 3 in which nitric oxide is reduced by sulphur dioxide. The highest average N 2O concentration measured by the on-line analyzer was 16 vpm, and for most of the boilers monitored the concentration was less than 10 vpm. There was no statistically significant difference between the measured N 2O emissions from normal boilers and those fitted with low-NO x burners. It is suggested that these values are close to the true levels of N 2O emissions from p.f. fired boilers and that recent reports of high levels (up to 200 vpm) are likely to be an artefact resulting from the observed generation of N 2O in stored samples. A consequence of these measurements of N 2O is that current estimates of the contribution of emissions from p.f. fired boilers to the global N 2O budget are likely to be too high.

  18. Power stations

    Cawte, H.; Philpott, E.F.


    The object is to provide a method of operating a dual purpose power station so that the steam supply system is operated at a high load factor. The available steam not required for electricity generation is used to provide process heat and the new feature is that the process plant capacity is determined to make the most economic use of the steam supply system, and not to match the passout capacity of the turbine of the turbogenerator. The product of the process plant should, therefore, be capable of being stored. A dual-purpose power station with a nuclear-powered steam source, turbogenerating means connected to the steam source and steam-powered process plant susceptible to wide variation in its rate of operation is described. (U.K.)

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

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


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

  20. Nuclear techniques for the on-line bulk analysis of carbon in coal-fired power stations.

    Sowerby, B D


    Carbon trading schemes usually require large emitters of CO(2), such as coal-fired power stations, to monitor, report and be audited on their CO(2) emissions. The emission price provides a significant additional incentive for power stations to improve efficiency. In the present paper, previous work on the bulk determination of carbon in coal is reviewed and assessed. The most favourable method is that based on neutron inelastic scattering. The potential role of on-line carbon analysers in improving boiler efficiency and in carbon accounting is discussed.

  1. Natural radionuclides near a coal-fired power station. [/sup 210/Po and /sup 210/Pb levels in cattle livers

    Smith-Briggs, J L; Crick, M J [National Radiological Protection Board, Harwell (UK)


    Previous measurements have shown enhanced levels of /sup 210/Po and /sup 210/Pb from fly ash deposited in the environment around old coal-fired power stations. Preliminary results are presented for levels of /sup 210/Po and /sup 210/Pb in liver samples from cattle which had grazed for two to three years in a field adjacent to a modern power station. No significant difference in the levels of these natural radionuclides was found compared to liver samples obtained from cattle in a control area.

  2. Large-scale straw supplies to existing coal-fired power stations

    Gylling, M.; Parsby, M.; Thellesen, H.Z.; Keller, P.


    It is considered that large-scale supply of straw to power stations and decentral cogeneration plants could open up new economical systems and methods of organization of straw supply in Denmark. This thesis is elucidated and involved constraints are pointed out. The aim is to describe to what extent large-scale straw supply is interesting with regard to monetary savings and available resources. Analyses of models, systems and techniques described in a foregoing project are carried out. It is reckoned that the annual total amount of surplus straw in Denmark is 3.6 million tons. At present, use of straw which is not agricultural is limited to district heating plants with an annual consumption of 2-12 thousand tons. A prerequisite for a significant increase in the use of straw is an annual consumption by power and cogeneration plants of more than 100.000 tons. All aspects of straw management are examined in detail, also in relation to two actual Danish coal-fired plants. The reliability of straw supply is considered. It is concluded that very significant resources of straw are available in Denmark but there remain a number of constraints. Price competitiveness must be considered in relation to other fuels. It is suggested that the use of corn harvests, with whole stems attached (handled as large bales or in the same way as sliced straw alone) as fuel, would result in significant monetary savings in transport and storage especially. An equal status for whole-harvested corn with other forms of biomass fuels, with following changes in taxes and subsidies could possibly reduce constraints on large scale straw fuel supply. (AB) (13 refs.)

  3. Coal-fired power stations - the radiological impact of effluent discharges to atmosphere

    Camplin, W.C.


    An assessment is made of the radiological impact of atmosphere discharges from a hypothetical 2000 MWe power station sited in Great Britain. The exposure pathways considered are external irradiation from the plume and from activity deposited on the ground, inhalation of material in the plume and material resuspended from land surfaces, and ingestion of contaminated foodstuffs. The reduction in radiation exposure due to naturally-occurring 14 C by releases of stable carbon from the power station is also considered. The ingestion pathway is found to result in the highest individual doses, whereas the inhalation pathway makes the dominant contribution to collective dose. The most important radionuclides are 210 Pb, 210 Po and the thorium isotopes 232 Th, 230 Th and 228 Th. For 30 years operation of the power-station, the collective effective dose equivalent commitment truncated to 500 years is estimated to be 340 man Sv. The maximum annual committed effective dose equivalent to an individual is evaluated as 230 μSv, though it is considered improbable that this level of dose would be found in practice. (author)

  4. Projected costs of generating electricity from nuclear and coal-fired power stations for commissioning in 1995


    This report updates and extends the previous NEA study, ''The Costs of Generating Electricity in Nuclear and Coal-fired Power Stations'', published by the OECD in late 1983. Despite the changed expectations concerning coal prices and the considerable movements in exchange rates since the first study was completed, the conclusions remain essentially the same. Nuclear Power is projected to be economically superior by a significant margin to coal-fired plants for base load electricity production in Europe, Japan and some regions of North America. In areas of North America in close proximity to supplies of cheap coal, this would be the more economic fuel, unless future nuclear investment costs can be reduced to match the best US and Canadian experience. In all regions considered, the economic advantage of both coal and nuclear over oil and gas-fired plants for commissioning in the mid-1990s is expected to be substantial. These conclusions are based on an analysis of cost projections for 900 MWe to 1400 MWe Light Water Reactors to be commissioned in 1995, operating at a levelised load factor of about 72 per cent over an assumed 25 years economic life and calculated with a 5 per cent (real) discount rate. This parallels the reference reactor selected for the NEA report ''The Economics of the Nuclear Fuel Cycle'', which was published by the OECD in June 1985, though it deviates somewhat from the reference conditions of the previous generation cost study. Contemporary coal-fired stations ranging in capacity from 330 MWe to 700 MWe with the same assumed economic life and load factor provide the basis for comparison. Some data are included on CANDU Pressurised Heavy Water Reactors, and a brief comment is annexed on the relevance of the comparisons for the smaller plants that may be of interest to countries with smaller electricity networks or where special circumstances apply

  5. Large scale carbon dioxide production from coal-fired power stations for enhanced oil recovery: a new economic feasibility study

    Tontiwachwuthikul, P.; Chan, C. W.; Kritpiphat, W.; Demontigny, D.; Skoropad, D.; Gelowitz, D.; Aroonwilas, A.; Mourits, F.; Wilson, M.; Ward, L.


    The concept of capturing carbon dioxide from fossil-fuelled electric power generating plants and utilizing it as a flooding agent in enhanced oil recovery (EOR) processes, was explored. In this context, this paper describes how cogeneration concepts, together with process optimization strategies, help to reduce the carbon dioxide production cost by utilizing low-pressure steam and waste heat from various sections of the power generation process. Based on these optimization strategies, the recovery cost of carbon dioxide from coal-fired power stations is estimated to be in the range of $ 0.50 to $ 2.00/mscf. Assuming an average cost of $ 1.25/mscf, the production cost of incremental oil would be about $ 18.00. This means that even with today's modest oil prices, there is room for profit to be made operating a carbon dioxide flood with flue gas extracted carbon dioxide

  6. Diagnostics for a coal-fired MHD retrofit of an existing power station

    Cook, R L; Shepard, W S [Mississippi State Univ. (USA). Diagnostic Instrumentation and Analysis Lab.


    MHD flows represent one of the most severe environments encountered by gasdynamic diagnostics. Special state-of-the-art techniques and instrumentation systems are required to monitor and collect data for the MHD components, and these diagnostic systems must operate under very severe environmental and magnetic field conditions. The Diagnostic Instrumentation and Analysis Laboratory (DIAL) at Mississippi State University has developed, and is continuing to develop, advanced optical diagnostic techniques and instrumentation systems to provide nonintrusive, remote real-time measurements and to operate successfully in the industrial-like environment of a large-scale MHD retrofit power station. Such diagnostic instrumentation can provide the information to completely evaluate the performance of individual components, as well as, the entire power plant. It is essential to determine as much detail as possible about the various component operations in an MHD retrofit system so that a commercial plant design can be optimized quickly. This paper discusses the instrumentation systems which DIAL proposed for an MHD retrofit of an existing power station. Instruments which have been making measurements on the U.S. MHD test facilities for several years are presented, along with instruments which will be available within two years. Parameters to be measured along with location and frequency are discussed in detail. These parameters include electron density, electrical conductivity, K-atom density, gas temperature, gas velocity, temperature and velocity profiles, gas composition, and particle size, number, density and distrib00000

  7. Does environmental impact assessment really support technological change? Analyzing alternatives to coal-fired power stations in Denmark

    Lund, H.; Hvelplund, F.


    Danish energy policy calls for development of decentralized, cleaner technologies to replace conventional power stations and, since 1990, aims to reduce CO 2 emissions in 2005 to 20% below their 1988 level. These political goals require a technological change, from conventional, central power stations to cleaner, decentralized technologies such as energy conservation, cogeneration, and renewable energy. In principle, environmental impact assessment (EIA) supports this change on a project-by-project basis. The EU directive on EIA was based on the preventive principle: to eliminate pollution source rather than attempting to counteract it subsequently. According to the Danish implementation of the directive, an EIA must review a project's main alternatives and the environmental consequences of the alternatives. If this were done properly, EIAs could assist Denmark in meeting its CO 2 reduction goals. However, because EIA is implemented on a restricted, regional basis, it does not support technological change. Responsibility for the preparation of the EIA is given to the regional authorities through a law which does not require alternatives to be assessed that extend geographically beyond the boundaries of a regional authority. Thus, there is no certainty of serious analysis of cleaner technology alternatives to large coal-fired power stations. This conclusion is based on examination of three case studies using a participatory research method

  8. The fire at Browns Ferry station



    A cable fire broke out at Browns Ferry-1 and -2 power station when sealing material which had been used as a make-shift seal for a cable duct caught fire in the course of a leakage test with an open light. Both blocks of the power station were scrammed manually so that nobody was injured and no activity was released. On the basis of the information supplied by NRC and TVA (the operator), the IRS has attemped a tentative evaluation of the incident. The results are presented in a summarized version. Note: a detailed description of the incident as published by the operator is available at ZAED. (orig./AK) [de

  9. Fire Power

    Denker, Deb; West, Lee


    For education administrators, campus fires are not only a distressing loss, but also a stark reminder that a campus faces risks that require special vigilance. In many ways, campuses resemble small communities, with areas for living, working and relaxing. A residence hall fire may raise the specter of careless youth, often with the complication of…

  10. Long range transport of fine particle windblown soils and coal fired power station emissions into Hanoi between 2001 to 2008

    Cohen, D.D.; Crawford, J.; Stelcer, E.; Vuong, T.B. [Australian Nuclear Science & Technology Organisation, Kirrawee DC, NSW (Australia)


    Fine particulate matter (PM2.5), source fingerprints and their contributions have been measured and reported previously at Hanoi, Vietnam, from 25 April 2001 to 31 December 2008. In this study back trajectories are used to identify long range transport into Hanoi for two of these sources, namely, windblown dust (Soil) from 12 major deserts in China and emissions from 33 coal fired power plants (Coal) in Vietnam and China. There were 28 days of extreme Soil events with concentrations greater than 6 {mu} g m{sup -3} and 25 days of extreme Coal with concentrations greater than 30 {mu} g m{sup -3} from a total of 748 sampling days during the study period. Through the use of back trajectories it was found that long range transport of soil from the Taklamakan and Gobi desert regions (more than 3000 km to the north west) accounted for 76% of the extreme events for Soil. The three local Vietnamese power stations contributed to 15% of the extreme Coal events, while four Chinese power stations between 300 km and 1700 km to the north-east of Hanoi contributed 50% of the total extreme Coal events measured at the Hanoi sampling site.

  11. Geochemistry of coals, coal ashes and combustion wastes from coal-fired power stations

    Vassilev, S.V.; Vassileva, C.G.


    Contents, concentration trends, and modes of occurrence of 67 elements in coals, coal ashes, and combustion wastes at eleven Bulgarian thermoelectric power stations (TPS) were studied. A number of trace elements in coal and coal ash have concentrations greater than their respective worldwide average contents (Clarke values). Trace elements are concentrated mainly in the heavy accessory minerals and organic matter in coal. In decreasing order of significance, the trace elements in coal may occur as: element-organic compounds; impurities in the mineral matter; major components in the mineral matter; major and impurity components in the inorganic amorphous matter; and elements in the fluid constituent. A number of trace elements in the waste products, similar to coal ashes, exceed known Clarke contents. Trace elements are mainly enriched in non-magnetic, heavy and fine-grained fractions of fly ash. They are commonly present as impurities in the glass phases, and are included in the crystalline components. Their accessory crystalline phases, element-organic compounds, liquid and gas forms, are of subordinate importance. Some elements from the chalcophile, lithophile and siderophile groups may release into the atmosphere during coal burning. For others, the combustion process appears to be a powerful factor causing their relative enrichment in the fly ash and rarely in the bottom ash and slag. 65 refs., 1 fig., 11 tabs

  12. Environmental impact assessment for nuclear and coal-fired power stations in Czechoslovakia

    Lapcik, V.


    Czechoslovakia has had legislation requiring environmental impact assessment since 1992. A methodology for complex evaluation of areas with thermal and nuclear energy sources, as related to ecology and environment, was developed by the staff of the Department of Ecology in accordance with the environmental Protection act (No. 17/1992) for use by the Czech Energy Company (Prague). This methodology will serve as a handbook of environmental impact assessment for the energy industry. Chapter 1 of the handbook describes the project, including information on the site, design, and size of the thermal or nuclear power station. Chapter 2 includes the data necessary to identify and assess the main effects that the project is likely to have on the environment. Chapter 3 describes aspects of the environment likely to be affected significantly by a proposed project, including population, fauna, flora, soil, water, air, climatic factors, material assets (such as architectural and archeological heritage), landscape, and the interrelationship between the above factors. Chapter 4 summarizes the measures envisaged to prevent, reduce, and where possible, offer any significant adverse effects on the environment

  13. Demonstration test of electron beam flue gas treatment pilot plant of a coal fired thermal power station

    Doi, Yoshitaka; Hayashi, Kazuaki; Izutsu, Masahiro; Watanabe, Shigeharu; Namba, Hideki; Tokunaga, Okihiro; Hashimoto, Shoji; Tanaka, Tadashi; Ogura, Yoshimi.


    The Japan Atomic Energy Research Institute, Chubu Electric Power Company and Ebara Corporation jointly constructed a pilot plant for electron beam flue gas treatment (dry process) capable of treating 12,000 m 3 /h (NTP) of flue gas from a coal fired boiler, at Shin-Nagoya Thermal Power Station, Chubu Electric Power Company. Various tests carried out at the plant over a period extending one year verified the followings. By appropriately controlling parameters such as electron beam dosage, flue gas temperature, and ammonia stoichiometric amount, highly efficient simultaneous SO 2 and NOx removal from flue gas was achieved under all gas conditions, equal to or more efficient than that by the highest level conventional treatment. The operation of the pilot plant was stable and trouble-free over a long term, and the operation and the process was easy to operate and control. By-products (ammonium sulfate and ammonium nitrate) produced by the flue gas treatment were proven to have superior quality, equivalent to that of market-available nitrogen fertilizers. These by-products had been registered as by-product nitrogen fertilizers. (author)

  14. HSIP Fire Stations in New Mexico

    Earth Data Analysis Center, University of New Mexico — Fire Stations in New Mexico Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their jobs is...

  15. Efficient power generation from large 7500C heat sources. Application to coal-fired and nuclear power station

    Tilliette, Z.P.; Pierre, B.


    Considering the future concern about a more efficient, rational use of heat sources, and also about a greater location flexibility of power plants owing to dry cooling possibility, closed gas cycles can offer new solutions for fossil or nuclear energy. An efficient heat conversion into power is obtained by the combination of a main non-intercooled helium cycle with a flexible, superheated, low pressure bottoming steam cycle. Emphasis is placed on the matching of the two cycle; for that, a recuperator by-pass arrangement is used. The operation of the main gas turbocompressor does not depend upon the operation of the small steam cycle. Results are given for a conservative turbine inlet temperature of 750 0 C. Applications are made to a coal-fired power plant and to a gas turbine, gas-cooled nuclear reactor. Overall net plant efficiencies of 39 per cent and 46 per cent respectively are reached. For a cycle top temperature equal to 850 0 C, corresponding net efficiencies would be 42 and 49 per cent

  16. An electron beam flue gas treatment plant for a coal fired thermal power station. EBA demonstration plant in Chengdu thermal power station (China EBA Project)

    Doi, Yoshitaka; Nakanishi, Ikuo; Shi, Jingke


    Ebara's electron beam flue gas treatment plant was installed and is being demonstrated in Chengdu Thermal Power Station, Sichuan, China. The demonstration is proving that this plant is fully capable of meeting the target removal of sulfur dioxides from flue gas (flow rate : 300-thousand m 3 /h). Recovered by-products, namely ammonium sulfate and ammonium nitrate, from the treatment were actually tested as fertilizers, the result of which was favorable. The sale and distribution of these by-products are already underway. In May 1995, this plant was presented the certificate of authorization by China's State Power Corporation. It is noted that this was the first time a sulfur dioxide removal plant was certified as such in China. (author)

  17. Advanced optical diagnostics for a coal-fired MHD retrofit of an existing power station

    Shepard, W.S.; Cook, R.L.


    The retrofit concept involves integrating a magnetohydrodynamic (MHD) power generation facility with an existing commercial steam power plant. The MHD power train will be 250 MW t and represents a 5:1 scale-up of existing developmental, proof-of-concept (POC) facilities. The program provides a cost effective way to demonstrate the effectiveness, reliability, and operability of the technology and a basis for future commercialization. An aspect of the program must be to accumulate information on component performance and scale-up relations to enable a smooth transition to commercial plant designs. Special state-of-the-art optical diagnostic instrumentation systems are required for this modern energy conversion technology. In-situ measurements with such systems provide a clearer understanding of the processes involved in the ash/seed-laden MHD gas stream, fundamental scale-up data, performance monitors, and a basis for improved control strategies and control instruments. The types of instrumentation, the measurement locations and frequency, and the benefits for the retrofit program are discussed

  18. Advances in power station construction



    This book is about power stations - specifically about the construction of modern power stations by the Central Electricity Generating Board in England and Wales over the past decade. It describes the work of the CEGB's Generation Development and Construction Division, perhaps better known throughout the world as simply 'Barnwood' where it has its Headquarters in Gloucester, UK. Barnwood was formed in the early 1970s to concentrate the CEGB's then dispersed engineering construction resources to cope with the smaller number but greatly increased size and complexity of modern power station projects. Perhaps uniquely over the ten years since its formation Barnwood has managed the construction of all types of station; coal-fired, oil-fired, nuclear, pumped storage and hydro. This book tells the story of these various projects and gives detailed descriptions of the respective stations. However, it is not intended as a comprehensive description of power station technology. Rather it is intended to convey the scale of such projects and the many decisions and compromises which have to be made in the course of managing their construction

  19. The costs of generating electricity in nuclear and coal fired power stations

    Petroll, M.


    An ad-hoc group of experts for international comparison of electricity generation cost was established in the OECD more than two years ago. This group of experts submitted their report of results in English at the end of last year. This paper publishes an abbreviated version making use of original quotations exclusively in order to keep true to the content of the study as much as possible. The study arrives at the following conclusion: ''There is no uniform set of input data for nuclear and coalfired power plants and assumptions concerning the base parameters of the reactor differ from country to country. Despite these differences, the outcome is that, nuclear energy is cheaper than coal in all countries concerned with the exception of some parts of the United States and Canada.'' (orig./UA) [de

  20. Fire protection in the nuclear power plant

    Takuma, Masao


    According to the publication by US NRC, 32 fires have occurred in the nuclear power stations in operation, but most of them were small fire, and did not affect the safety of the nuclear power stations. The largest fire was that which occurred in the Browns Ferry Nuclear Power Station of TVA, USA, in March, 1976. It did not jeopardize the safety of the reactor facilities, and the leak of radioactive substance did not occur at all. But the investigation was made extensively by the joint committee of both houses, the government and others, and the deficiency in the countermeasures to fire was found, and it was clarified that some revision would by required on the standard applied heretofore. It was the valuable experience for improving further the safety of nuclear power stations. The fire occurred by the ignition of the polyurethane for sealing cable penetrations due to candle flame for testing. About 1600 cables were burned. When fire breaks out in a nuclear power station, it is necessary to stop and cool the reactor without fail, and to prevent the leak of radioactive substances definitely. In case of the fire in Browns Ferry, these requirements were fulfilled satisfactorily. The countermeasures on the basis of the experience in Browns Ferry and the design of the counterplan to fire in nuclear power stations are explained. (Kako, I.)

  1. Reducing nitrogen oxides from power stations

    Scheller, W.


    The report contains 17 individual lectures of the seminar included in databanks. The lectures concern combustion and waste gas measures for reducing the sulfur dioxide and nitrogen oxide emission from coal-fired and gas-fired power stations. (PW) [de

  2. The significance of lead-210, polonium-210 and protactinium-231 in emissions from coal-fired power stations: a comparison with natural environmental sources

    Corbett, J.O.


    Recently published calculations have suggested that a hypothetical individual may receive an effective radiation dose equivalent of 23 mrem/y from coal-fired power station emissions through the ingestion of lead-210, polonium-210 and protactinium-231. It is shown that the model used in those calculations is over-pessimistic by one or two orders of magnitude when applied to the deposition of Pb-210 and Po-210 derived from the decay of radon naturally present in the atmosphere. A more recent assessment of metabolic data for Pa-231 suggests that estimated doses from this nuclide also can be reduced by about a factor of twenty. It is concluded that the maximum effective dose equivalent from power station emissions probably does not exceed 1-2 mrem/y. (author)

  3. Tobruk power station

    Boergardts, B


    In February of 1975, the Electricity Corporation Benghazi (ECB) awarded a contract for the construction of a turnkey power station and seawater desalination plant in Tobruk, Libya to a consortium under the leadership of BBC Mannheim. This power station has an output of 129 MW and supplies about 24,000 m/sup 3/ of drinking water daily. It went into operation in 1977, two and a half years after the contract was awarded.

  4. Large scale carbon dioxide production from coal-fired power stations for enhanced oil recovery : a new economic feasibility study

    Tontiwachwuthikul, P.; Chan, C.W.; Kritpiphat, W.; DeMontigny, D.; Skoropad, D.; Gelowitz, D.; Aroonwilas, A.; Mourits, F.; Wilson, M.; Ward, L.


    A study was conducted to investigate the economics of capturing carbon dioxide from coal-fired power plants to be subsequently used as a flooding agent for enhanced oil recovery (EOR) technologies. It was shown that the production of CO 2 for EOR projects can be technically and economically feasible, particularly when the concepts of cogeneration and optimization are used to reduce steam and electricity expenditures. This is done by using low-pressure steam and waste heat from various sections of the power generation process. It was shown that recovery costs could range between $0.50 to $2.00 per mscf. This translates to a recovered oil price of in the range of $17.39 to $19.95 per bbl., suggesting that even at today's low oil prices there is room for CO 2 flooding with flue gas extracted CO 2 . Practical implications for Saskatchewan were examined. 15 refs., 4 tabs., 7 figs

  5. Pumps for nuclear power stations

    Ogura, Shiro


    16 nuclear power plants are in commercial operation in Japan, and nuclear power generation holds the most important position among various substitute energies. Hereafter also, it is expected that the construction of nuclear power stations will continue because other advantageous energy sources are not found. In this paper, the outline of the pumps used for BWR plants is described. Nuclear power stations tend to be large scale to reduce the construction cost per unit power output, therefore the pumps used are those of large capacity. The conditions to be taken in consideration are high temperature, high pressure, radioactive fluids, high reliability, hydrodynamic performances, aseismatic design, relevant laws and regulations, and quality assurance. Pumps are used for reactor recirculation system, control rod driving hydraulic system, boric acid solution injecting system, reactor coolant purifying system, fuel pool cooling and purifying system, residual heat removing system, low pressure and high pressure core spraying systems, and reactor isolation cooling system, for condensate, feed water, drain and circulating water systems of turbines, for fresh water, sea water, make-up water and fire fighting services, and for radioactive waste treating system. The problems of the pumps used for nuclear power stations are described, for example, the requirement of high reliability, the measures to radioactivity and the aseismatic design. (Kako, I.)

  6. Technoeconomic Assessment of an Advanced Aqueous Ammonia-Based Postcombustion Capture Process Integrated with a 650-MW Coal-Fired Power Station.

    Li, Kangkang; Yu, Hai; Yan, Shuiping; Feron, Paul; Wardhaugh, Leigh; Tade, Moses


    Using a rigorous, rate-based model and a validated economic model, we investigated the technoeconomic performance of an aqueous NH 3 -based CO 2 capture process integrated with a 650-MW coal-fired power station. First, the baseline NH 3 process was explored with the process design of simultaneous capture of CO 2 and SO 2 to replace the conventional FGD unit. This reduced capital investment of the power station by US$425/kW (a 13.1% reduction). Integration of this NH 3 baseline process with the power station takes the CO 2 -avoided cost advantage over the MEA process (US$67.3/tonne vs US$86.4/tonne). We then investigated process modifications of a two-stage absorption, rich-split configuration and interheating stripping to further advance the NH 3 process. The modified process reduced energy consumption by 31.7 MW/h (20.2% reduction) and capital costs by US$55.4 million (6.7% reduction). As a result, the CO 2 -avoided cost fell to $53.2/tonne: a savings of $14.1 and $21.9/tonne CO 2 compared with the NH 3 baseline and advanced MEA process, respectively. The analysis of energy breakdown and cost distribution indicates that the technoeconomic performance of the NH 3 process still has great potential to be improved.

  7. Recent history of sediment metal contamination in Lake Macquarie, Australia, and an assessment of ash handling procedure effectiveness in mitigating metal contamination from coal-fired power stations

    Schneider, Larissa, E-mail: [Institute for Applied Ecology, University of Canberra, Canberra, ACT 2601 (Australia); Maher, William [Institute for Applied Ecology, University of Canberra, Canberra, ACT 2601 (Australia); Potts, Jaimie [New South Wales Office of Environmental and Heritage, Lidcombe, NSW, 2141 Australia (Australia); Gruber, Bernd [Institute for Applied Ecology, University of Canberra, Canberra, ACT 2601 (Australia); Batley, Graeme [CSIRO Land and Water, Lucas Heights, NSW 2234 (Australia); Taylor, Anne [Institute for Applied Ecology, University of Canberra, Canberra, ACT 2601 (Australia); Chariton, Anthony [CSIRO Land and Water, Lucas Heights, NSW 2234 (Australia); Krikowa, Frank [Institute for Applied Ecology, University of Canberra, Canberra, ACT 2601 (Australia); Zawadzki, Atun; Heijnis, Henk [Institute for Environmental Research, Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW 2234 (Australia)


    This study assessed historical changes in metal concentrations in sediments of southern Lake Macquarie resulting from the activities of coal-fired power stations, using a multi-proxy approach which combines {sup 210}Pb, {sup 137}Cs and metal concentrations in sediment cores. Metal concentrations in the lake were on average, Zn: 67 mg/kg, Cu: 15 mg/kg, As: 8 mg/kg, Se: 2 mg/kg, Cd: 1.5 mg/kg, Pb: 8 mg/kg with a maximum of Zn: 280 mg/kg, Cu: 80 mg/kg, As: 21 mg/kg, Se: 5 mg/kg, Cd: 4 mg/kg, Pb: 48 mg/kg. The ratios of measured concentrations in sediment cores to their sediment guidelines were Cd 1.8, As 1.0, Cu 0.5, Pb 0.2 and Zn 0.2, with the highest concern being for cadmium. Of special interest was assessment of the effects of changes in ash handling procedures by the Vales Point power station on the metal concentrations in the sediments. Comparing sediment layers before and after ash handling procedures were implemented, zinc concentrations have decreased 10%, arsenic 37%, selenium 20%, cadmium 38% and lead 14%. An analysis of contaminant depth profiles showed that, after implementation of new ash handling procedures in 1995, selenium and cadmium, the main contaminants in Australian black coal had decreased significantly in this estuary. - Highlights: • The main sources of metals to Southern Lake Macquarie are coal-fired power stations. • The metal of highest concern in this estuary is cadmium. • Arsenic was mobile in sediments. • Selenium and cadmium decreased in sediments following new ash handling procedures.

  8. Recent history of sediment metal contamination in Lake Macquarie, Australia, and an assessment of ash handling procedure effectiveness in mitigating metal contamination from coal-fired power stations

    Schneider, Larissa; Maher, William; Potts, Jaimie; Gruber, Bernd; Batley, Graeme; Taylor, Anne; Chariton, Anthony; Krikowa, Frank; Zawadzki, Atun; Heijnis, Henk


    This study assessed historical changes in metal concentrations in sediments of southern Lake Macquarie resulting from the activities of coal-fired power stations, using a multi-proxy approach which combines 210 Pb, 137 Cs and metal concentrations in sediment cores. Metal concentrations in the lake were on average, Zn: 67 mg/kg, Cu: 15 mg/kg, As: 8 mg/kg, Se: 2 mg/kg, Cd: 1.5 mg/kg, Pb: 8 mg/kg with a maximum of Zn: 280 mg/kg, Cu: 80 mg/kg, As: 21 mg/kg, Se: 5 mg/kg, Cd: 4 mg/kg, Pb: 48 mg/kg. The ratios of measured concentrations in sediment cores to their sediment guidelines were Cd 1.8, As 1.0, Cu 0.5, Pb 0.2 and Zn 0.2, with the highest concern being for cadmium. Of special interest was assessment of the effects of changes in ash handling procedures by the Vales Point power station on the metal concentrations in the sediments. Comparing sediment layers before and after ash handling procedures were implemented, zinc concentrations have decreased 10%, arsenic 37%, selenium 20%, cadmium 38% and lead 14%. An analysis of contaminant depth profiles showed that, after implementation of new ash handling procedures in 1995, selenium and cadmium, the main contaminants in Australian black coal had decreased significantly in this estuary. - Highlights: • The main sources of metals to Southern Lake Macquarie are coal-fired power stations. • The metal of highest concern in this estuary is cadmium. • Arsenic was mobile in sediments. • Selenium and cadmium decreased in sediments following new ash handling procedures

  9. Industrial test and techno-economic analysis of CO2 capture in Huaneng Beijing coal-fired power station

    Huang, Bin; Xu, Shisen; Gao, Shiwang; Liu, Lianbo; Tao, Jiye; Niu, Hongwei; Cai, Ming; Cheng, Jian


    The first industrial-scale CO 2 capture plant in China has been demonstrated at Huaneng Beijing power plant has shown that this technology is a good option for the capture of CO 2 produced by commercial coal-fired power plants. The commissioning and industrial tests are introduced in this paper. The tests show that in the early stages of the passivation phase, the concentration variations of amine, anti-oxidant and Fe 3+ are in the normal range, and the main parameters achieve the design value. The efficiency of the CO 2 capture was about 80-85%, and by the end of January 2009 about 900 tons of CO 2 (99.7%) have been captured. The equipment investment and consumptive costs, including steam, power, solution and others, have been analyzed. The results show: the cost of the absorber and the stripper account for about 50% of main equipment; the consumptive cost is about 25.3 US$ per metric tons of CO 2 , of which the steam requirement accounts for about 55%; the COE increased by 0.02 US$/kW h and the electricity purchase price increased by 29%. (author)

  10. Large-scale resource development in a rural community. The case of Haapavesi peat-fired power station. Kehitysaluekunta suurhankkeen vastaanottajana. Haapaveden turvevoimalan tapaus

    Kiukaanniemi, E.; Joutsenoja, M.


    This case study deals with the effects of an extensive production investment in an economically remote area on its immediate surroundings, i.e. economic repercussions of the peat-fired power plant being built in Haapavesi. The construction of the power station involved a major adaptation problem for the target area. Some 40% of the workforce in 1987 was recruited from the local administrative district, and at the same time thirty new companies were founded, mainly in the service sector. The estimated impact of the future operational phase was assessed using a Keynesian income multiplier model. The estimated effects of the early operational phase in 1991 were calculated to be 262 new jobs in Haapavesi, an increase of 25.6 million FIM in personal incomes and an increase of 4.5 million FIM in local government tax revenues. (20 refs).

  11. The nuclear power station

    Plettner, B.


    The processes taking place in a nuclear power plant and the dangers arising from a nuclear power station are described. The means and methods of controlling, monitoring, and protecting the plant and things that can go wrong are presented. There is also a short discourse on the research carried out in the USA and Germany, aimed at assessing the risks of utilising nuclear energy by means of the incident tree analysis and probability calculations. (DG) [de

  12. Power station instrumentation

    Jervis, M.W.


    Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

  13. Smoke control of fires in subway stations

    Chen, Falin; Guo, Shin-Chang [Institute of Applied Mechanics, National Taiwan University, Taipei, Taiwan 106 (Taiwan); Chuay, He-Yuan [SinoTech Engineering Consulting Co., 171 Nanking E. Road, 5 Sec., Taipei, Taiwan 105 (Taiwan); Chien, Shen-Wen [Department of Fire Science and Administration, National Central Police University, Taoyuan, Taiwan 333 (Taiwan)


    We investigate the effectiveness of the smoke control scheme of the Gong-Guan subway station (GGSS), a typical subway station of the Taipei Rapid Transit System and whose mechanical control systems are also standard in modern subway station design. Three-dimensional smoke flow fields under various kinds of fires are computed by computational fluid dynamics techniques and the results are illustrated on various cross-sectional planes. Results indicate that the stack effect plays a deterministic role in smoke control when a fire occurs near the stairwell; under such circumstances, no mechanical smoke control is necessary. When a fire occurs in other places, such as at the end or the center of the platform, the current mechanical control schemes of GGSS are effective; namely, the smoke can be well controlled, either it is confined to a small region or is evacuated from the station, leaving the four exits free of smoke so that the passengers can escape through them. The effect of the platform edge door (PED) on smoke control is also investigated. With the PED, the effectiveness of the present smoke control system for fires occurring on the chassis of a train, a serious fire in the subway station, increases. We also propose an innovative smoke control scheme with a PED, which turns out to be much more efficient in evacuating smoke than that currently used. This study provides both valuable information for the design of passenger evacuation routes in fires as well as criteria for the design of a smoke control system for subway stations. (orig.)

  14. The emissions of SO{sub 2}, NOx, PM, trace elements and other HAPS of coal-fired power stations in the Netherlands

    R. Meij; B.H. Te Winkel [KEMA Power Generation & Sustainables, Arnhem (Netherlands)


    The emission limit values for coal-fired power stations in the European community and the Netherlands are described and compared in this paper. These limits are discussed in relation to the daily emissions in practice. Most attention is paid to heavy metals and other HAPS. The KEMA TRACE MODEL{reg_sign} can predict these elements fate. It is based on 25 years of research and predicts the distribution of elements over bottom ash, ESP ash, gypsum, emitted flue gases, sludge and effluent of the wastewater treatment plant. Next to this it predicts the composition of ash and flue gases. Wet FGD is the cause of a non-relation between the fuel composition and the emission into air for nearly most elements, except for some volatile elements (boron, bromine, chlorine, fluorine, mercury, iodine, sulphur and selenium). Although the emissions of these volatile elements are low, the concentrations are measured frequently, with emphasis on mercury, chlorine and fluorine. The consequences of co-combustion on emissions into air and the quality of by-products are discussed. The KEMA TRACE MODEL incorporates complicated EU regulations regarding co-combustion (the EU Waste Incineration Directive and the European Waste Catalogue). Modern coal-fired power stations in the Netherlands equipped with high-efficiency ESPs, wet FGD units and some with SCR meet the stringent present Dutch limits. Moreover, the quality of the by-products was such that a 100% of these by-products are sold as building materials. The increasing percentage of co-combustion hardly influences the emissions into air. However, more effort is necessary to maintain the quality of the by-products, but they can still be fully applied.

  15. Physical and chemical processes of sulphur dioxide in the plume from an oil-fired power station

    Flyger, H.; Lewin, E.; Lund Thomsen, E.; Fenger, J.; Lyck, E.; Gryning, S.E.


    The Danish contribution to the EUROCOP COST 61a project is described. Work concerned the physical and chemical reactions of sulphur dioxide released from a power station. The investigation was based on the application of two tracers. Inactive, inert SF 6 is used to monitor the dispersion of and deposition from the plume; it was intended to use radioactive 35 SO 2 to determine the degree of oxidation of sulphur released from the stack; so far, however, public reaction has prevented the use of a release of activity in field experiments. The report describes the construction and testing of airborne instruments for continuous registration of sulphur dioxide, nitrogen oxides, ozone and the tracer SF 6 , as well as for measurements of temperature and humidity. Sulphur samples were collected on filter paper in a specially constructed low volume air sampler, and the subsequent chemical analysis in the laboratory is described. Finally, the problem of navigation is treated. It is shown that nitrogen oxides may be used as an internal tracer in plume experiments. Preliminary experiments based on inactive analysis only indicated an overall half-life for SO 2 in the plume of about half an hour. (author)

  16. Wind turbine power stations



    The Countryside Council for Wales (CCW's) policy on wind turbine power stations needs to be read in the context of CCW's document Energy:Policy and perspectives for the Welsh countryside. This identifies four levels of action aimed at reducing emission of gases which contribute towards the risk of global warming and gases which cause acid deposition. These are: the need for investment in energy efficiency; the need for investment in conventional power generation in order to meet the highest environmental standards; the need for investment in renewable energy; and the need to use land use transportation policies and decisions to ensure energy efficiency and energy conservation. CCW views wind turbine power stations, along with other renewable energy systems, within this framework. CCW's policy is to welcome the exploitation of renewable energy sources as an element in a complete and environmentally sensitive energy policy, subject to the Environmental Assessment of individual schemes and monitoring of the long-term impact of the various technologies involved. (Author)

  17. Principles of nuclear power station control

    Knowles, J.B.


    This memorandum represents lecture notes first distributed as part of a UKAEA introductory course on Reactor Technology held during November 1975. A nuclear power station is only one element of a dispersed interconnected arrangement of other nuclear and fossil-fired units which together constitute the national 'grid'. Thus the control of any one station must relate to the objectives of the grid network as a whole. A precise control of the supply frequency of the grid is achieved by regulating the output power of individual stations, and it is necessary for each station to be stable when operating in isolation with a variable load. As regards individual stations, several special control problems concerned with individual plant items are discussed, such as: controlled reactivity insertions, temperature reactivity time constants and flow instability. A simplified analysis establishes a fundamental relationship between the stored thermal energy of a boiler unit (a function of mechanical construction) and the flexibility of the heat source (nuclear or fossil-fired) if the station is to cope satisfactorily with demands arising from unscheduled losses of other generating sets or transmission capacity. Two basic control schemes for power station operation are described known as 'coupled' and 'decoupled control'. Each of the control modes has its own merits, which depend on the proposed station operating strategy (base load or load following) and the nature of the heat source. (U.K.)

  18. Flame visualization in power stations

    Hulshof, H J.M.; Thus, A W; Verhage, A J.L. [KEMA - Fossil Power Plants, Arnhem (Netherlands)


    The shapes and temperature of flames in power stations, fired with powder coal and gas, have been measured optically. Spectral information in the visible and near infrared is used. Coal flames are visualized in the blue part of the spectrum, natural gas flames are viewed in the light of CH-emission. Temperatures of flames are derived from the best fit of the Planck-curve to the thermal radiation spectrum of coal and char, or to that of soot in the case of gas flames. A measuring method for the velocity distribution inside a gas flame is presented, employing pulsed alkali salt injection. It has been tested on a 100 kW natural gas flame. 3 refs., 9 figs.

  19. Controversial power station

    Marcan, P.


    When information on plans to build a power station in Trebisov first appeared reactions differed. A 40-billion investment in a town with more than 20% unemployment seemed attractive. But some people did not like the idea of having a power plant located in the town. Around one year after the investment was officially announced TREND returned to Trebisov. In the meantime the investor has managed to overcome one of the biggest obstacles on its way to building a new power plant. The ministry responsible gave the environmental study a positive rating. But objectors are still not sure that everything is fine. They claim that the study misinterprets data and that the ministry did not show expertise when evaluating it. 'Is it possible that a coal power plant located in a town would have twice as many positive effects on peoples' health than negative ones? Why don't we build them everywhere?'asked the chairman of the civic society, Trebisov nahlas, Gejza Gore. The developer of the project, Ceskoslovenska energeticka spolocnost (CES), Kosice is fighting back and claims that their counterpart lacks professional arguments. In the meantime it is preparing for area management proceedings. Trebisov is also involved in the discussion and claims that the town planning scheme does not include such a project. The Ministry of Construction has a different opinion. In the opinion of the Ministry the town planning scheme allows a 885-megawatt power plant to be built only a few hundred meters away from housing estates. (author)

  20. Technical and Energy Performance of an Advanced, Aqueous Ammonia-Based CO2 Capture Technology for a 500 MW Coal-Fired Power Station.

    Li, Kangkang; Yu, Hai; Feron, Paul; Tade, Moses; Wardhaugh, Leigh


    Using a rate-based model, we assessed the technical feasibility and energy performance of an advanced aqueous-ammonia-based postcombustion capture process integrated with a coal-fired power station. The capture process consists of three identical process trains in parallel, each containing a CO2 capture unit, an NH3 recycling unit, a water separation unit, and a CO2 compressor. A sensitivity study of important parameters, such as NH3 concentration, lean CO2 loading, and stripper pressure, was performed to minimize the energy consumption involved in the CO2 capture process. Process modifications of the rich-split process and the interheating process were investigated to further reduce the solvent regeneration energy. The integrated capture system was then evaluated in terms of the mass balance and the energy consumption of each unit. The results show that our advanced ammonia process is technically feasible and energy-competitive, with a low net power-plant efficiency penalty of 7.7%.

  1. Bradwell Nuclear Power Station


    When built, the Magnox reactors were expected to have operating lifetimes of 20-25 years. In order to satisfy the licensing authorities of their continued safety, long term safety reviews (LTSRs) are being carried out as the reactors reach 20 years of operation. This is the Nuclear Installations Inspectorate's (NII) summary report on Bradwell nuclear power station. The objectives of the LTSR are stated. A description of the plant is followed by an explanation of the statutory position on licensing. The responsibilities of the Central Electricity Generating Board (CEGB) and the NII are defined. From the examination of the CEGB's LTSR it is concluded that this generally confirms the validity of the existing safety case for present operation. However, some recommendations are made as to work required for reactor operation up to 1992. A summary of the NII findings is presented. This includes the reactor pressure circuit integrity, effects of ageing and in-service wear and radiation doses. (U.K.)

  2. Prediction of unburned carbon and NOx in a tangentially fired power station using single coals and blends

    R.I. Backreedy; J.M. Jones; L. Ma; M. Pourkashanian; A. Williams; A. Arenillas; B. Arias; J.J. Pis; F. Rubiera [University of Leeds, Leeds (United Kingdom). Energy and Resources Research Institute


    Two approaches can be employed for prediction of NOx and unburned carbon. The first approach uses global models such as the 'slice' model which requires the combustor reaction conditions as an input but which has a detailed coal combustion mechanism. The second involves a computational fluid dynamic model that in principle can give detailed information about all aspects of combustion, but usually is restricted in the detail of the combustion model because of the heavy computational demands. The slice model approach can be seen to be complimentary to the CFD approach since the NOx and carbon burnout is computed using the slice model as a post-processor to the CFD model computation. The slice model that has been used previously by our group is applied to a commercial tangentially fired combustor operated in Spain and using a range of Spanish coals and imported coals, some of which are fired as blends. The computed results are compared with experimental measurements, and the accuracy of the approach assessed. The CFD model applied to this case is one of the commercial codes modified to use a number of coal combustion sub-models developed by our group. In particular it can use two independent streams of coal and as such it can be used for the combustion of coal blends. The results show that both model approaches can give good predictions of the NOx and carbon in ash despite the fact that certain parts of the coal combustion models are not exactly the same. However, if a detailed insight into the combustor behaviour is required then the CFD model must be used. 28 refs., 4 figs., 6 tabs.

  3. Discharges from nuclear power stations


    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

  4. Mercury concentrations in water resources potentially impacted by coal-fired power stations and artisanal gold mining in Mpumalanga, South Africa.

    Williams, Chavon R; Leaner, Joy J; Nel, Jaco M; Somerset, Vernon S


    Total mercury (TotHg) and methylmercury (MeHg) concentrations were determined in various environmental compartments collected from water resources of three Water Management Areas (WMAs) - viz. Olifants, Upper Vaal and Inkomati WMAs, potentially impacted by major anthropogenic mercury (Hg) sources (i.e coal-fired power stations and artisanal gold mining activities). Aqueous TotHg concentrations were found to be elevated above the global average (5.0 ng/L) in 38% of all aqueous samples, while aqueous MeHg concentrations ranged from below the detection limit (0.02 ng/L) to 2.73 +/- 0.10 ng/L. Total Hg concentrations in surface sediment (0-4 cm) ranged from 0.75 +/- 0.01 to 358.23 +/- 76.83 ng/g wet weight (ww). Methylmercury accounted for, on average, 24% of TotHg concentrations in sediment. Methylmercury concentrations were not correlated with TotHg concentrations or organic content in sediment. The concentration of MeHg in invertebrates and fish were highest in the Inkomati WMA and, furthermore, measured just below the US EPA guideline for MeHg in fish.

  5. Risk of fire and dust explosions analysis in thermal Power station of ''As Pontes''; Analisis del Riesgo de fuego y Explosion en la Central Termica As Pontes



    Among the numerous difficulties come up in the industrial processes that operate with coal, the handling of combustible solids constitutes a priority objective because of the potential risk of fire and dust explosions that implies. The aim of this project was to determine the coal usage conditions that assure total safety in its manipulation avoiding every risks at the Thermal Power Station. Several variables had to be considered starting with the basis concept of coal, which ranges very different types, compositions and origins and studying the coal handling and operation condition on different areas in the Thermal Power Station. (Author)

  6. Combination of a pyrolysis plant with a hard coal power station firing system; Kombination einer Pyrolyseanlage mit einer Steinkohlekraftwerksfeuerung

    Schulz, W.; Hauk, R. [Vereinigte Elektrizitaetswerke Westfalen AG (VEW), Dortmund (Germany)


    VEW ENERGIE AG plans and operates power plants and thermal plants for the disposal of residual materials (e.g. household waste, sewage sludge, used wood, residues from paper manufacture). In order to make itself familiar with the market for secondary fuels the company undertook a study to find out what cost-effective techniques are available on the market and how power plants can be used for optimal energy use and with a minimum of disposal costs. Its choice finally fell on pyrolysis because this technology is the most flexible for the thermal and physical utilisation of substitute fuels. Moreover, pyrolysis combines very well with power plants. [Deutsch] VEW ENERGIE AG plant und betreibt Kraftwerke und thermische Anlagen zur Entsorgung von Reststoffen (z.B. Hausmuell, Klaerschlamm, Altholz, Reststoff aus der Papierherstellung). Um sich auf dem Markt der Ersatzbrennstoffe einzustellen, wurde untersucht, welche kostenguenstigen Techniken auf dem Markt verfuegbar sind und wie Kraftwerke zur optimalen Energienutzung und zur Minimierung der Entsorgungskosten eingesetzt werden koennen. Die Pyrolysetechnik wurde ausgewaehlt, weil sie am flexibelsten fuer die thermische und stoffliche Verwertung der Ersatzbrennstoffe ist. Sie laesst sich auch sehr gut mit Kraftwerken kombinieren. (orig.)

  7. Torness: proposed nuclear power station



    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  8. Islands for nuclear power stations

    Usher, E.F.F.W.; Fraser, A.P.


    The safety principles, design criteria and types of artificial island for an offshore nuclear power station are discussed with particular reference to siting adjacent to an industrial island. The paper concludes that the engineering problems are soluble and that offshore nuclear power stations will eventually be built but that much fundamental work is still required. (author)

  9. Nuclear power stations licensing

    Solito, J.


    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

  10. Fire scenarios in nuclear power plant

    Asp, I.B.; MacDougall, E.A.; Hall, R.E.


    This report defines a Design Base Fire and looks at 3 major areas of a hypothetical model for a Nuclear Power Plant. In each of these areas a Design Base Fire was developed and explained. In addition, guidance is given for comparing fire conditions of a given Nuclear Power Plant with the model plant described. Since there is such a wide variation in nuclear plant layouts, model areas were chosen for simplicity. The areas were not patterned after any existing plant area; rather several plant layouts were reviewed and a simplified model developed. The developed models considered several types of fires. The fire selected was considered to be the dominant one for the case in point. In general, the dominant fire selected is time dependent and starts at a specific location. After these models were developed, a comparison was drawn between the model and an operating plant for items such as area, cable numbers and weight, tray sizes and lengths. The heat loads of the model plant are summarized by area and compared with those of an actual operating plant. This document is intended to be used as a guide in the evaluation of fire hazards in nuclear power stations and a summarization of one acceptable analytical methodology to accomplish this

  11. The Trencin water power station


    This leaflet describes the Trencin water power station. The Trencin water power station was built seven years after the Dubnica nad Vahom water power station started its operation and was the last stage of the first and the oldest derived cascade of water power stations on the Vah River. After completing water power stations at Ladce (1936), Ilava (1946) and Dubnica nad Vahom (1949) and before constructing the Trencin water power station, the whole second derived cascade of water power stations including water power stations at Kostolna, Nove Mesto nad Vahom and Horna Streda was built as soon as possible mainly because the need to get compensation for discontinued electricity supplies as well as energetic coal from the Czech Republic. Hereby, experiences from the construction of previous grades were used, mainly as far as the dimensioning was concerned, as the fi rst installed power stations had, in comparison with the growing requirements on the electricity supplies, very low absorption capacity - only 150 m 3 .s -1 . Thus the Trencin power station (original name was the Skalka power station) was already dimensioned for the same absorption capacity as the cascade located downstream the river, that is 180 m 3 .s -1 . That was related also to growing demands on electricity supplies during the peaks in the daily electric system load diagram, and thus to the transfer from continuous operation of the water power station to semi-peak or even peak performance. According to the standards of power station classification, the Trencin water power station is a medium size, low pressure, channel power station with two units equipped by Kaplan turbines and synchronous hydro-alternators. The water power station installed capacity is 16.1 MW in total and its designed annual production of electrical energy for medium water year is 85,000 MWh, while the average annual production during the last 30 years is 86,252 MWh. Installed unit has a four-blade Kaplan turbine with the diameter

  12. Dose assessment of natural radioactivity in fly ash and environmental materials from Morupule a coal-fired power station in Botswana

    Mudiwa, J


    This study has been undertaken to estimate the occupational and public radiation doses due to natural radioactivity at Morupule, a Coal-Fired Power Station and its environs. The radiation doses were reconstructed to include 60 year period from 1985 to 2045. Direct gamma ray spectroscopy was used to determine the natural radionuclides Th-232, U-238, and K-40 both qualitatively and quantitatively for fly ash, coal, soil and water (from the fly ash ponds) samples. The average activity concentrations for Th-232, U-238, and K-40 in fly ash samples were 64.54 Bq/kg, 49.37 Bq/kg and 40.08 Bq/kg respectively. In the case of coal, the corresponding average activity concentrations for Th-232, U-238, and K-40 were 27.43 Bq/kg, 18.10 Bq/kg and 17.38 Bq/kg respectively. For soil samples, the average activity concentrations for Th-232, U-238, and K-40 were 10.11 Bq/kg, 6.76 Bq/kg and 118.03 Bq/kg respectively. In water samples, the average activity concentrations for Th-232, U-238, and K-40 were 0.79 Bq/l, 0.32 Bq/l and 1.01 Bq/l respectively. These average activity concentrations were generally comparable to the average world activity concentrations in the case of coal samples, but were generally lower than the average world activity concentrations in the case of fly ash, soil and water samples. The average annual effective doses for the study area were estimated as 0.320 mSv, 0.126 mSv, 0.069 mSv and 0.003 mSv for fly ash, coal, soil and water samples respectively. Dose reconstruction modelling estimated the average fly ash annual effective doses for the years 1985, 1995, 2005, 2015, 2025, 2035 and 2045 to be 0.182 mSv, 0.459 mSv, 0.756 mSv, 0.320 mSv, 0.183 mSv, 0.137 mSv and 0.124 mSv respectively. The reconstructed average coal annual effective doses for similar years were 0.070 mSv, 0.182 mSv, 0.303 mSv, 0.126 mSv, 0.070 mSv, 0.060 mSv and 0.046 mSv respectively. The dose reconstruction modelling also estimated the average soil annual effective doses for the same years as

  13. Maintenance of fire systems and equipment at Virginia Power

    Doubrely, E.B. Jr.


    The basics of fire protection systems maintenance are well codified and documented in the National Fire Codes published by the National Fire Protection Association. In addition, Insurers often promulgate minimum standards for fire protection systems design and maintenance to which they attach conditions of insurability. Regulatory agencies and even in-house corporate policies can impact the maintenance of fire protection systems and equipment. This presentation will focus on the various methods and alternate ways of performing system maintenance, whether required by code, insurer, or by some regulatory commitment at Virginia Powers North Anna and Surry nuclear power stations. The approach to performing similar work is handled differently at each station. This difference can be attributed to proximity to outside assistance as well as plant philosophy. In addition to station maintenance practices, a discussion of in-house servicing of portable fire suppression equipment is offered. 1 tab

  14. Services for nuclear power stations

    Fremann, M.; Ryckelynck


    This article gives an information as complete as possible about the activities of the french nuclear industry on the export-market. It describes the equipment and services available in the field of services for nuclear power stations [fr

  15. Fire protection in power plants

    Penot, J.


    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. [de

  16. The Miksova water power station


    This leaflet describes the Miksova water power station. The Miksova water power station is part of the second derived cascade of hydro power stations on the river Vah. It was built at the end of a huge development in Slovak hydro-energy in the late 1950's and the beginning of the 1960's. It is the second water power station on this derived cascade, which is situated downstream the Hricov reservoir and water power station. At the power station, three turbine sets with vertical Kaplan turbines are installed with a total power output of 3 x 31.2 = 93.6 MW. With this power output the Miksova water power station (Miksova I) was the biggest water power station in the Slovak Republic until the construction of Pumping water power station Liptovska Mara. And it is still the biggest channel water power station on the Vah so far. It was put into operation during the period 1963 to 1965. There are three turbine sets with Kaplan turbines from CKD Blansko, with a synchronous hydro-alternator installed in the power station. Their installed capacity is 93.6 MW in total and the projected annual production of electrical energy is 207 GWh. The turbines are fi ve-bladed (on the Hricov and Povazska Bystrica water power stations they are four-bladed) and the impeller wheel has a diameter of 4800 mm. They are designed for extension of the head from 24.1 to 22.21 m and each of them has an absorption capacity of 134 m 3 .s -1 nd a nominal operating speed of 2.08 m 3 .s -1 , runaway speed 4.9 m 3 .s -1 . Each synchronous hydro-alternator has a maximum power output of 31.2 MW, a nominal voltage of 10.5 kV and power factor cos φ of 0.8. Power from the power station is led out through 110 kV switchgear. The water power station operates under automatic turbine mode of operation with remote indication and control from the Dispatch Centre at Vodne elektrarne, in Trencin. From start of operation until the end of 2003 all three turbine sets operated for a total of 450,500 running hours and the

  17. The economic consequences of the Sizewell 'B' nuclear power station

    Fothergill, S.; Gudgin, G.; Mason, N.


    The subject is covered in chapters, entitled: introduction (the background to Sizewell 'B'); policy options (Sizewell 'B'; a new coal-fired station; the no-new-station option; a PWR programme); economic framework (direct effects; financing; final macroeconomic effects); the construction phase (capital costs; direct effects; final effects; summary); the operating phase (a new power station as a replacement for older stations; the period of base-load operation; the later years of operation; summary); conclusions and policy recommendations. The first recommendation is that if a new power station is built it should be a coal-fired station rather than a PWR. The second recommendation is that if a new coal station is built there is a case for building it early, ahead of demand. (U.K.)

  18. Balakovo nuclear power station


    A key means of improving the safety and reliability of nuclear power plants is through effective training of plant personnel. The goal of this paper is to show the progress of the training at the Balakovo Nuclear Power Plant, and the important role that international cooperation programs have played in that progress

  19. Prevention of cable fires in nuclear power plants

    Murota, George; Yajima, Kazuo


    Nuclear power generation is indispensable to secure required electric power, therefore double or triple safety measures are necessary to prevent serious accidents absolutely. As for the countermeasures to cable fires, interest grew rapidly with the fire in Browns Ferry Power Station in USA in 1975 as the turning point, because multi-strand grouped cables caused to promote the spread of fire. In Japan, also the fire prevention measures for wires and cables were more strengthened, and the measures for preventing the spread of cable fires with the agent preventing the spread of fires have occupied the important position. When multi-strand cables are ignited by some cause, the fire spreads with very large combustion force along wirings to other rooms and installations, and electric systems are broken down. The harmful corrosive gas generated from the burning coating materials of cables diffuses very quickly. In nuclear power stations, the cables which are very hard to burn are adopted, fire prevention sections are established positively, the fire-resisting capability of fire prevention barriers is reviewed, and fire-resisting and smoke-preventing treatments are applied to the parts where cables penetrate walls, floors or ceilings. The paint and the sealing material which prevent the spread of fires are introduced. (Kako, I.)

  20. The Paks Nuclear Power Station

    Erdosi, N.; Szabo, L.


    As the first stage in the construction of the Paks Nuclear Power Station, two units of 440 MW(e) each will be built. They are operated with two coolant loops each. The reactor units are VVER 440 type water-moderated PWR type heterogeneous power reactors designed in the Soviet Union and manufactured in Czechoslovakia. Each unit operates two Soviet-made K-220-44 steam turbines and Hungarian-made generators of an effective output of 220 MW. The output of the transformer units - also of Hungarian made - is 270 MVA. The radiation protection system of the nuclear power station is described. Protection against system failures is accomplished by specially designed equipment and security measures especially within the primary circuit. Some data on the power station under construction are given. (R.P.)

  1. Power station simulators



    The number and the variety of simulators have gown to such an extent that it has become necessary to classify the numerous types now available. Simulators are of paramount importance for the design of nuclear power plants, for optimizing their efficiency and for the training of their operators: factors that contribute to their overall security. This book contains chapters on the following subjects: the development of power plant simulators, the components and classification of simulators, simulator technology, simulator performance and problems in simulator training

  2. Process instrumentation for nuclear power station

    Yanai, Katsuya; Shinohara, Katsuhiko


    Nuclear power stations are the large scale compound system composed of many process systems. Accordingly, for the safe and high reliability operation of the plants, it is necessary to grasp the conditions of respective processes exactly and control the operation correctly. For this purpose, the process instrumentation undertakes the important function to monitor the plant operation. Hitachi Ltd. has exerted ceaseless efforts since long before to establish the basic technology for the process instrumentation in nuclear power stations, to develop and improve hardwares of high reliability, and to establish the quality control system. As for the features of the process instrumentation in nuclear power stations, the enormous quantity of measurement, the diversity of measured variables, the remote measurement and monitoring method, and the ensuring of high reliability are enumerated. Also the hardwares must withstand earthquakes, loss of coolant accidents, radiations, leaks and fires. Hitachi Unitrol Sigma Series is the measurement system which is suitable to the general process instrumentation in nuclear power stations, and satisfies sufficiently the basic requirements described above. It has various features as the nuclear energy system, such as high reliability by the use of ICs, the methods of calculation and transmission considering signal linkage, loop controller system and small size. HIACS-1000 Series is the analog controller of high reliability for water control. (Kako, I.)

  3. A study of operation of station fire brigade with comparison for Japan and the U.S

    Ichiki, Kuniyasu


    With the occurrence of a fire at Kashiwazaki Kariwa No. 3 unit on a site transformer when Niigata Chuetsu Offshore Earthquake occurred in 2007, the movement of establishing station fire brigade broke out all over Japan. Fire brigade of U.S. power stations is an organization structured with the standards of clear requirements. Some of station fire event reports include examples of activation of station fire brigade. Preparing station fire brigade with good expertise is quite meaningful on the viewpoint of ruling out significant threats of fire against nuclear safety, such as Browns Ferry station fire occurred in 1975. The purpose of this study is to extract useful knowledge through making research on examples of operations of station fire brigade of both Japan and the U.S. As for fire occurrence, relatively frequent fires are seen at Japanese stations with miscellaneous components or some material for works. In the U.S., on the other hand, we can identify relatively frequent fires occurred with important equipment. This might make fire brigades of the U.S. well-prepared for fire fighting by establishing fire-coping strategies for every location in the station. Also, in some stations, fire brigade is continuously trained to enhance its firefighting and rescuing abilities. With the aspect of training of brigades, they are often assembled with devoted staff, which enable them acquiring frequent training and educations to improve their skills further. Fire fighting and rescuing are inevitably dangerous task. This is why frequent training is essential in order to prevent injuries and to keep up their motivation. Unfortunately, the circumstance for brigades in Japan is not helpful enough in experiencing special training needed for them. We have to figure out some way to get over such disadvantages. (author)

  4. Space Station power system issues

    Giudici, R.J.


    Issues governing the selection of power systems for long-term manned Space Stations intended solely for earth orbital missions are covered briefly, drawing on trade study results from both in-house and contracted studies that have been conducted over nearly two decades. An involvement, from the Program Development Office at MSFC, with current Space Station concepts began in late 1982 with the NASA-wide Systems Definition Working Group and continued throughout 1984 in support of various planning activities. The premise for this discussion is that, within the confines of the current Space Station concept, there is good reason to consider photovoltaic power systems to be a venerable technology option for both the initial 75 kW and 300 kW (or much greater) growth stations. The issue of large physical size required by photovoltaic power systems is presented considering mass, atmospheric drag, launch packaging and power transmission voltage as being possible practicality limitations. The validity of searching for a cross-over point necessitating the introduction of solar thermal or nuclear power system options as enabling technologies is considered with reference to programs ranging from the 4.8 kW Skylab to the 9.5 gW Space Power Satellite

  5. Monitoring of nuclear power stations

    Ull, E.; Labudda, H.J.


    The purpose of the invention is to create a process for undelayed automated detection and monitoring of accidents in the operation of nuclear power stations. According to the invention, this problem is solved by the relevant local measurements, such as radiation dose, components and type of radiation and additional relevant meteorological parameters being collected by means of wellknown data collection platforms, these being transmitted via transmission channels by means of satellites to suitable worldwide situated receiving stations on the ground, being processed there and being evaluated to recognise accidents. The local data collection platforms are used in the immediate vicinity of the nuclear power station. The use of aircraft, ships and balloons as data collection systems is also intended. (HWJ)

  6. Some retrofit considerations for revitalizing and upgrading the Oji-River coal-fired thermal power station for service in 21st century Nigeria

    Oguejofor, G.C. [Nnamdi Azikiwe University, Awka (Nigeria). Faculty of Engineering & Technology, Dept. of Chemical Engineering


    The aim of this article is to show that in the context of sustainable development, coal and its downstream power generation industry could complement petroleum and hydroelectric industries in the national power generation scheme. The continued utilization of coal in power generation schemes in the world as well as environmental pollution caused by other fossil fuels were examined. These were presented as justifications for the proposed reintegration of coal as a complement to hydropower and oil/gas sources of electric energy in Nigeria. The scheme of power generation in the Oji-River thermal station was reviewed to enhance the appreciation of the retrofit models to be presented for the revitalization of the plant. Subsequently, two sustainable development retrofit models were considered for the revitalization of the Oji-River thermal power station and enhanced industrial civilization of the Oji neighbourhood. To ensure self-sufficiency, the paper shows how the two retrofit models depend on abundant locally available resources, namely, coal, limestone, water and air.

  7. Merchant funding for power stations

    Johnston, B.; Bartlam, M.


    The next frontier for project finance is merchant generation: the financing of IPPs without long-term offtake contracts. Banks are just beginning to finance merchant generation power stations. One of the first was Destec's Indian Queens project in Cornwall, UK. Bruce Johnston and Martin Bartlam of Wilde Sapte discuss the project. (UK)

  8. FIRE

    Brtis, J.S.; Hausheer, T.G.


    FIRE, a microcomputer based program to assist engineers in reviewing and documenting the fire protection impact of design changes has been developed. Acting as an electronic consultant, FIRE is designed to work with an experienced nuclear system engineer, who may not have any detailed fire protection expertise. FIRE helps the engineer to decide if a modification might adversely affect the fire protection design of the station. Since its first development, FIRE has been customized to reflect the fire protection philosophy of the Commonwealth Edison Company. That program is in early production use. This paper discusses the FIRE program in light of its being a useful application of expert system technologies in the power industry

  9. 46 CFR 132.130 - Fire stations.


    ... a single length of hose. (b) Each part of the main machinery space, including the shaft alley if it... to protect its hose from heavy weather. (n) Each section of fire hose must be lined commercial fire...

  10. Power station stack gas emissions

    Hunwick, Richard J.


    There are increasing awareness and pressure to reduce emissions of acid rain and photochemical smog. There is a need to produce new control system and equipment to capture those emissions. The most visible form of pollutions are the chimney smoke, dust and particles of fly ash from mineral matter in the fuel. Acid gases are hard on structures and objects containing limestone. Coal fired power generation is likely to be able to sustain its competitive advantage as a clean source of electricity in comparison with nuclear power and natural gas

  11. Reviewing nuclear power station achievement

    Howles, L.R.


    For measurement of nuclear power station achievement against original purchase the usual gross output figures are of little value since the term loosely covers many different definitions. An authentically designed output figure has been established which relates to net design output plus house load at full load. Based on these figures both cumulative and moving annual load factors are measured, the latter measuring the achievement over the last year, thus showing trends with time. Calculations have been carried out for all nuclear stations in the Western World with 150 MW(e) gross design output and above. From these are shown: moving annual load factor indicating relative station achievements for all the plants; cumulative load factors from which return of investment can be calculated; average moving annual load factors for the four types of system Magnox, PWR, HWR, and BWR; and a relative comparison of achievement by country in a few cases. (U.K.)

  12. Decommissioning of nuclear power stations

    Gregory, A.R.


    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  13. 20 years of power station master training

    Schwarz, O.


    In the early fifties, the VGB working group 'Power station master training' elaborated plans for systematic and uniform training of power station operating personnel. In 1957, the first power station master course was held. In the meantime, 1.720 power station masters are in possession of a master's certificate of a chamber of commerce and trade. Furthermore, 53 power station masters have recently obtained in courses of the 'Kraftwerksschule e.V.' the know-how which enables them to also carry out their duty as a master in nuclear power stations. (orig.) [de

  14. Slovak power stations (Annual report 1997)


    A brief account of activities carried out by the Slovak power stations, s.a. (SE) in 1997 is presented. These activities are reported under the headings: (1) Foreword of the chairman of the Board of directors; (2) Highlights of 1997; (3) Board of directors; (4) Supervisory board; (5) Organisation structure of SE; (6) Branches of SE; (7) Auditor's report; (8) Balance sheet / Economic balance; (9) Economic results; (10) Analysis of economic result; (11) SE capital investment in other trade companies; (12) Basic data; (13) Management and operation of the Slovak Republic's power system; (14) Labour safety and health, fire protection; (15) Electricity trade; (16) Trade heat; (17) Customer services provided to electricity users (18) Investment programme; (19) Environmental protection; (20) Support of renewable; (21) Nuclear safety; (22) Quality system; (23) International co-operation; (24) Centrel; (25) Information technology; (26) Public relations; (27) Business strategy and development programme; (28) Strategic change programme

  15. Fire models for assessment of nuclear power plant fires

    Nicolette, V.F.; Nowlen, S.P.


    This paper reviews the state-of-the-art in available fire models for the assessment of nuclear power plants fires. The advantages and disadvantages of three basic types of fire models (zone, field, and control volume) and Sandia's experience with these models will be discussed. It is shown that the type of fire model selected to solve a particular problem should be based on the information that is required. Areas of concern which relate to all nuclear power plant fire models are identified. 17 refs., 6 figs

  16. Fire protection in nuclear power plants


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

  17. Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

    Lambright, J.A.; Cerjak, J.; Spiler, J.; Ioannidi, J.


    Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

  18. Practical experience with own monitoring of clay sealings on dumps for brown coal-fired power station residues. Erfahrungen mit der Eigenueberwachung an Tonabdichtungen der Deponien fuer Braunkohlenkraftwerksrueckstaende

    Winter, K


    In order to dispose of power station residues Rheinbraun erects dumps which are encased by a clay sealing. For the Fortuna dump 10 hectares sealing area, with a permeability that is lower than the required limit value of k = 5x10{sup -10} m/s, have so far been constructed. The quality of the sealing is monitored and ensured by graded checking. The practical experience gained so far with own monitoring (selection of material, supervision of construction site and own checking) on the finished clay sealings is discussed in the present paper. The system of testing the sealings has proved very satisfactory. The results of the tests carried out in the course of own monitoring show that processing work in the laboratory can be reduced by systematic selection of material and intensive expert supervision of the construction site. (orig.).

  19. Plant diagnostics in power stations

    Sturm, A.; Doering, D.


    The method of noise diagnostics is dealt with as a part of plant diagnostics in nuclear power stations. The following special applications are presented: (1) The modular noise diagnostics system is used for monitoring primary coolant circuits and detecting abnormal processes due to mechanical vibrations, loose parts or leaks. (2) The diagnostics of machines and plants with antifriction bearings is based on bearing vibration measurements. (3) The measurement of the friction moment by means of acoustic emission analysis is used for evaluating the operational state of slide bearings

  20. Local society and nuclear power stations


    This report was made by the expert committee on region investigation, Japan Atomic Industrial Forum Inc., in fiscal years 1981 and 1982 in order to grasp the social economic influence exerted on regions by the location of nuclear power stations and the actual state of the change due to it, and to search for the way the promotion of local community should be. The influence and the effect were measured in the regions around the Fukushima No. 1 Nuclear Power Station of Tokyo Electric Power Co., Inc., the Mihama Power Station of Kansai Electric Power Co., Inc., and the Genkai Nuclear Power Station of Kyushu Electric Power Co., Inc. The fundamental recognition in this discussion, the policy of locating nuclear power stations and the management of regions, the viewpoint and way of thinking in the investigation of the regions where nuclear power stations are located, the actual state of social economic impact due to the location of nuclear power stations, the connected mechanism accompanying the location of nuclear power stations, and the location of nuclear power stations and the acceleration of planning for regional promotion are reported. In order to economically generate electric power, the rationalization in the location of nuclear power stations is necessary, and the concrete concept of building up local community must be decided. (Kako, I.)

  1. Insurance of nuclear power stations

    Debaets, M.


    Electrical utility companies have invested large sums in the establishment of nuclear facilities. For this reason it is normal for these companies to attempt to protect their investments as much as possible. One of the methods of protection is recourse to insurance. For a variety of reasons traditional insurance markets are unable to function normally for a number of reasons including, the insufficient number of risks, an absence of meaningful accident statistics, the enormous sums involved and a lack of familiarity with nuclear risks on the part of insurers, resulting in a reluctance or even refusal to accept such risks. Insurers have, in response to requests for coverage from nuclear power station operators, established an alternative system of coverage - insurance through a system of insurance pools. Insurers in every country unite in a pool, providing a net capacity for every risk which is a capacity covered by their own funds, and consequently without reinsurance. All pools exchange capacity. The inconvenience of this system, for the operators in particular, is that it involves a monopolistic system in which there are consequently few possibilities for the negotiation of premiums and conditions of coverage. The system does not permit the establishment of reserves which could, over time, reduce the need for insurance on the part of nuclear power station operators. Thus the cost of nuclear insurance remains high. Alternatives to the poor system of insurance are explored in this article. (author)

  2. Fire prevention in nuclear power plants


    The causes and frequency of fires at nuclear power plants in various countries are briefly given. Methods are described of fire hazard assessment at nuclear power plants, such as Gretener's method and the probabilistic methods. Approaches to the management of nuclear reactor fire protection in various countries as well as the provisions to secure such protection are dealt with. An overview and the basic characteristics of fire detection and extinguishing systems is presented. (Z.S.). 1 tab

  3. Pedestrian evacuation at the subway station under fire

    Xiao-Xia, Yang; Hai-Rong, Dong; Xiu-Ming, Yao; Xu-Bin, Sun


    With the development of urban rail transit, ensuring the safe evacuation of pedestrians at subway stations has become an important issue in the case of an emergency such as a fire. This paper chooses the platform of line 4 at the Beijing Xuanwumen subway station to study the emergency evacuation process under fire. Based on the established platform, effects of the fire dynamics, different initial pedestrian densities, and positions of fire on evacuation are investigated. According to simulation results, it is found that the fire increases the air temperature and the smoke density, and decreases pedestrians’ visibility and walking velocity. Also, there is a critical initial density at the platform if achieving a safe evacuation within the required 6 minutes. Furthermore, different positions of fire set in this paper have little difference on crowd evacuation if the fire is not large enough. The suggestions provided in this paper are helpful for the subway operators to prevent major casualties. Project supported by the National Natural Science Foundation of China (Grant Nos. 61322307 and 61233001).

  4. Simulators of nuclear power stations

    Zanobetti, D.


    The report deals with the simulators of nuclear power stations used for the training of operators and for the analysis of operations. It reviews the development of analogical, hybrid and digital simulators up to the present, indicating the impact resulting from the TMI-2 accident. It indicates, the components of simulators and the present accepted terminology for a classification of the various types of simulators. It reviews the present state of the art of the technology: how a basic mathematical model of a nuclear power system is worked out and what are the technical problems associated with more accurate models. Examples of elaborate models are given: for a PWR pressurizer, for an AGR steam generator. It also discusses certain problems of hardware technology. Characteristics of present replica simulators are given with certain details: simulated transient evolutions and malfunctions, accuracy of simulation. The work concerning the assessment of the validity of certain simulators is reported. A list of simulator manufacturers and a survey of the principal simulators in operation in the countries of the European Community, in the United States, and in certain other countries are presented. Problem associated with the use of simulators as training facilities, and their use as operational devices are discussed. Studies and research in progress for the expected future development of simulators are reviewed

  5. Water pollution and thermal power stations

    Maini, A.; Harapanahalli, A.B.


    There are a number of thermal power stations dotting the countryside in India for the generation of electricity. The pollution of environment is continuously increasing in the country with the addition of new coal based power stations and causing both a menace and a hazard to the biota. The paper reviews the problems arising out of water pollution from the coal based thermal power stations. (author). 2 tabs

  6. Sources of the wind power stations

    Chudivani, J.; Huettner, L.


    The paper deals with problems of the wind power stations. Describes the basic properties of wind energy. Shows and describes the different types of electrical machines used as a source of electricity in the wind power stations. Shows magnetic fields synchronous generator with salient poles and permanent magnets in the program FEMM. Describes methods for assessing of reversing the effects of the wind power stations on the distribution network. (Authors)

  7. 1100 MW BWR power station



    Now, the start-up test of No. 2 plant in Fukushima No. 2 Nuclear Power Station is smoothly in progress, and the start of its commercial operation is scheduled at the beginning of 1984. Here, the main features of No. 2 plant including piping design are explained. For No. 2 plant, many improving measures were adopted as the base plant of the improvement and standardization project of the Ministry of International Trade and Industry, such as the adoption of Mark-2 improved PCV, the adoption of an intermediate loop in the auxiliary cooling system, one-body forging of the lower end cover of the reactor pressure vessel, the adoption of many curved pipes, the adoption of large one-body structural components in reactor recirculation system piping and so on, which are related to the reduction of radiation exposure and the improvement of plant reliability in operation and regular inspection. Also, in order to do general adjustment in the arrangement of equipment and piping and in route design, and to establish the rational construction work plan, model engineering was adopted. In No. 2 plant, a remote-controlled automatic and semiautomatic ultrasonic flaw detection system was adopted to reduce radiation exposure in in-service inspection. Automatic welding was adopted to improve the quality. (Kako, I.)

  8. Quantitative Risk Modeling of Fire on the International Space Station

    Castillo, Theresa; Haught, Megan


    The International Space Station (ISS) Program has worked to prevent fire events and to mitigate their impacts should they occur. Hardware is designed to reduce sources of ignition, oxygen systems are designed to control leaking, flammable materials are prevented from flying to ISS whenever possible, the crew is trained in fire response, and fire response equipment improvements are sought out and funded. Fire prevention and mitigation are a top ISS Program priority - however, programmatic resources are limited; thus, risk trades are made to ensure an adequate level of safety is maintained onboard the ISS. In support of these risk trades, the ISS Probabilistic Risk Assessment (PRA) team has modeled the likelihood of fire occurring in the ISS pressurized cabin, a phenomenological event that has never before been probabilistically modeled in a microgravity environment. This paper will discuss the genesis of the ISS PRA fire model, its enhancement in collaboration with fire experts, and the results which have informed ISS programmatic decisions and will continue to be used throughout the life of the program.

  9. Fire protection at nuclear power plants


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

  10. Periodical inspection in nuclear power stations


    Periodical inspection is presently being made of eight nuclear power plants in nuclear power stations. Up to the present time, in three of them, failures as follows have been observed. (1) Unit 3 (PWR) of the Mihama Power Station in The Kansai Electric Power Co., Inc. Nineteen heat-transfer tubes of the steam generators were plugged up due to failure. A fuel assembly with a failed spring fixture and in another the control-rod cluster with a failed control rod fixture were replaced. (2) Unit 2 (PWR) of the Oi Power Station in The Kansai Electric Power Co., Inc. Eight heat-transfer tubes of the heat exchangers were plugged up due to failure. (3) Unit 6 (BWR) of the Fukushima Nuclear Power Station I in The Tokyo Electric Power Co., Inc. A fuel assembly with leakage was replaced. (Mori, K.)

  11. Study into the status of co-combustion of sewage sludge, biomass and household refuse in coal-fired power stations. Final report; Untersuchungen zum Stand der Mitverbrennung von Klaerschlamm, Hausmuell und Biomasse in Kohlekraftwerken. Schlussbericht

    Hein, K.R.G.; Spliethoff, H.; Scheurer, W. [Stuttgart Univ. (Germany). Inst. fuer Verfahrenstechnik und Dampfkesselwesen; Seifert, H.; Richers, U. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer technische Chemie - Thermische Abfallbehandlung


    The co-combustion of wastes in power stations is an additional option for the thermal treatment of certain waste materials and thus for complying with the specifications of the German TA-Siedlungsabfall (technical directive on disposal of municipal solid waste). The present investigation compiles the status of knowledge about co-combustion of sewage sludge, biomass and selected waste materials in coal-fired power stations. The results are meant to provide extensive assistance to evaluate the processes and thus to contribute to sort out uncertainties, both on the part of power plant operators and of the authorities. Based on the information acquired, the report shall point out the gaps in knowledge, the further need for research and development and the need for action conerning the authorities. By enquiries at disposal enterprises, power station operators as well as authorities, the literature work was completed and a comprehensive view of the current situation in Germany elaborated. The report points out the legal conditions of co-combustion and supplementary fuel potentials, presents the process engineering of co-combustion, and examines the obstacles encountered during the technical conversion, the environmental questions, and the potential for co-combustion of the above materials in existing power stations. The electrical power sector is subject to strong changes due to the liberalisation of the energy market. The pressure on costs has increased and the periods available for planning are shorter. On the one hand, this arouses an increased interest in co-combustion of waste materials because of possible additional payments for the wastes. On the other hand, however, initiatives in this respect are counteracted by high investments costs necessary for the introduction of co-combustion with the existing high environmental standards. What is more, the competitive situation reduces the exchange of experience between the power station operators. Co-combustion of sewage

  12. Beaver Valley Power Station and Shippingport Atomic Power Station. 1977 annual environmental report: radiological. Volume 2


    The environmental monitoring conducted during 1977 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station is described. The environmental monitoring program consists of onsite sampling of water, gaseous, and air effluents, as well as offsite monitoring of water, air, river sediments, and radiation levels in the vicinity of the site. The report discusses releases of small quantities of radioactivity to the Ohio River from the Beaver Valley Power Station and Shippingport Atomic Power Station during 1977

  13. General conditions for gas-fired power plants in Europe

    Hugi, Ch.; Fuessler, J.; Sommerhalder, M.


    This comprehensive report for the Swiss Federal Office of Energy (SFOE) takes a look at the general conditions for the installation of gas-fired power plants in Europe. Combined cycle power stations are characterised and the associated power production costs are discussed. Also, the prices resulting from the internalisation of external costs are noted. The problems associated with carbon dioxide emissions are discussed and the trading of emission certificates is looked at. Also, nitrogen oxide emissions are examined and discussed. The use of waste heat from the combined cycle power stations is also examined. Further topics include subsidies and special credits for the gas industry in Europe and the granting of permission for the planning, construction, operation and dismantling of the power station facilities. The situation in various European countries is examined and the associated market distortion is commented on

  14. Reliability study of nuclear power stations

    Nemec, J.; Sedlacek, J.


    The paper considers the physical and mathematical bases underlying nuclear power station reliability from the standpoints of material fatigue, thermal yield and ageing. The risk of failure of nuclear power station components is determined by means of the Markov stochastic process

  15. Construction work management for nuclear power stations

    Yoshikawa, Yuichiro


    Nuclear power generation is positioned as the nucleus of petroleum substitution. In the Kansai Electric Power Co., efforts have been made constantly to operate its nuclear power plants in high stability and safety. At present, Kansai Electric Power Co. is constructing Units 3 and 4 in the Takahama Nuclear Power Station in Fukui Prefecture. Under the application of the management of construction works described here, both the nuclear power plants will start operation in 1985. The activities of Kansai Electric Power Co. in the area of this management are described: an outline of the construction works for nuclear power stations, the management of the construction works in nuclear power stations (the stages of design, manufacturing, installation and test operation, respectively), quality assurance activities for the construction works of nuclear power plants, important points in the construction work management (including the aspects of quality control). (J.P.N.)

  16. Pre-fire planning for nuclear power plants

    Talbert, J.H.


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

  17. Upgrading of fire safety in Indian nuclear power plants

    Agarwal, N.K.


    Indian nuclear power programme started with the installation of 2 nos. of Boiling Water Reactor (BWR) at Tarapur (TAPS I and II) of 210 MWe each commissioned in the year 1996. The Pressurized Heavy Water Reactor (PHWR) programme in the country started with the installation of 2x220 MWe stations at Rawatbhatta near Kota (RAPS I and II) in the State of Rajasthan in the sixties. At the present moment, the country has 10 stations in operation. Construction is going on for 4 more units of 220 MWe where as work on two more 500 MWe units is going to start soon. Fire safety systems for the earlier units were engineered as per the state-of-art knowledge available then. The need for review of fire protection systems in the Indian nuclear power plants has also been felt since long almost after Brown's Ferry fire in 1975 itself. Task forces consisting of fire experts, systems design engineers, O and M personnel as well as the Fire Protection engineers at the plant were constituted for each plant to review the existing fire safety provisions in details and highlight the upgradation needed for meeting the latest requirements as per the national as well as international practices. The recommendations made by three such task forces for the three plants are proposed to be reviewed in this paper. The paper also highlights the recommendations to be implemented immediately as well as on long-term basis over a period of time

  18. The risks at nuclear power stations and their insurance

    Schludi, H.N.


    Insurance can offer an uninterrupted insurance cover from start-up-to shut-down of a nuclear power station. This is assured by the insurance for the erection, for the nuclear liability, for the nuclear/fire, for the engines, for operational interruptions and for the transport. For each of the above mentioned insurance branches, essential characteristic features, such as risk carrier, protection range and insurance costs, are given. (orig.) [de

  19. Development of non-halogen cables for nuclear power stations

    Yagyu, Hideki; Yamamoto, Yasuaki; Onishi, Takao (Hitachi Cable, Ltd., Tokyo (Japan))


    The non-halogen fire-resistant cables for nuclear power stations which never generate halogen gas, have been developed. The cables comprise the insulator of EP rubber and the sheath of polyolefine containing non-halogen inorganic fire-retardant. The results of the environmental test and fire-resistance test are described. In the environmental test, the cables were subjected to the heating, gamma-irradiation and steam exposure successively, according to IEEE specification 323,383, and subsequently the change in the appearance, tensile strength and electrical performance of the cables was measured. In the fire-resistance test, the vertical tray fire test according to the IEEE specification 383 was adopted, and other tests including the vertical fire test on insulator cores, oxygen index, the generation of corrosive gas, copper mirror corrosion test, gas toxicity test and optical smoke density test were carried out. It became clear that the cables did not generate halogen gas on burning, and brought about reduced toxicity, corrosion and smoke, and that the safety against fire is greatly improved by using the cables.

  20. Development of non-halogen cables for nuclear power stations

    Yagyu, Hideki; Yamamoto, Yasuaki; Onishi, Takao


    The non-halogen fire-resistant cables for nuclear power stations which never generate halogen gas, have been developed. The cables comprise the insulator of EP rubber and the sheath of polyolefine containing non-halogen inorganic fire-retardant. The results of the environmental test and fire-resistance test are described. In the environmental test, the cables were subjected to the heating, gamma-irradiation and steam exposure successively, according to IEEE specification 323,383, and subsequently the change in the appearance, tensile strength and electrical performance of the cables was measured. In the fire-resistance test, the vertical tray fire test according to the IEEE specification 383 was adopted, and other tests including the vertical fire test on insulator cores, oxygen index, the generation of corrosive gas, copper mirror corrosion test, gas toxicity test and optical smoke density test were carried out. It became clear that the cables did not generate halogen gas on burning, and brought about reduced toxicity, corrosion and smoke, and that the safety against fire is greatly improved by using the cables. (Yoshitake, I.)

  1. Tokai earthquakes and Hamaoka Nuclear Power Station

    Komura, Hiroo


    Kanto district and Shizuoka Prefecture are designated as ''Observation strengthening districts'', where the possibility of earthquake occurrence is high. Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., is at the center of this district. Nuclear power stations are vulnerable to earthquakes, and if damages are caused by earthquakes in nuclear power plants, the most dreadful accidents may occur. The Chubu Electric Power Co. underestimates the possibility and scale of earthquakes and the estimate of damages, and has kept on talking that the rock bed of the power station site is strong, and there is not the fear of accidents. However the actual situation is totally different from this. The description about earthquakes and the rock bed in the application of the installation of No.3 plant was totally rewritten after two years safety examination, and the Ministry of International Trade and Industry approved the application in less than two weeks thereafter. The rock bed is geologically evaluated in this paper, and many doubtful points in the application are pointed out. In addition, there are eight active faults near the power station site. The aseismatic design of the Hamaoka Nuclear Power Station assumes the acceleration up to 400 gal, but it may not be enough. The Hamaoka Nuclear Power Station is intentionally neglected in the estimate of damages in Shizuoka Prefecture. (Kako, I.)

  2. Analysis of fire protection in nuclear power plants

    Hosser, D.; Schneider, U.


    Regulations and test specifications for fire prevention in nuclear power plants are presented as well as the fire protection measures in a newly constructed nuclear power plant. Although the emphasis is placed differently, all rules are based on the following single measures: Fire prevention, fire detection, fire fighting, fire checking, attack, flight, and rescue, organisational measures. (orig./GL) [de

  3. Fuel saving, carbon dioxide emission avoidance, and syngas production by tri-reforming of flue gases from coal- and gas-fired power stations, and by the carbothermic reduction of iron oxide

    Halmann, M.; Steinfeld, A.


    Flue gases from coal, gas, or oil-fired power stations, as well as from several heavy industries, such as the production of iron, lime and cement, are major anthropogenic sources of global CO 2 emissions. The newly proposed process for syngas production based on the tri-reforming of such flue gases with natural gas could be an important route for CO 2 emission avoidance. In addition, by combining the carbothermic reduction of iron oxide with the partial oxidation of the carbon source, an overall thermoneutral process can be designed for the co-production of iron and syngas rich in CO. Water-gas shift (WGS) of CO to H 2 enables the production of useful syngas. The reaction process heat, or the conditions for thermoneutrality, are derived by thermochemical equilibrium calculations. The thermodynamic constraints are determined for the production of syngas suitable for methanol, hydrogen, or ammonia synthesis. The environmental and economic consequences are assessed for large-scale commercial production of these chemical commodities. Preliminary evaluations with natural gas, coke, or coal as carbon source indicate that such combined processes should be economically competitive, as well as promising significant fuel saving and CO 2 emission avoidance. The production of ammonia in the above processes seems particularly attractive, as it consumes the nitrogen in the flue gases

  4. MHD power station with coal gasification

    Brzozowski, W.S.; Dul, J.; Pudlik, W.


    A description is given of the proposed operating method of a MHD-power station including a complete coal gasification into lean gas with a simultaneous partial gas production for the use of outside consumers. A comparison with coal gasification methods actually being used and full capabilities of power stations heated with coal-derived gas shows distinct advantages resulting from applying the method of coal gasification with waste heat from MHD generators working within the boundaries of the thermal-electric power station. (author)

  5. Environmental surveillance of PWR power stations

    Conti, M.


    The action of Electricite de France with respect to the environment of PWR nuclear power stations is essentially centred on prevention. Controls are carried out at two levels: - before the power station goes on stream (radioecological study), - when the power station is operational. The purpose of the controls effected on the radioactive effluents and the environment is to check that the maximum discharge rate stipulated in the corresponding orders is complied with and to ensure that there are no anomalies in the environment [fr

  6. Space power station. Uchu hatsuden

    Kudo, I. (Electrotechnical Laboratory, Tsukuba (Japan))


    A calculation tells that the amount of electric power the world will use in the future will require 100 to 500 power plants each with an output of 5-GW class. If this conception is true, it is beyond dispute that utilizing nuclear power will constitute a core of the power generation even though the geographical conditions are severe for nuclear power plants. It is also certain that power generation using clean solar energy will play important roles if power supply stability can be achieved. This paper describes plans to develop space solar power generation and space nuclear power generation that can supply power solving problems concerning geographical conditions and power supply stability. The space solar power generation is a system to arrest solar energy on a static orbit. According to a result of discussions in the U.S.A., the plan calls for solar cell sheets spread over the surface of a structure with a size of 5 km [times] 10 km [times] 0.5 km thick, and electric power obtained therefrom is transmitted to a rectenna with a size of 10 km [times] 13 km, a receiving antenna on the ground. The space nuclear power generation will be constructed similarly on a static orbit. Researches on space nuclear reactors have already begun. 10 refs., 8 figs., 1 tab.

  7. Sizewell B Power Station control dosimetry system

    Renn, G.


    Sizewell B Power Station is the first Pressurized Water Reactor (PWR) built in the UK for commercial electricity production. An effective control dosimetry system is a crucial tool, in allowing the station to assess its radiological performance against targets. This paper gives an overview of the control dosimetry system at Sizewell B and describes early operating experience with the system. (UK)

  8. Low Power Wireless Smoke Alarm System in Home Fires

    Juan Aponte Luis


    Full Text Available A novel sensing device for fire detection in domestic environments is presented. The fire detector uses a combination of several sensors that not only detect smoke, but discriminate between different types of smoke. This feature avoids false alarms and warns of different situations. Power consumption is optimized both in terms of hardware and software, providing a high degree of autonomy of almost five years. Data gathered from the device are transmitted through a wireless communication to a base station. The low cost and compact design provides wide application prospects.

  9. Extension of life of nuclear power stations

    Takahashi, Hideaki


    At the time of designing nuclear power stations, as their service life, generally 40 years are taken, and the basic design specifications of machinery and equipment are determined. In USA where atomic energy has been developed, the new construction of nuclear power stations is cased for a while, however, if this situation continues as it is, since old power stations reach the service life of 40 years and are retired in near future, it is feared that the circumstance of the total amount of power generation becoming short will occur. As one of the countermeasures to this, the research on the extension of life of nuclear power stations has been carried out in many fields in USA, and it is expected that the application for extending the life for the power stations constructed in the initial period of development is submitted in 1991. The researches that have been carried out for solving the technical problems in this extension of life and the situation in Japan are reported. The NEC of USA decided that the operation period of nuclear power stations in USA, which is considered to be 40 years so far, can be extended up to the limit of 20 years. The background and circumstances of this problem in USA, Nuclear Plant Aging Research Program, Plant Life Extension Program and so on are reported. (K.I.)

  10. Fire protection guidelines for nuclear power plants


    Guidelines acceptable to the NRC staff for implementing in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. Suitable bases and justification should be provided for alternative approaches to establish acceptable implementaion of General Design Criterion 3

  11. Valves and fittings for nuclear power stations


    The standard specifies technical requirements for valves and pipe fittings in nuclear power stations with PWR type reactors. Details of appropriate materials, welding, surface treatment for corrosion protection, painting, and complementary supply are given

  12. Anticorrosional protection in nuclear power station objects

    Czarnocki, A.; Kwiatkowski, A.


    The distribution and qualities of chemical protection and demands concerning preparation of the bottom for protecting coats in nuclear power station objects are discussed. The solutions of protections applied abroad and in the objects of ''MARIA'' reactor are presented. (author)

  13. Heating of water by nuclear power stations


    The aim of this note is to examine: the thermal conditions of the Rhone in its present state; heating caused by the building of nuclear power stations; the main hydrobiological and ecological characteristics of the Rhone [fr

  14. Training of power station staff

    Dusserre, J.


    ELECTRICITE DE FRANCE currently operates 51 generating stations with 900 and 1300 MW Pressurized Water Reactors while, only 15 years ago, France possessed only a very small number of such stations. It was therefore vital to set up a major training organization to produce staff capable of starting, controlling and maintaining these facilities with a constant eye to improving quality and safety. Operator and maintenance staff training is based on highly-structured training plans designed to match both the post to be filled and the qualifications possessed by the person who is to fill it. It was essential to set up suitable high-performance training resources to handle this fast growth in staff. These resources are constantly being developed and allow EDF to make steady progress in a large number of areas, varying from the effects of human factors to the procedures to be followed during an accident

  15. Solidifying power station resins and sludges

    Willis, A.S.D.; Haigh, C.P.


    Radioactive ion exchange resins and sludges arise at nuclear power stations from various operations associated with effluent treatment and liquid waste management. As the result of an intensive development programme, the Central Electricity Generating Board (CEGB) has designed a process to convert power station resins and sludges into a shielded, packaged solid monolithic form suitable for final disposal. Research and development, the generic CEGB sludge/resin conditioning plant and the CEGB Active Waste Project are described. (U.K.)

  16. Energy analysis of nuclear power stations

    Lindhout, A.H.


    A study based on a 1000MWe light water reactor power station was carried out to determine the total energy input and output of the power station. The calculations took into account the mining and processing of the ore, enrichment of the uranium, treatment of used nuclear fuel, investment in land, buildings, machinery, and transport. 144 tons of natural uranium produce 6100 million kWh (electric) and 340 million kWh (thermal) per annum. (J.S.)

  17. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Wright, J.K.


    A description is given of the CEGB's current assessment of the potential contribution to electricity generation of those methods considered to be the most significant alternatives to conventional power stations or thermal nuclear reactors for generating electricity. The state of development of the technology, the timescale on which it could be developed, its ability to generate electricity reliably and the cost of generating electricity are some of the matters considered. The following topics are covered: potential developments in coal fired generating plant; combined heat and power generation; energy storage; electricity generation from renewable energy sources; fast reactors and fusion. (U.K.)

  18. Commerical electric power cost studies. Capital cost addendum multi-unit coal and nuclear stations


    This report is the culmination of a study performed to develop designs and associated capital cost estimates for multi-unit nuclear and coal commercial electric power stations, and to determine the distribution of these costs among the individual units. This report addresses six different types of 2400 MWe (nominal) multi-unit stations as follows: Two Unit PWR Station-1139 MWe Each, Two Unit BWR Station-1190 MWe Each, Two Unit High Sulfur Coal-Fired Station-1232 MWe Each, Two Unit Low Sulfur Coal-Fired Station-1243 MWe Each, Three Unit High Sulfur Coal-Fired Station-794 MWe Each, Three Unit Low Sulfur Coal-Fired Station-801 MWe Each. Recent capital cost studies performed for ERDA/NRC of single unit nuclear and coal stations are used as the basis for developing the designs and costs of the multi-unit stations. This report includes the major study groundrules, a summary of single and multi-unit stations total base cost estimates, details of cost estimates at the three digit account level and plot plan drawings for each multi-unit station identified

  19. Improvement of fire protection measures for nuclear power plants


    Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic tool to actual plants, With regard to fire tests for the fire data acquisition, cable fire test and oil fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, CFAST were implemented in order to analyze the fire progression phenomena, Trial simulation of fire hazard as Metal-Clad Switch Gear Fire of ONAGAWA NPP in Tohoku earthquake (HEAF accident). (author)

  20. Tampa Electric Company Polk Power Station IGCC project: Project status

    McDaniel, J.E.; Carlson, M.R.; Hurd, R.; Pless, D.E.; Grant, M.D. [Tampa Electric Co., FL (United States)


    The Tampa Electric Company Polk Power Station is a nominal 250 MW (net) Integrated Gasification Combined Cycle (IGCC) power plant located to the southeast of Tampa, Florida in Polk County, Florida. This project is being partially funded under the Department of Energy`s Clean Coal Technology Program pursuant to a Round II award. The Polk Power Station uses oxygen-blown, entrained-flow IGCC technology licensed from Texaco Development Corporation to demonstrate significant reductions of SO{sub 2} and NO{sub x} emissions when compared to existing and future conventional coal-fired power plants. In addition, this project demonstrates the technical feasibility of commercial scale IGCC and Hot Gas Clean Up (HGCU) technology. The Polk Power Station achieved ``first fire`` of the gasification system on schedule in mid-July, 1996. Since that time, significant advances have occurred in the operation of the entire IGCC train. This paper addresses the operating experiences which occurred in the start-up and shakedown phase of the plant. Also, with the plant being declared in commercial operation as of September 30, 1996, the paper discusses the challenges encountered in the early phases of commercial operation. Finally, the future plans for improving the reliability and efficiency of the Unit in the first quarter of 1997 and beyond, as well as plans for future alternate fuel test burns, are detailed. The presentation features an up-to-the-minute update on actual performance parameters achieved by the Polk Power Station. These parameters include overall Unit capacity, heat rate, and availability. In addition, the current status of the start-up activities for the HGCU portion of the plant is discussed.

  1. Starting of nuclear power stations

    Kotyza, V.


    The procedure is briefly characterized of jobs in nuclear power plant start-up and the differences are pointed out from those used in conventional power generation. Pressure tests are described oriented to tightness, tests of the secondary circuit and of the individual nodes and facilities. The possibility is shown of increased efficiency of such jobs on an example of the hydraulic tests of the second unit of the Dukovany nuclear power plant where the second and the third stages were combined in the so-colled integrated hydraulic test. (Z.M.). 5 figs

  2. The status and prospects for the fossil-fired and nuclear power industry in Japan

    Miyahara, S.


    Power plant capacity in Japan amounts to about 200 GW, of which 180 GW belong to the electricity supply industry. 60% are installed in fossil-fired power stations, 19% in nuclear power stations and 21% in hydro-electric power stations. Key engineering techniques for power production from fossil fuels are supercritical steam conditions and combined cycle power plant technology. Crucial points for nuclear power generation are the development of the advanced light water reactor, the commericialization of the fast breeder reactor and the installation of a closed nuclear fuel cycle. (orig.) [de

  3. Small hydroelectric power stations and their reality

    Kamenski, Miroslav


    Construction of a small hydroelectric power station provides additional amounts of electric energy, engages a private capital, revives investment activities and promotes the use of renewable energy sources. Transmission losses are reduced, a voltage of higher quality is achieved and idle power is compensated by the generation of electricity in the small hydroelectric power stations and at the place of consumption. Legislation and technical regulations, however, require a multidisciplinary approach, defining of complex spaces and environmental protection. Unfortunately, complete documents should be prepared for small,hydroelectric plants just as for big ones what is a long procedure and many of those papers are unnecessary or even superfluous. (Author)

  4. Distributed systems for protecting nuclear power stations

    Jover, P.


    The advantages of distributed control systems for the control of nuclear power stations are obviously of great interest. Some years ago, EPRI, (Electric Power Research Institute) showed that multiplexing the signals is technically feasible, that it enables the availability specifications to be met and costs to be reduced. Since then, many distributed control systems have been proposed by the manufacturers. This note offers some comments on the application of the distribution concept to protection systems -what should be distributed- and ends with a brief description of a protection system based on microprocessors for the pressurized power stations now being built in France [fr

  5. Discharges to the environment and environmental protection at CEGB power stations

    Wright, J.K.


    The subject is discussed under the headings: introduction (scope of paper will cover the principles, methods and results obtained in environmental protection in relation to atmospheric discharges made routinely during power generation); air pollution control; nuclear power stations (type of discharge, annual discharges, environmental monitoring); fossil fuelled power stations; health effects; trace elements; long range transport and acid rain; future coal fired plant; carbon dioxide. (U.K.)

  6. Nuclear power station achievement 1968-1980

    Howles, L.R.

    This report reviews and gives an analysis of the achievement of operating nuclear power stations in the Western world on three relevant bases: (1) both annual and cumulative achievement of all nuclear power stations at a particular time; (2) cumulative achievement of all nuclear power stations at the end of the first and subsequent years of their lives to show trends with age; (3) achievement based on refuelling period considerations. Nowhere in the report are any operating details ignored, omitted or eliminated in the method of analysis. Summarising the results of the reviews shows: an improvement with time from initial electricity generation on all bases; that initially, larger sizes of reactor/turbine operate less well than smaller sizes (except for PHWR's); that after an initial number of years, the largest size units operate as well as the intermediate and smaller sizes, or better in the PHWR case; that a 75 per cent cumulative load factor achievement in the middle years of a reactor/turbines life can be expected on the refuelling period considerations base; that at June 1980, 35 nuclear power stations achieved an annual load factor over 75 per cent; that the above achievement was possible despite the repercussions following the Three Mile Island 'accident' and the shutdowns in the USA for piping system seismic adequacy checks required by the Nuclear Regulatory Commission for five nuclear power stations; and that even when reactors/turbines are reaching towards the end of their design life, there is no rapid deterioration in their achievements. (author)

  7. Error management process for power stations

    Hirotsu, Yuko; Takeda, Daisuke; Fujimoto, Junzo; Nagasaka, Akihiko


    The purpose of this study is to establish 'error management process for power stations' for systematizing activities for human error prevention and for festering continuous improvement of these activities. The following are proposed by deriving concepts concerning error management process from existing knowledge and realizing them through application and evaluation of their effectiveness at a power station: an entire picture of error management process that facilitate four functions requisite for maraging human error prevention effectively (1. systematizing human error prevention tools, 2. identifying problems based on incident reports and taking corrective actions, 3. identifying good practices and potential problems for taking proactive measures, 4. prioritizeng human error prevention tools based on identified problems); detail steps for each activity (i.e. developing an annual plan for human error prevention, reporting and analyzing incidents and near misses) based on a model of human error causation; procedures and example of items for identifying gaps between current and desired levels of executions and outputs of each activity; stages for introducing and establishing the above proposed error management process into a power station. By giving shape to above proposals at a power station, systematization and continuous improvement of activities for human error prevention in line with the actual situation of the power station can be expected. (author)

  8. Socioeconomic impacts: nuclear power station siting


    The rural industrial development literature is used to gain insights on the socioeconomic effects of nuclear power stations. Previous studies of large industrial facilities in small towns have important implications for attempts to understand and anticipate the impacts of nuclear stations. Even a cursory review of the nuclear development literature, however, reveals that industrialization research in rural sociology, economic geography and agricultural economics has been largely ignored

  9. Retrofit of new digital control systems in existing power stations

    Smith, J.E.; Baird, C.F.


    With the notable exception of the Canadian CANDU nuclear power stations, little use has been made of digital control in North American nuclear stations. Recently, however, there has been renewed interest in such systems within the nuclear industry in response to demands for better ergonomics in control room design and the obsolescence of control equipment whose fundamental design has changed little in 20 yr. Early in 1985, Atomic Energy of Canada Limited was asked by New Brunswick Power to advise on the redesign of the control systems for two fossil-fired generating stations, Coleson Cove and Courtenay Bay Unit 4. Coleson Cove is to be converted from oil to coal firing with consequent extensive control system changes and Courtenay Bay Unit 4 required a low-cost solution to the problem of relocating its control room from the existing isolated location to the combined control center used by units 1, 2, and 3. In both cases, the recommended solution involves the retrofit of state-of-the-art digital control systems. Although the units involved are nonnuclear the experience is applicable

  10. New Zealand's Clyde power station

    Hatton, J W; Black, J C; Foster, P F


    A 100 m-high mass concrete gravity dam, for the generation of 432 MW of power, is under construction at Clyde on the Clutha River in the South Island of New Zealand. A feature of the dam is the provision of a slip joint to allow up to 2 m of movement on the plane of a fault passing through the dam foundation. Details of the dam foundations, seismic design, river channel fault and slip joint, mass concrete, spillway and sluice, powerhouse, and landslide hazard at the site are given. 3 refs.

  11. The Grossmatt hydro-power station

    Hintermann, M.


    This final report for the Swiss Federal Office of Energy (SFOE) presents the project for a small hydropower station on the Birs river in north-western Switzerland. The report reviews the history of the project, in which a new 385 kW-hydro-power station at the site of an earlier installation is foreseen. Details are presented on the investigations made and on the co-ordination with the owners of the hydro-power station situated up-river, the local power utility and the local authorities. Also, the requirements placed on the project by the fishing authorities are quoted and the solution foreseen is described. Also discussed are the requirements placed on the project by legislation on environmental impact and flood protection. Figures on electrical energy production and building costs are presented

  12. Safety aspects of nuclear power stations

    Binner, W.


    Psychological aspects of the fear of nuclear power are discussed, cancer deaths due to a nuclear accident are predicted and the need for nuclear accident prevention is stressed. A simplified analysis of the safety precautions in a generalised nuclear power station is offered, with reference to loss-of-coolant incidents, and developments in reactor design for fail-safe modes are explained. The importance of learning from the Three Mile Island incident is noted and failure statistics are presented. Tasks to be undertaken at the Austrian Zwentendorf nuclear power station are listed, including improved quality control and acoustic detectors. Precautions against earthquakes are also discussed and it is stated that safe operation of the Zwentendorf station will be achieved. (G.M.E.)

  13. Can we afford shutting down power stations?

    Hesse, David


    The author discusses and criticizes some popular beliefs on the profitability of nuclear power stations, on the fact that they are now too old to be exploited, and on the fact that nuclear energy is the most subsidised energy. As some European countries decided to phase out nuclear, he notices that the decrease of gas prices undermines the profitability of nuclear power stations in the USA and that new rules aimed at the reduction of CO 2 emissions result in high subsidies for renewable energies which are however handicapped by the grid ability to integrate all energies. He outlines that shutting down a nuclear power station costs a lot of money to the society, and denies the argument of non-profitability of these stations. He states that the issue of nuclear subsidies is in fact a matter of tax policy. He also states that these so-said old power stations take in fact advantage of numerous technical innovations for their equipment, components, technology and fuels which improve their efficiency, durability, performance and flexibility

  14. Nuclear power generation modern power station practice


    Nuclear Power Generation focuses on the use of nuclear reactors as heat sources for electricity generation. This volume explains how nuclear energy can be harnessed to produce power by discussing the fundamental physical facts and the properties of matter underlying the operation of a reactor. This book is comprised of five chapters and opens with an overview of nuclear physics, first by considering the structure of matter and basic physical concepts such as atomic structure and nuclear reactions. The second chapter deals with the requirements of a reactor as a heat source, along with the diff

  15. Characterizing toxic emissions from a coal-fired power plant demonstrating the AFGD ICCT Project and a plant utilizing a dry scrubber/baghouse system: Bailly Station Units 7 and 8 and AFGD ICCT Project. Final report. Final report

    Dismukes, E.B.


    This report describes results of assessment of the risk of emissions of hazardous air pollutants at one of the electric power stations, Bailly Station, which is also the site of a Clean Coal Technology project demonstrating the Pure Air Advanced Flue Gas Desulfurization process (wet limestone). This station represents the configuration of no NO{sub x} reduction, particulate control with electrostatic precipitators, and SO{sub 2} control with a wet scrubber. The test was conducted September 3--6, 1993. Sixteen trace metals were determined along with 5 major metals. Other inorganic substances and organic compounds were also determined.

  16. Developmental state and perspectives of USSR power stations, espec. nuclear power stations


    According to the resolutions of the 25th and 26th party congresses of the CPSU, the Soviet electric and thermal energy economy envisages as the mainstreams in development: Energy projects based on nuclear fuel, i.e. nuclear power stations (NPS), nuclear heat- and -power stations (NHPS) and nuclear heat stations (NHS); fuel-energy complexes: Ekibastuz, Kansk-Achinsk, West-Siberian complex (Tyumen); power stations utilizing non-conventional regenerative energy sources, i.e. solar, geothermal, MHD power stations. Further down, an overview is given on the developmental perspectives of nuclear-heat and nuclear-power economy and on the development of energy management based on fossil fuels. (orig./UA) [de

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


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

  18. Poultry litter power station in the United Kingdom



    Poultry litter has presented a waste disposal problem to the poultry industry in many parts of the United Kingdom. The plant at Eye is a small to medium scale power station, fired using poultry litter. The 12.7 MW of electricity generated is supplied, through the local utility, to the National Grid. The spent litter that constitutes the fuel is made up of excrement and animal bedding (usually 90% excrement and 10% straw or wood shavings). It comes from large climate-controlled buildings (broiler houses) where birds, reared for meat production, are allowed to roam freely. (UK)

  19. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Harrison, J.R.


    An overview is given of the Safety Case for the Sizewell B nuclear power station as presented in the Pre-Construction Safety Report. Information which has been made available since its publication is included. Safety is considered for normal operation of the reactor and under fault conditions. Faults considered are those due to external hazards such as earthquakes, extreme weather conditions and aircraft crashes, internal hazards such as fire and missiles and reactor faults. Reactor fault studies described include transient analyses of pressurised faults and of loss-of-coolant accidents and the evaluation of the radiological consequences of design basis faults. (U.K.)

  20. Aseismic foundation system for nuclear power stations

    Jolivet, F.; Richli, M.


    The aseismic foundation system, as described in this paper, is a new development, which makes it possible to build standard nuclear power stations in areas exposed to strong earthquakes. By adopting proven engineering concepts in design and construction of components, great advantages are achieved in the following areas: safety and reliability; efficiency; design schedule; cost. The need for an aseismic foundation system will arise more and more, as a large part of nuclear power station sites are located in highly seismic zones or must meet high intensity earthquake criteria due to the lack of historic data. (Auth.)

  1. PFBC development for lignite-fired CC power plants

    Bauer, F.; Meier, H.J.; Smuda, J.V.; Stuhlmueller, F. [VEAG Vereinigte Energiewerke AG (Germany)


    A power station design based on pressurised combustion in a circulating fluid-bed is used to illustrate the principle, layout and potential of a lignite-fired combined power station. The fundamental reasons for concentrating on the circulating pressurised fluid-bed consist in its improved emission values, the possibility of separating heat source and heat sink, and better operating performance (part-load). This design has been developed as part of a feasibility study supported by the Federal Ministry for Research and Tehcnology. The paper describes the design of the power plant components. Combustion trials carried out at the pilot plant in Friedrichsfield are reported and the cost-effectiveness of the innovatory design discussed. 10 figs.

  2. Flame visualization in power stations

    Hulshof, H J.M.; Thus, A W; Verhage, A J.L. [KEMA Fossil Generation, Arnhem (Netherlands)


    The study on the title subject is aimed at the determination of the form of the flame and the radiation temperature of the flames of the burners in electric power plants. The adjustment of the burners in a boiler is assessed on the basis of the total performance, in which the NO[sub x]- and CO-concentrations in the flue gases are normative. By comparing the burners mutually, deviating adjustments can be observed, applying optical monitoring techniques. Measurements have been carried out of the coal flames in the unit Gelderland13 of the Dutch energy production company EPON and of the gas flames at the Claus plant A and B of the Dutch energy company EPZ. The final aim of the title study is to draft guidelines, based on the measured flame data, by means of which for every individual burner the adjustment of the fuel supply, the relation with the air supply and the swirl of the combustion air can be optimized

  3. Plant computer system in nuclear power station

    Kato, Shinji; Fukuchi, Hiroshi


    In nuclear power stations, centrally concentrated monitoring system has been adopted, and in central control rooms, large quantity of information and operational equipments concentrate, therefore, those become the important place of communication between plants and operators. Further recently, due to the increase of the unit capacity, the strengthening of safety, the problems of man-machine interface and so on, it has become important to concentrate information, to automate machinery and equipment and to simplify them for improving the operational environment, reliability and so on. On the relation of nuclear power stations and computer system, to which attention has been paid recently as the man-machine interface, the example in Tsuruga Power Station, Japan Atomic Power Co. is shown. No.2 plant in the Tsuruga Power Station is a PWR plant with 1160 MWe output, which is a home built standardized plant, accordingly the computer system adopted here is explained. The fundamental concept of the central control board, the process computer system, the design policy, basic system configuration, reliability and maintenance, CRT display, and the computer system for No.1 BWR 357 MW plant are reported. (K.I.)

  4. Nuclear safeguards control in nuclear power stations

    Boedege, R.; Braatz, U.; Heger, H.


    The execution of the Non-Proliferation Treaty (NPT) has initiated a third phase in the efforts taken to ensure peace by limiting the number of atomic powers. In this phase it is important, above all, to turn into workable systems the conditions imposed upon technology by the different provisions of the Verification Agreement of the NPT. This is achieved mainly by elaborating annexes to the Agreement specifically geared to certain model plants, typical representatives selected for LWR power stations being the plants at Garigliano, Italy (BWR), and Stade, Federal Republic of Germany (PWR). The surveillance measures taken to prevent any diversion of special nuclear material for purposes of nuclear weapons manufacture must be effective in achieving their specific objective and must not impede the circumspect management of operations of the plants concerned. A VDEW working party has studied the technical details of the planned surveillance measures in nuclear power stations in the Federal Republic of Germany and now presents a concept of material balancing by units which meets the conditions imposed by the inspection authority and could also be accepted by the operators of nuclear power stations. The concept provides for uninterrupted control of the material balance areas of the nuclear power stations concerned, allows continuous control of the whole nuclear fuel cycle, is based exclusively on existing methods and facilities, and can be implemented at low cost. (orig.) [de

  5. Evaluation of scenery in power stations

    Wakatani, Yoshifumi; Yamamoto, Kimio


    In the location of power sources hereafter, the location in natural landscape away from urban district tends to increase, accordingly, it is necessary to investigate beforehand the influence to surrounding scenery. However, the method of predicting and evaluating the effect on scenery has not yet been established, therefore, in this study, the basic concept on the investigation, forecast and evaluation of the scenery in power stations was clarified, and the establishment of the work procedure to evaluate the scenery and the effectiveness of the method of forecast and evaluation were examined. Also, the problems when power station facilities exert influence on scenery and the countermeasures to them were considered. Psychological experiment was carried out on the method of evaluation, and the structure and the regulating factors of scenery evaluation were clarified. Recently, good living environment is desired by public, and to the problems of fine environment regarding power stations, more attention is paid. The scenery problems of power stations are the protection of nature and the preservation of good living environment. Since this is an undeveloped field, many problems to be examined still remain. (Kako, I.)

  6. Virginia power nuclear power station engineer training program

    Williams, T.M.; Haberstroh-Timpano, S.


    In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

  7. Nuclear Power Plant Fire Protection Research Program

    Datta, A.


    The goal is to develop test data and analytical capabilities to support the evaluation of: (1) the contribution of fires to the risk from nuclear power plants; (2) the effects of fires on control room equipment and operations; and (3) the effects of actuation of fire suppression systems on safety equipment. A range of fire sources will be characterized with respect to their energy and mass evolution, including smoke, corrosion products, and electrically conductive products of combustion. An analytical method for determining the environment resulting from fire will be developed. This method will account for the source characteristics, the suppression action following detection of the fire, and certain parameters specific to the plant enclosure in which the fire originates, such as the geometry of the enclosure and the ventilation rate. The developing local environment in the vicinity of safety-related equipment will be expressed in terms of temperatures, temperature rise rates, heat fluxes, and moisture and certain species content. The response of certain safe shutdown equipment and components to the environmental conditions will be studied. The objective will be to determine the limits of environmental conditions that a component may be exposed to without impairment of its ability to function

  8. Manual fire fighting tactics at Nuclear Power Plant

    Jee, Moon Hak; Moon, Chan Kook


    The general requirements of fire protection at nuclear power plant (NPP) are fire protection program, fire hazard analysis, and fire prevention features. In addition, specific fire protection requirements such as water supplies, fire detection, fire protection of safe related equipment, and safe shutdown capabilities must be provided. Particularly, manual fire fighting is required as specific requirements with the provisions to secure manual fire suppression, fire brigade and its training, and administrative controls for manual fire fighting. If a fire is alarmed and confirmed to be a real fire, the fire brigade must take manual fire fighting activities as requested at fire protection program. According to the present requirements in itself, there is not any specific manual fire fighting ways or practical strategies. In general, fire zones or compartments at NPPs are built in a confined condition. In theory, the fire condition will change from a combustible-controlled fire to a ventilation-governing fire with the time duration. In case of pool fire with the abundant oxygen and flammable liquid, it can take just a few minutes for the flash-over to occur. For the well-confined fire zone, it will change from a flame fire to a smoldering state before the entrance door is opened by the fire brigade. In this context, the manual fire fighting activities must be based on a quantitative analysis and a fire risk evaluation. At this paper, it was suggested that the fire zones at NPPs should be grouped on the inherent functions and fire characteristics. Based on the fire risk characteristics and the fire zone grouping, the manual fire fighting tactics are suggested as an advanced fire fighting solution

  9. Improvement of fire protection measures for nuclear power plants



    Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic Tool to actual plants (FDT{sup S}), With regard to fire tests for the fire data acquisition, cable fire test and High Energy Arcing Faults (HEAF) fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, and CFAST were implemented in order to analyze the fire progression phenomena. Trial simulation of HEAF accident of Onagawa NPP in Tohoku earthquake. (author)

  10. Lunar base thermoelectric power station study

    Determan, William; Frye, Patrick; Mondt, Jack; Fleurial, Jean-Pierre; Johnson, Ken; Stapfer, G.; Brooks, Michael D.; Heshmatpour, Ben


    Under NASA's Project Prometheus, the Nuclear Systems Program, the Jet Propulsion Laboratory, Pratt & Whitney Rocketdyne, and Teledyne Energy Systems have teamed with a number of universities, under the Segmented Thermoelectric Multicouple Converter (STMC) program, to develop the next generation of advanced thermoelectric converters for space reactor power systems. Work on the STMC converter assembly has progressed to the point where the lower temperature stage of the segmented multicouple converter assembly is ready for laboratory testing and the upper stage materials have been identified and their properties are being characterized. One aspect of the program involves mission application studies to help define the potential benefits from the use of these STMC technologies for designated NASA missions such as the lunar base power station where kilowatts of power are required to maintain a permanent manned presence on the surface of the moon. A modular 50 kWe thermoelectric power station concept was developed to address a specific set of requirements developed for this mission. Previous lunar lander concepts had proposed the use of lunar regolith as in-situ radiation shielding material for a reactor power station with a one kilometer exclusion zone radius to minimize astronaut radiation dose rate levels. In the present concept, we will examine the benefits and requirements for a hermetically-sealed reactor thermoelectric power station module suspended within a man-made lunar surface cavity. The concept appears to maximize the shielding capabilities of the lunar regolith while minimizing its handling requirements. Both thermal and nuclear radiation levels from operation of the station, at its 100-m exclusion zone radius, were evaluated and found to be acceptable. Site preparation activities are reviewed and well as transport issues for this concept. The goal of the study was to review the entire life cycle of the unit to assess its technical problems and technology

  11. Studying dynamics of indicators of nuclear power stations exploitation (the case of US nuclear power stations)

    Varshavsky, Leonid


    Analysis of external and internal factors influencing significant improvement of economic indicators of US nuclear power stations in the 1990s is carried out. Approaches to modeling dynamics of capacity factors of nuclear power stations are proposed. Comparative analysis of dynamics of capacity factors and occupational radiation exposure for various generations of US nuclear power plants is carried out. Dynamical characteristics of «learning by doing» effects for analyzed indicators are measu...

  12. Dosimetry systems in nuclear power stations

    Weidmann, U.


    In the following paper the necessity of the use of electronic dosimetry systems in nuclear power stations is presented, also encompassing the tasks which this type of systems has to fulfill. Based on examples the construction principles and the application possibilities of a PC supported system are described. 5 figs

  13. Water turbine technology for small power stations

    Salovaara, T.


    The paper examines hydro-power stations and the efficiency and costs of using water turbines to run them. Attention is given to different turbine types emphasizing the use of Kaplan-turbines and runners. Hydraulic characteristics and mechanical properties of low head turbines and small turbines, constructed of fully fabricated steel plate structures, are presented.

  14. Protection and safety of nuclear power stations



    The extreme requirements for the safety of nuclear power stations set tasks to the civil engineer which, resulting from dynamic load assumptions, among other things also demand the development of novel special concrete steels with a high elastic limit (here: DYWIDAG thread tie rod) for singly reinforced members. (orig.) [de

  15. Impact studies and nuclear power stations

    Chambolle, Thierry


    Impact studies form an essential part of environmental protection. The impact study discipline has enabled the EDF to have a better understanding of the effects of nuclear power stations on the environment and to remedy them at the project design stage [fr

  16. Reliability models for Space Station power system

    Singh, C.; Patton, A. D.; Kim, Y.; Wagner, H.


    This paper presents a methodology for the reliability evaluation of Space Station power system. The two options considered are the photovoltaic system and the solar dynamic system. Reliability models for both of these options are described along with the methodology for calculating the reliability indices.

  17. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Wilson, A.


    The methods of establishing construction time, capital cost, availability and lifetime of different types of generating plant are described. In volume one assessments are presented for a new coal fired station, for a new AGR station and for a new PWR station - Sizewell B. Volume two, contains all diagrams, tables and appendices presented as evidence. (U.K.)

  18. Toluene stability Space Station Rankine power system

    Havens, V. N.; Ragaller, D. R.; Sibert, L.; Miller, D.


    A dynamic test loop is designed to evaluate the thermal stability of an organic Rankine cycle working fluid, toluene, for potential application to the Space Station power conversion unit. Samples of the noncondensible gases and the liquid toluene were taken periodically during the 3410 hour test at 750 F peak temperature. The results obtained from the toluene stability loop verify that toluene degradation will not lead to a loss of performance over the 30-year Space Station mission life requirement. The identity of the degradation products and the low rates of formation were as expected from toluene capsule test data.

  19. Coal-fired power materials - Part II

    Viswanathan, V.; Purgert, R.; Rawls, P. [Electric Power Research Institute, Palo Alto, CA (United States)


    Part 1 discussed some general consideration in selection of alloys for advanced ultra supercritical (USC) coal-fired power plant boilers. This second part covers results reported by the US project consortium, which has extensively evaluated the steamside oxidation, fireside corrosion, and fabricability of the alloys selected for USC plants. 3 figs.

  20. Rocky Mountain Research Station 2008-2012 National Fire Plan Investments

    Erika Gallegos


    This report highlights selected accomplishments by the USDA Forest Service Rocky Mountain Research Station's Wildland Fire and Fuels Research & Development projects in support of the National Fire Plan from 2008 through 2012. These projects are examples of the broad range of knowledge and tools developed by National Fire Plan funding beginning in 2008.

  1. Fire social science research from the Pacific Southwest research station: studies supported by national fire plan funds

    Deborah J. Chavez; James D. Absher; Patricia L. Winter


    Fire events often have a large impact on recreation and tourism, yet these issues had not been addressed from a social science perspective. To address his, the Wildland Recreation and Urban Cultures Research Work Unit (RWU) of the Pacific Southwest Research Station acquired funding through the National Fire Plan within the community assistance topic area. The three...

  2. Practical design considerations for photovoltaic power station

    Swanson, T. D.

    Aspects of photovoltaic (PV) technology are discussed along with generic PV design considerations, taking into account the resource sunlight, PV modules and their reliability, questions of PV system design, the support structure subsystem, and a power conditioning unit subsystem. A description is presented of two recent projects which demonstrate the translation of an idea into actual working PV systems. A privately financed project in Denton, Maryland, went on line in early December, 1982, and began providing power to the local utility grid. It represents the first intermediate size, grid-connected, privately financed power station in the U.S. Based on firm quotes, the actual cost of this system is about $13/W peak. The other project, called the PV Breeder, is an energy independent facility which utilizes solar power to make new solar cells. It is also the first large industrial structure completely powered by the sun.

  3. Training of fire protection personnel in nuclear power plants

    Blaser, W.


    Training of fire protection personnel in nuclear power plants is divided up in three categories: training of fire protection commissioners which is mostly carried out externally; training of fire fighting personnel in the form of basic and repeated training usually by the fire protection commissioner; training of other employers with regard to behaviour in case of fire and during work involving a fire hazard. (orig.) [de

  4. Operating experience at Scottish Nuclear's power stations

    Blackburn, P.


    A brief history is presented of the design and operation of the four Scottish nuclear power stations currently run by Scottish Nuclear, namely Hunterston 'A' and 'B' and the Torness reactors. A design flaw in the Magnox reactor at Hunterston 'A' led to it being operated at lower than optimal temperature and hence producing less power. For Hunterston 'B' reactor the Advanced Gas Cooled design prototype was used. Operating setbacks and successes are noted. The design chosen for Torness embraced all the good points of Hunterston 'B' but sought to eliminate its faults. After 26 years of successful operation Hunterston 'A' is now being decommissioned, while the other three stations continue to generate electricity successfully. (UK)

  5. Safety planning for nuclear power stations

    Tadmor, J.


    The article shows that compared to the many industries and other human activities, nuclear power stations are among the safest. A short description of the measures taken to prevent accidents and of the additional safety means entering into action if an accident does occur is presented. It is shown that in nuclear plants the death frequency following malfunctioning is 1 death in 100.000 years whereas deaths following other human activities is 1 in 2 to 100 years and following natural calamities like earthquakes and floods is 1 in 10 years. As an example it is shown that for a population of 15.000.000 living in a radius of 40 km around 100 power stations the average number of deaths will be of 2 per year as compared to 4200 from road accidents with the corresponding number of injuries of 20 and 375.000 respectively. (B.G.)

  6. Dynamics and control in nuclear power stations

    Butterfield, M.H.


    This volume presents a wide view of aspects of control of nuclear power stations by taking into consideration the plant as a whole and the protection systems employed therein. Authors with worldwide experience consider all aspects of dynamics and control in the context of both fast and thermal power stations. The topics discussed include the methods of development and applications within the analysis of plant behaviour, the validation of mathematical models, plant testing, and the design and implementation of controls. There are 27 papers all of which are indexed separately; steady states and model evolution (5 papers), control and protection systems (5 papers), transients (7 papers), testing and data (3 papers), model validation (6 papers) and commissioning and operation (1 paper). (author)

  7. The decommissioning of nuclear power stations

    Barker, F.


    This report has been commissioned by the National Steering Committee of Nuclear Free Local Authorities to provide: a comprehensive introduction to the technical, social, political, environmental and economic dimensions to nuclear power station decommissioning; an independent analysis of Nuclear Electric's recent change of decommissioning strategy; the case for wider public involvement in decision making about decommissioning; and a preliminary assessment of the potential mechanisms for achieving that essential wider public involvement

  8. Technological development of Guangdong nuclear power station

    Huang Shiqiang


    After over 5 years of operations, the Guangdong Nuclear Power Station (GNPS) has achieved good results both economically and in operational safety performance. The main attributes to the success of the plant operational performances include the equipment reliability, the technical capability and management efficiency. To that the key strategy has been to adopt know-how and technological transfer and encourage self-innovation, aiming to strive for the long-term self-reliance in design, manufacturing and operating the plant. (author)

  9. Requirement profile for nuclear power station personnel

    Roeglin, H.C.


    The starting point in deriving the requirement profile for the shift personnel in the control rooms of nuclear power stations is information of a technical, organisational and ergonomic kind. The technique used, the distribution of work to different work areas and the configuration of the workplace is determined by the tasks and the environmental conditions in which they have to be done. (orig./DG) [de

  10. Front against the Temelin nuclear power station



    Though the main concern of the author is the Czechoslovakian Temelin power station, the main target of his attacks are the Austrian proponents of nuclear energy i.e. the Reactor Safty Commission and the Austrian Chancellor. The newly opened possibility of anti-nuclear propaganda in the CSFR, by Greenpeace and the author's organisation is welcomed. The number of signatures collected against Temelin is given as 350.000. 815 signatures come from Japan: a facsimile of some Japanese signatures is presented

  11. Thermodynamic power stations at low temperatures

    Malherbe, J.; Ployart, R.; Alleau, T.; Bandelier, P.; Lauro, F.

    The development of low-temperature thermodynamic power stations using solar energy is considered, with special attention given to the choice of the thermodynamic cycle (Rankine), working fluids (frigorific halogen compounds), and heat exchangers. Thermomechanical conversion machines, such as ac motors and rotating volumetric motors are discussed. A system is recommended for the use of solar energy for irrigation and pumping in remote areas. Other applications include the production of cold of fresh water from brackish waters, and energy recovery from hot springs.

  12. Efficiency of a small wind power station

    Ivanov, K.; Christov, Ch.; Kozarev, N.


    The aim of the study is to obtain the optimal solution for wind station both by technical parameters and costs. The energetic characteristics of the wind as a renewable energy source are discussed and assessment of the economical efficiency is made. For the determination of the optimal wind parameters the method of integral wind curves is used. The low power wind generators (0.4 - 1.5 kW) are considered as optimal for the presented wind characteristics

  13. Community reaction to noise from power stations

    Job, R.F.S.; Hede, A.J.


    Community reaction is a major consideration in noise control. The relationship between noise exposure and community reaction has received considerable attention in relation to railway, traffic, aircraft and impulsive noise. The results have shown a number of features in common, including: similarly shaped noise/reaction functions; similar results across different measurement techniques and cultures, noise/reaction correlations based on individual respondent data are low (mean r = 0.42 ± 0.12: Job, 1988), although correlations of .58 and above have been reported correlations based on data grouped by noise exposure are generally high and relatively unaffected by the type of noise studied whereas correlations based on individual data tend to be lower for impulsive noise than for transportation noise attitude to the noise source and sensitivity to noise shows strong correlations with reaction. This paper reports that the present study was undertaken in order toe establish over a wider range of noise exposure whether community reaction to power station noise is similar to reaction to other types of non-impulsive noise. It is possible that reaction is different given important differences in the source of the noise which may affect attitude. Attitudes towards power stations may be more positive than attitudes to aircraft or rail noise for example, because almost all respondents use electricity regularly every day. Further, the power stations in the present study provided employment for the relatively small surrounding communities

  14. High pressure axial flow fans for modern coal power stations

    Cyrus, Vaclav [AHT Energetika s.r.o., Praha (Czech Republic); Koci, Petr [ZVVZ Milevsko a.s. (Czech Republic)


    Brown coal fired power stations, located in Northern Bohemia, have mostly older boiler blocks with an output of 110 and 200 MWe. Flue gases are cleaned by the desulphurization plants installed between 1993 and 1997. Usually, each boiler block has two air fans and one to three flue gas fans. Flue gas fans operate in severe conditions; fan blades should be resistant to the flue gases containing sulphur and acid drops with the operating temperature at 170 C to 190 C. Additionally, flue gas also often contains ash particles. Currently, some boiler blocks are gradually being refurbished. New blocks with an electrical power output of 600 to 700 MWe are at the design stage. Submitted paper shows our design study of one stage axial flow fan for the new blocks. Results from the new aerodynamic research of the axial flow stages were used in the fan design. (orig.)

  15. Contamination Impact of Station Brush Fire on Cleanroom Facilities

    Carey, Phil; Blakkolb, Brian


    Brush and forest fires, both naturally occurring and anthropogenic in origin, in proximity to space flight hardware processing facilities raise concerns about the threat of contamination resulting from airborne particulate and molecular components of smoke. Perceptions of the severity of the threat are possibly heightened by the high sensitivity of the human sense of smell to some components present in the smoke of burning vegetation.On August 26th, 2009, a brushfire broke out north of Pasadena, California, two miles from the Jet Propulsion Laboratory. The Station Fire destroyed over 160,000 acres, coming within a few hundred yards of JPL. Smoke concentrations on Lab were very heavy over several days. All Lab operations were halted, and measures were taken to protect personnel, critical hardware, and facilities. Evaluation of real-time cleanroom monitoring data, visualinspection of facilities, filter systems, and analysis of surface cleanliness samples revealed facility environments andhardware were minimally effected.Outside air quality easily exceeded Class Ten Million. Prefilters captured most large ash and soot; multi-stage filtration greatly minimized the impact on the HEPA/ULPA filters. Air quality in HEPA filtered spacecraft assembly cleanrooms remained within Class 10,000 specification throughout. Surface cleanliness was inimally affected, as large particles were effectively removed from the airstream, and sub-micron particles have extremely long settling rates. Approximate particulate fallout within facilities was 0.00011% area coverage/day compared to 0.00038% area coverage/day during normal operations. Deposition of condensable airborne components, as measured in real time, peaked at approximately1.0 ng/cm2/day compared to 0.05 ng/cm2/day nominal.

  16. Fire protection in nuclear power plants


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

  17. Emissions from coal-fired electric stations : environmental health effects and reduction options

    Love, P.; Lourie, B.; Pengelly, D.; Labatt, S.; Ogilvie, K.; Kelly, B.


    Findings of a study on the environmental effects of current emissions from coal-fired electric stations were summarized. Current and projected emissions from coal-fired electric stations for five emission reduction scenarios were estimated for Ontario, Eastern Canada, Ohio Valley/Great Lakes, and the U.S. northeast regions. Coal-fired electric stations generate a wide range of environmentally significant air emissions. The five pollutants selected - sulphur dioxide, nitrogen oxides, particulate matter (less than 10 micrometres in size), mercury, and carbon dioxide - are considered to impact most on environmental health. This report focused on 312 coal-fired electric stations in the regions named above. They were selected based on the likelihood that long-range transport of the emissions from these coal-fired utilities would have an impact on human health and the environment. 55 refs., 10 tabs., 8 figs

  18. Circulating water pumps for nuclear power stations

    Satoh, Hiroshi; Ohmori, Tsuneaki


    Shortly, the nuclear power station with unit power output of 1100 MW will begin the operation, and the circulating water pumps manufactured recently are those of 2.4 to 4 m bore, 840 to 2170 m 3 /min discharge and 2100 to 5100 kW driving power. The circulating water pumps are one of important auxiliary machines, because if they fail, power generation capacity lowers immediately. Enormous quantity of cooling water is required to cool condensers, therefore in Japan, sea water is usually used. As siphon is formed in circulating water pipes, the total head of the pumps is not very high. The discharge of the pumps is determined so as to keep the temperature rise of discharged water lower than 7 deg. C. The quantity of cooling water for nuclear power generation is about 50% more as compared with thermal power generation because of the difference in steam conditions. The total head of the pumps is normally from 8 to 15 m. The circulating water pumps rarely stop after they started the operation, therefore it is economical to determine the motor power so that it can withstand 10% overload for a short period, instead of large power. At present, vertical shaft, oblique flow circulating water pumps are usually employed. Recently, movable blade pumps are adopted. The installation, construction and materials of the pumps and the problems are described. (Kako, I.)

  19. Fire protection at the Mochovce nuclear power plant

    Molnarova, Zuzana; Zeman, Peter


    A succinct account is given of current situation in fire prevention at the Mochovce NPP and of past fire events. The fact is stressed that no fire ever occurred at any technological facility of the plant since the startup of the reactor units. Steps required to improve fire safety at a nuclear power plant are highlighted. (orig.)

  20. Care management at Ikata Power Station

    Sakai, Koji


    For operating nuclear power stations safely and economically, it is necessary to control nuclear fuel itself and reactor cores. Nuclear fuel must be controlled consistently in view of quantitative balance and operational method over the whole nuclear fuel cycle of uranium ore, fabrication, burning in reactors and reprocessing, based on the plan of using fuel in electric power companies. The control of the burning in reactors is called core management, and it is important because the users of fuel execute it. For dealing with such core management works, Shikoku Electric Power Co., Inc., has developed the computer code system for grasping the state of fuel exchange and the burning condition in reactors and used it since 1972. The outline of the core management in Ikata Power Station is reported in this paper centering around computing works. The core management works are divided into those at the time of regular inspection and those in operation. In the regular inspection, fuel inspection, fuel exchange and reactor physics test are performed. In operation, the burning condition of fuel is grasped. The technical computations corresponding to these works are explained, and the examples of computations are shown. (Kako, I.)

  1. Obrigheim nuclear power station. Annual report 1987

    Koerner, C.


    The Obrigheim nuclear power station was operated at full load during the year 1987; 7.351 operating hours procuded electrical energy of 2.607 GWh. This is the fifth best annual result during Obrigheim's operating period. Since commissioning in October 1968, 139.310 hours of operation have generated 46.681 GWh (gross) and from test operation in March 1969 until the end of 1987, 138.530 hours of operation have generated 46.569 GWh. This is an availability of power of 81.6% in this period and a time availability of 83.9%. In 1987, the plant was shut down for 1.222 hours for the 18th refueling including testing, inspection and repair work. Apart from refueling, the plant had a good time availability and therefore contributed 5% to the safe, economical and environmentally acceptable electricity supply of the Land Baden-Wuerttemberg. The power station is of great significance to the region, both in terms of power supply and the economy. (orig./HP) [de

  2. Vacuum switchgear for power station auxiliary switchboards

    Coombs, P.E.


    Sizewell B is the first UK power station in which vacuum switchgear is used for the auxiliary switchboards. Previously the 3.3kV, 6.6kV or 11kV switchgear has used air-break circuit breakers and fused air-break contactors, known as motor starting devices or fused switching devices (FSD). The use of vacuum interrupters is therefore a new technology in this application, although it has been established in the UK distribution network and in industrial installations from the mid 1970s. Vacuum switchgear was already in use in the USA for power station auxiliary switchgear at the time that it was proposed for Sizewell B. The Sizewell B high voltage auxiliary switchgear comprises eight Unit and Station Auxiliary Switchboards at 3.3kV and 11kV, and four 3.3kV Essential Switchboards for the essential safety related circuits, making a total of 65 circuit breakers plus FSD panels. (Author)

  3. Managing nuclear power stations for success

    Smith, G.


    Ontario Power Generation's (OPG) top operational priority is to manage its nuclear assets to ensure they operate as safely, efficiently and cost effectively as possible. In meeting these objectives, the company is focused on continuously improving its nuclear performance and benchmarking that performance against the best in North America. This presentation explores how OPG is improving its nuclear performance and the steps it is taking to sustain performance success going forward. Topics to be discussed include the measures OPG is taking to enhance human performance and station reliability as well as the company's preparations to determine if a business case exists for extending the lives of the Pickering B and eventually the Darlington nuclear stations. (author)

  4. Lifetime management of Magnox power stations

    Smitton, C.


    Magnox Electric, which is, a subsidiary of BNFL, operates six nuclear power plants that have an average age of about 33 years. The procedures developed to maintain the plants and ensure nuclear safety in longer-term operation are reviewed. The technical limit on station lifetimes is expected to be determined by the effect of ageing on major reactor structures where replacement is impractical. Examination of the effect of ageing confirms that the stations are capable of operating to a life of at least 40 years. The economic factors affecting operation are reviewed, recognising the need to sell electricity in a competitive market. Recently Magnox Electric and BNFL have merged and all plant supporting Magnox operations are now within a single integrated company that will provide further opportunities for improved efficiency. (author)

  5. Dealing with operational power station wastes

    Pepper, R B [Central Electricity Generating Board, London (UK). Nuclear Health and Safety Dept.


    The disposal of wastes from nuclear power stations is discussed. Liquid and gaseous wastes, from magnox stations, which are of low level activity, are dispersed to the sea or estuaries on coastal sites or for the case of Trawfynyeld, to the nearby lake. Low activity solid wastes are either disposed of on local authority tips or in shallow land burial sites. Intermediate level wastes, consisting mainly of wet materials such as filter sludges and resins from cooling ponds, are at present stored in shielded storage tanks either dry or under water. Only one disposal route for intermediate waste is used by Britain, namely, sea-dumping. Materials for sea dumping have to be encapsulated in a durable material for example, concrete.

  6. The deposition of trace elements in the environs of a power station

    Godbeer, W.C.; Swaine, D.J.


    The fate of trace elements during combustion is discussed, followed by the deposition of trace elements from the atmosphere and from coal firing. Methods of measuring deposition are described. Data from a four year long investigation of deposition around the Wallerawang power station is given. Sphagnum moss was used as a collector. 74 refs., 8 figs., 5 tabs

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


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

  8. ALARA organization in nuclear power stations

    Dollo, R.


    EDF's nuclear power stations were built with provisions being made, as from the design stage, to limit radiation sources and the results observed over the first ten years (annual collective dose and dose per unit of less than 2 man.Sv) were considered to be very good. However, these results began to deteriorate from 1988 onwards. At the same time, considerable progress was being made by other generators of electricity, who were achieving results which were better than those achieved by our later units. Furthermore, radiological protection standards are being revised and personal dose limits will soon be lowered. (authors)

  9. Economical dismantling of nuclear power stations

    Mallok, J.; Andermann, H.


    The dismantling of nuclear power stations requires a high degree of security and economic efficiency due to the strong contamination of components and the close spatial conditions. In order to protect involved staff from radiation, modern remote-controlled technology is applied in sectors with heavy radioactive contamination such as reactor pressure vessels. The article shows, that the dismantling of reactor pressure vessels using a remote-controlled milling machine developed by the Siemens subsidiary Mechanik Center Erlangen GmbH, can be done in a secure and efficient way. (orig.) [de

  10. Multivariable control in nuclear power stations

    Parent, M.; McMorran, P.D.


    Multivariable methods have the potential to improve the control of large systems such as nuclear power stations. Linear-quadratic optimal control is a multivariable method based on the minimization of a cost function. A related technique leads to the Kalman filter for estimation of plant state from noisy measurements. A design program for optimal control and Kalman filtering has been developed as part of a computer-aided design package for multivariable control systems. The method is demonstrated on a model of a nuclear steam generator, and simulated results are presented

  11. Pilot plant experiments at Wairakei Power Station

    Brown, Kevin L.; Bacon, Lew G.


    In the mid-1990s, several pilot plants were constructed at Wairakei to either improve the operational and economic performance of the power station or to mitigate the environmental effects of discharges to the Waikato River. The results of the following investigations are discussed: (1) fluid flow dynamic effects on silica scaling; (2) production of silica sols of predetermined particle size to evaluate the potential for generating commercial grade silica products; (3) use of 'sulfur oxidising bacteria' for the abatement of dissolved hydrogen sulphide in cooling water; (4) removal of arsenic from separated geothermal water; (5) steam line condensate corrosion; and (6) measurement and modelling of steam scrubbing in Wairakei's long steamlines. (author)

  12. CEGB nuclear power stations basic emergency plan


    The introduction states that this is a typical emergency plan for a nuclear power station employing about 500 people, having two reactors and a total electrical output of 500 Megawatts in an intensively farmed rural area. The document has the following headings: definitions ('site incident', etc); functions of the site emergency organization; conditions for taking emergency action; persons empowered to declare or cancel a site incident or an emergency; emergency actions by staff; control centres; communication; collaboration with other bodies; warnings; transport; house rules; public information centre. (U.K.)

  13. thermal power stations' reliability evaluation in a hydrothermal system

    Dr Obe

    A quantitative tool for the evaluation of thermal power stations reliability in a hydrothermal system is presented. ... (solar power); wind (wind power) and the rest, thermal power and ... probability of a system performing its function adequately for ...

  14. Solar dynamic power systems for space station

    Irvine, Thomas B.; Nall, Marsha M.; Seidel, Robert C.


    The Parabolic Offset Linearly Actuated Reflector (POLAR) solar dynamic module was selected as the baseline design for a solar dynamic power system aboard the space station. The POLAR concept was chosen over other candidate designs after extensive trade studies. The primary advantages of the POLAR concept are the low mass moment of inertia of the module about the transverse boom and the compactness of the stowed module which enables packaging of two complete modules in the Shuttle orbiter payload bay. The fine pointing control system required for the solar dynamic module has been studied and initial results indicate that if disturbances from the station are allowed to back drive the rotary alpha joint, pointing errors caused by transient loads on the space station can be minimized. This would allow pointing controls to operate in bandwidths near system structural frequencies. The incorporation of the fine pointing control system into the solar dynamic module is fairly straightforward for the three strut concentrator support structure. However, results of structural analyses indicate that this three strut support is not optimum. Incorporation of a vernier pointing system into the proposed six strut support structure is being studied.

  15. Gas-fired electric power generating technologies


    The workshop that was held in Madrid 25-27 May 1994 included participation by experts from 16 countries. They represented such diverse fields and disciplines as technology, governmental regulation, economics, and environment. Thus, the participants provided an excellent cross section of key areas and a diversity of viewpoints. At the workshop, a broad range of topics regarding gas-fired electric power generation was discussed. These included political, regulatory and financial issues as well as more specific technical questions regarding the environment, energy efficiency, advanced generation technologies and the status of competitive developments. Important technological advances in gas-based power and CHP technologies have already been achieved including higher energy efficiency and lower emissions, with further improvements expected in the near future. Advanced technology trends include: (a) The use of gas technology to reduce emissions from existing coal-fired power plants. (b) The wide-spread application of combined-cycle gas turbines in new power plants and the growing use of aero-derivative gas turbines in CHP applications. (c) Phosphoric acid fuel cells that are being introduced commercially. Their market penetration will grow over the next 10 years. The next generation of fuel cells (solid oxide and molten carbonate) is expected to enter the market around the year 2000. (EG)

  16. Iodine filters in nuclear power stations

    Wilhelm, J.G.


    On the basis of calculated and recorded release rates of nuclear power plants, the significance of iodine releases in the invironmental impact relative to other nuclides is discussed. The release pathways for iodine in LWR-type reactors and the efficiency of various methods to lower the activity release are given. The airborne species of iodine are discussed with regard to their removal in iodine sorption filters and environmental impact. The technical status of iodine removal by means of iodine sorption filters is studied for normal operation and accident conditions in nuclear power stations on the basis of the data given in the relevant literature for the efficiency of a number of iodine sorption materials. The applicability of concepts for ventilation and containment and their influence on iodine filter systems are discussed. Design, structure, and testing of iodine sorption filters are treated in detail; recommendations for design are given, and failure sources are mentioned. (orig.) [de

  17. The regional issues involved in the siting of power stations

    Livingstone, R.


    This paper deals with the regional implications of power station siting in England and Wales and refers to the procedures used by the CEGB to find and develop sites. The resources required for a power station are outlined both for conventional and nuclear stations and the possible development of uses for the rejected heat from power stations as a result of the energy crisis is discussed. (U.K.)

  18. Forecasting Canadian nuclear power station construction costs

    Keng, C.W.K.


    Because of the huge volume of capital required to construct a modern electric power generating station, investment decisions have to be made with as complete an understanding of the consequences of the decision as possible. This understanding must be provided by the evaluation of future situations. A key consideration in an evaluation is the financial component. This paper attempts to use an econometric method to forecast the construction costs escalation of a standard Canadian nuclear generating station (NGS). A brief review of the history of Canadian nuclear electric power is provided. The major components of the construction costs of a Canadian NGS are studied and summarized. A database is built and indexes are prepared. Based on these indexes, an econometric forecasting model is constructed using an apparently new econometric methodology of forecasting modelling. Forecasts for a period of 40 years are generated and applications (such as alternative scenario forecasts and range forecasts) to uncertainty assessment and/or decision-making are demonstrated. The indexes, the model, and the forecasts and their applications, to the best of the author's knowledge, are the first for Canadian NGS constructions. (author)

  19. Regulatory experience in nuclear power station decommissioning

    Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.


    In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

  20. Siting technology of underground nuclear power station

    Motojima, M.; Hibino, S.


    For the site of a nuclear power station, it may be possible to select a seaside mountain area, if the condition is suitable to excavate large rock caverns in which a reactor and other equipments are installed. As the case study on the siting technology for an underground nuclear power station, the following example was investigated. The site is a seaside steep mountain area, and almost all the equipments are installed in plural tunnel type caverns. The depth from the ground surface to the top of the reactor cavern is about 150 m, and the thickness of the rock pillar between the reactor cavern of 33 m W x 82 mH x 79 mD and the neighboring turbine cavern is 60 m. In this paper, the stability of rock caverns in this example, evaluated by numerical analysis, is described. The numerical analysis was carried out on the central cross section of the reactor cavern, taking the turbine cavern, geostress, the mechanical properties of rock mass and the process of excavation works in consideration. By the analysis, the underground caverns in this example were evaluated as stable, if the rock quality is equivalent to C H class or better according to the CRIEPI rock classification. (K.I.)

  1. Fire Risk Scoping Study: Investigation of nuclear power plant fire risk, including previously unaddressed issues

    Lambright, J.A.; Nowlen, S.P.; Nicolette, V.F.; Bohn, M.P.


    An investigation of nuclear power plant fire risk issues raised as a result of the USNRC sponsored Fire Protection Research Program at Sandia National Laboratories has been performed. The specific objectives of this study were (1) to review and requantify fire risk scenarios from four fire probabilistic risk assessments (PRAs) in light of updated data bases made available as a result of USNRC sponsored Fire Protection Research Program and updated computer fire modeling capabilities, (2) to identify potentially significant fire risk issues that have not been previously addressed in a fire risk context and to quantify the potential impact of those identified fire risk issues where possible, and (3) to review current fire regulations and plant implementation practices for relevance to the identified unaddressed fire risk issues. In performance of the fire risk scenario requantifications several important insights were gained. It was found that utilization of a more extensive operational experience base resulted in both fire occurrence frequencies and fire duration times (i.e., time required for fire suppression) increasing significantly over those assumed in the original works. Additionally, some thermal damage threshold limits assumed in the original works were identified as being nonconservative based on more recent experimental data. Finally, application of the COMPBRN III fire growth model resulted in calculation of considerably longer fire damage times than those calculated in the original works using COMPBRN I. 14 refs., 2 figs., 16 tabs

  2. 76 FR 46330 - NUREG-1934, Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG); Second Draft...


    ... NUCLEAR REGULATORY COMMISSION [NRC-2009-0568] NUREG-1934, Nuclear Power Plant Fire Modeling... 1023259), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft Report for...), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft for Comment,'' is...

  3. Nuclear power plants: a unique challenge to fire safety

    Nowlen, S.P.


    The evaluation of fire safety in a nuclear power plant must include the consideration of the impact of a fire on the operability of plant safety equipment and systems. This issue is not typical of the life safety and property protection issues which dominate traditional fire safety concerns. This paper provides a general discussion of the issue of nuclear power plant fire safety as it currently exists in the USA. Included is a discussion of the past history of nuclear power plant fire events, the development of nuclear industry specific fire safety guidelines, the adverse experience associated with the inadvertent operation of fire suppression systems, and the anticipated direction of fire safety requirements for future reactor designs in the USA. (Author)

  4. Prospects for using the technology of circulating fluidized bed for technically refitting Russian thermal power stations

    Ryabov, G. A.; Folomeev, O. M.; Litun, D. S.; Sankin, D. A.; Dmitryukova, I. G.


    The present state and development of circulating fluidized bed (CFB) technology around the world are briefly reviewed. Questions of increasing the capacity of single boiler units and raising the parameters of steam are discussed. CFB boilers for 225- and 330-MW power units are described and their parameters are estimated as applied to the conditions of firing different Russian fuels. Indicators characterizing CFB boilers and pulverized-coal boilers are given. Capital outlays and operational costs for new coal-fired units are compared, and the results from this comparison are used to show the field of the most promising use of the CFB technology during technical refitting of Russian thermal power stations.

  5. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Arnold, P.J.


    The systems benefits of the selection of the Sizewell site for a PWR power station are dealt with. The transmission modifications which would be needed to provide effective connection of this station to the system are considered. (U.K.)

  6. Operating experience of Fugen Nuclear Power Station

    Ohteru, Shigeru; Kaneko, Jun; Kawahara, Toshio; Matsumoto, Mitsuo


    The prototype ATR 'Fugen' developed as one of the national project has verified the performance and reliability of the advanced thermal reactor system through the operation for about eight years since 1979, and the elucidation of the characteristics in plutonium utilization and the development and verification of the tuilizing techniques have been advanced. Besides, the operational results and the achievement of the technical development are successively reflected to the design of a demonstration reactor. In this paper, the outline of Fugan and the operational results are reported. The ATR Fugen Power Station is that of the prototype reactor of heavy water moderated, boiling light water cooled, pressure tube type, having the electric output of 165 MW. It started the full scale operation on March 20, 1979, and as of January, 1987, the total generated electric power reached about 7 billion kWh, the time of power generation was about 43,000 h, and the average capacity factor was 60.6 %. Plutonium utilization techniques, the flow characteristics and the dynamic plant characteristics of a pressure tube type reactor, the operational characteristics of a heavy water system and the techniques of handling heavy water containing tritium, and the operational reliability and maintainability of the machinery and equipment installed have been studied. (Kako, I.)

  7. Drivers of biomass co-firing in U.S. coal-fired power plants

    Michael E. Goerndt; Francisco X. Aguilar; Kenneth Skog


    Substantial knowledge has been generated in the U.S. about the resource base for forest and other residue-derived biomass for bioenergy including co-firing in power plants. However, a lack of understanding regarding power plant-level operations and manager perceptions of drivers of biomass co-firing remains. This study gathered information from U.S. power plant...

  8. Nuclear power station main control room habitability

    Paschal, W.B.; Knous, W.S.


    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

  9. Living near a nuclear power station

    Marcan, P.; Slovak, K.


    The need to expand nuclear power and its advantages are discussed publicly nearly each week. According to politicians and the nuclear lobby investing tens of billions Sk at Mochovce will bring Slovakia the often cited 'independence and energy self-sufficiency'. It will also mean profit for Slovenske elektrarne and the company's shareholders - the state and Italian company, Enel. In addition to the lively discussion on the pros and cons of nuclear energy, TREND was also interested in the living conditions around the concrete and strictly guarded, potentially dangerous plants and in the opinion of the people most affected by Mochovce and Jaslovske Bohunice on expansion of the existing and the building of new nuclear power plants. The construction of nuclear powers stations in these regions was not only about new jobs. The state 'prescribed' iodine pills and did not allow any construction in the region and, in the case of Mochovce, ordered the complete demolition of a village. The only thing that remained from Mochovce village was the church. 'And when it was found that the power plant would not reach it, it was even given a new roof. Former inhabitants, especially the older ones that had problems accepting the evacuation, used to visit it often,' explained Jan Foldy, the head of the local municipality in Kalna nad Hronom. After many years, life in the neighbouring villages is not bad. Their budgets are overflowing and so they can afford to spoil their inhabitants with free cable TV and high standard sport facilities, which should partly compensate for the fact that the people are living so close to a nuclear facility. (authors)

  10. Fire protection system HMI in power plant

    Zainal, Yuda Bakti


    The central power station, a place where there are machines that generate power, equipped with substation where the voltage is produced by the generator and increased to a certain voltage with a step up voltage transformer. Effect on transformer oil is very important, transformer may malfunction if the oil that serves as a coolant and insulator gradually decreased its ability, over time their use. Power transformer on usability is vital, so it needs to be maintained so that the temperature rise must be overcome by applying a temperature control that can inform and control the control valve to open the hydrant tap transformer cooling. HMI implemented to facilitate the operators cope with excess heat in the transformer using thermocouple censor. Test results show that the control transformer and monitored using PLC and HMI. Transformer can maintain the condition of a maximum of 80 degrees Celsius heat.

  11. Study of methodology for low power/shutdown fire PSA

    Yan Zhen; Li Zhaohua; Li Lin; Song Lei


    As a risk assessment technology based on probability, the fire PSA is accepted abroad by nuclear industry in its application in the risk assessment for nuclear power plants. Based on the industry experience, the fire-induced impact on the plant safety during low power and shutdown operation cannot be neglected, therefore fire PSA can be used to assess the corresponding fire risk. However, there is no corresponding domestic guidance/standard as well as accepted analysis methodology up to date. Through investigating the latest evolvement on fire PSA during low power and shutdown operation, and integrating its characteristic with the corresponding engineering experience, an engineering methodology to evaluate the fire risk during low power and shutdown operation for nuclear power plant is established in this paper. In addition, an analysis demonstration as an example is given. (authors)

  12. Valves for condenser-cooling-water circulating piping in thermal power station and nuclear power station

    Kondo, Sumio


    Sea water is mostly used as condenser cooling water in thermal and nuclear power stations in Japan. The quantity of cooling water is 6 to 7 t/sec per 100,000 kW output in nuclear power stations, and 3 to 4 t/sec in thermal power stations. The pipe diameter is 900 to 2,700 mm for the power output of 75,000 to 1,100,000 kW. The valves used are mostly butterfly valves, and the reliability, economy and maintainability must be examined sufficiently because of their important role. The construction, number and arrangement of the valves around a condenser are different according to the types of a turbine and the condenser and reverse flow washing method. Three types are illustrated. The valves for sea water are subjected to the electrochemical corrosion due to sea water, the local corrosion due to stagnant water, the fouling by marine organisms, the cavitation due to valve operation, and the erosion by earth and sand. The fundamental construction, use and features of butterfly valves are described. The cases of the failure and repair of the valves after their delivery are shown, and they are the corrosion of valve bodies and valve seats, and the separation of coating and lining. The newly developed butterfly valve with overall water-tight rubber lining is introduced. (Kako, I.)

  13. Cable fire risk of a nuclear power plant

    Aulamo, H.


    The aim of the study is to carry out a comprehensive review of cable fire risk issues of nuclear power plants (NPP) taking into account latest fire and risk assessment research results. A special emphasis is put on considering the fire risk analysis of cable rooms in the framework of TVO Olkiluoto NPP probabilistic safety assessment. The assumptions made in the analysis are assessed. The literature study section considers significant fire events at nuclear power plants, the most severe of which have nearly led to a reactor core damage (Browns Ferry, Greifswald, Armenia, Belojarsk, Narora). Cable fire research results are also examined

  14. Fire fighting precautions at Bohunice Atomic Power Plants



    Some shortcomings are discussed of the project design of fire protection at the V-1 and V-2 nuclear power plants. The basic shortcoming of the system is insufficient division of the units for fire protection. Fire fighting measures are described for cable areas, switch houses and outside transformers, primary and secondary circuits and auxiliary units. Measures are presented for increasing fire safety in Jaslovske Bohunice from experience gained with a fire which had occurred at a nuclear power plant in Armenia. (E.S.)

  15. Particular features of fire protection in nuclear power plants

    Krueger, W.


    The particular features of fire protection in nuclear power plants that are connected with the need to ensure nuclear and radiation safety even during an emergency are outlined followed by the recommendation to lay them down in special fire protection standards. These, in conjunction with comprehensive fire hazard analyses, could serve to work out complex concepts for the fire protection of individual nuclear power plants. Such concepts would be very useful for review and assessment of the fire protection design during the licensing process and for later inspections. (author)

  16. Cable fire risk of a nuclear power plant; Ydinvoimalaitoksen kaapelipaloriski

    Aulamo, H.


    The aim of the study is to carry out a comprehensive review of cable fire risk issues of nuclear power plants (NPP) taking into account latest fire and risk assessment research results. A special emphasis is put on considering the fire risk analysis of cable rooms in the framework of TVO Olkiluoto NPP probabilistic safety assessment. The assumptions made in the analysis are assessed. The literature study section considers significant fire events at nuclear power plants, the most severe of which have nearly led to a reactor core damage (Browns Ferry, Greifswald, Armenia, Belojarsk, Narora). Cable fire research results are also examined. 62 refs.

  17. Nuclear power plant fire protection: philosophy and analysis

    Berry, D.L.


    This report combines a fire severity analysis technique with a fault tree methodology for assessing the importance to nuclear power plant safety of certain combinations of components and systems. Characteristics unique to fire, such as propagation induced by the failure of barriers, have been incorporated into the methodology. By applying the resulting fire analysis technique to actual conditions found in a representative nuclear power plant, it is found that some safety and nonsafety areas are both highly vulnerable to fire spread and impotant to overall safety, while other areas prove to be of marginal importance. Suggestions are made for further experimental and analytical work to supplement the fire analysis method

  18. TEPCO plans to construct Higashidori Nuclear Power Station

    Tsuruta, Atsushi


    In 2006, TEPCO submitted to the government plans for the construction of Higashidori Nuclear Power Station. The application was filed 41 years after the project approved by the Higashidori Village Assembly. This nuclear power station will be the first new nuclear power plant constructed by TEPCO since the construction of Units No.6 and 7 at the Kashiwazaki Kariwa Nuclear Power Station 18 years ago. Higashidori Nuclear Power Station is to be constructed at a completely new site, which will become the fourth TEPCO nuclear power station. Higashidori Nuclear Power Station Unit No.1 will be TEPCO's 18th nuclear reactor. Unit No.1 will be an advanced boiling water reactor (ABWR), a reactor-type with a proven track record. It will be TEPCO's third ABWR. Alongside incorporating the latest technology, in Higashidori Nuclear Power Station Unit No.1, the most important requirement is for TEPCO to reflect in the new unit information and experience acquired from the operation of other reactors (information and experience acquired through the experience of operating TEPCO's 17 units at Fukushima Daiichi Nuclear Power Station, Fukushima Daini Nuclear Power Station and Kashiwazaki Kashiwa Nuclear Power Station in addition to information on non-conformities at nuclear power stations in Japan and around the world). Higashidori Nuclear Power Station is located in Higashidori-Village (Aomori Prefecture) and the selected site includes a rich natural environment. From an environmental perspective, we will implement the construction with due consideration for the land and sea environment, aiming to ensure that the plant can co-exist with its natural surroundings. The construction plans are currently being reviewed by the Nuclear and Industrial Safety Agency. We are committed to making progress in the project for the start of construction and subsequent commercial operation. (author)

  19. Steam generator replacement at Surry Power Station

    McKay, H.S.


    The purposes of the steam generator repair program at Surry Power Station were to repair the tube degradation caused by corrosion-related phenomena and to restore the integrity of the steam generators to a level equivalent to new equipment. The repair program consisted of (1) replacing the existing lower-shell assemblies with new ones and (2) adding new moisture separation equipment to the upper-shell assemblies. These tasks required that several pieces of reactor coolant piping, feedwater piping, main steam piping, and the steam generator be cut and refurbished for reinstallation after the new lower shell was in place. The safety implications and other potential effects of the repair program both during the repair work and after the unit was returned to power were part of the design basis of the repair program. The repair program has been completed on Unit 2 without any adverse effects on the health and safety of the general public or to the personnel engaged in the repair work. Before the Unit 1 repair program began, a review of work procedures and field changes for the Unit 2 repair was conducted. Several major changes were made to avoid recurrence of problems and to streamline procedures. Steam generator replacements was completed on June 1, 1981, and the unit is presently in the startup phase of the outrage

  20. User Context Aware Base Station Power Flow Model

    Walsh, Barbara; Farrell, Ronan


    At present the testing of power amplifiers within base station transmitters is limited to testing at component level as opposed to testing at the system level. While the detection of catastrophic failure is possible, that of performance degradation is not. This paper proposes a base station model with respect to transmitter output power with the aim of introducing system level monitoring of the power amplifier behaviour within the base station. Our model reflects the expe...

  1. Increasing the efficiency of thermal power stations

    Schwarz, N.F.


    High energy prices and an increased investment of costs in power plants as well as the necessity to minimize all kinds of environmental pollution have severe consequences on the construction and operation of thermal power stations. One of the most promising measures to cope with the mentioned problems is to raise the thermal efficiency of power plants. With the example of an Austrian electric utility it can be shown that by application of high efficiency combined cycles primary energy can be converted into electricity in a most efficient manner. Excellent operating experience has proved the high reliability of these relatively complex systems. Raising the temperature of the gas topping process still higher will not raise the efficiency considerably. In this respect a Rankine cycle is superior to a Brayton cycle. In a temperature range of 850 to 900 0 C were conventional materials with known properties can still be used, only the alkali metals cesium and potassium have the necessary physical and thermodynamic properties for application in Rankine topping cycles. Building on experience gained in the Fast Breeder development and from the US space program, a potassium topping cycle linked to a conventional water steam cycle with an intermediate diphenyl vapour cycle has been proposed which should give thermal efficiencies in excess of 50%. In a multi-national program this so called Treble Rankine Cycle is being investigated under the auspices of the International Energy Agency. Work is in progress to investigate the technical and economic feasibility of this energy conversion system. Experimental investigations are already under way in the Austrian Research Center Seibersdorf where high temperature liquid metal test facilities have been operated since 1968. (Author)

  2. On the development of small nuclear power stations

    Goetzmann, C.A.


    There are weighty reasons for and against the building of small nuclear power stations. Factors such as specific investment costs, opportunities for and areas of application, geographical conditions as well as those relating to infrastructure, security and availability play an important role in the planning, construction and running of a nuclear power station. For the usual large power stations, the comparatively low specific investment costs and a proven technology are favorable factors which minimize the investment risk. The article presents an overview of reasons for using small power stations and also considers the difficulties which would arise in practice. (orig.) [de

  3. Work place regulations - effects on power station construction

    Richter, E.


    The paper describes that the Workplace Order and Workplace Regulations cannot be applied in every area of a conventional power station or the conventional sections of nuclear power stations. In any case extensive regulations already exist for the hot regions of nuclear power stations. A proposal is made as to which areas of power stations should be developed in accordance with the Workplace Order and the Workplace Regulations and which areas are not deemed to be 'Workplaces'. This is illustrated with the aid of typical examples. (orig.) [de

  4. Simulation of a pressurized-water nuclear power station

    Larminaux, Robert; Ourmann, Michel


    Faced with the large programme of fitting out PWR nuclear power stations, Electricite de France have undertaken a series of studies with a view to ensuring the best possible adaptation of the secondary part -particularly the feed water heating section- to the nuclear boiler. In order to undertake such studies it has been necessary to finalize simulation models of the entire power station. So as to verify the validity of the models, experiment-calculation comparisons were made during transient operating states recorded at the Ardennes power station as well as during starting up trials at the Tihange I power station [fr

  5. Modern power station practice incorporating modern power system practice

    Reynolds, PM


    This volume contains two additional features which enhance the value of Modern Power Station Practice as a whole: a cumulative subject index and a detailed list of tables of contents for the entire work. The cumulative index provides access to the vast body of information presented in the set, and also indicates at a glance the breadth and depth of the treatment through the use of inclusive page ranges for major topics. In order to allow the reader the greatest flexibility in using the index there are many cross-references. The entries themselves are qualified by up to two descriptive subheadi

  6. Fire protection in nuclear power plants

    Wright, H.A.


    This lecture describes briefly the chronological order of events which may arise for a very serious emergency situation in a nuclear power plant for which preparations should be made even though the situation has an extremely low probability of happening. The planning and preparedness required are expected to cope with a whole spectrum of emergency situations, from minor accidents to serious plant failures which also lead to releases of significant quantities of radioactive material beyond the site boundary. Fire protection aspects will be briefly covered, and some guidance will be provided on exercises to ensure the plans are feasible and the appropriate personnel and facilities are in a satisfactory state of preparedness. (orig./RW)

  7. Root cause analysis for fire events at nuclear power plants


    Fire hazard has been identified as a major contributor to a plant' operational safety risk. The International nuclear power community (regulators, operators, designers) has been studying and developing tools for defending against this hazed. Considerable advances have been achieved during past two decades in design and regulatory requirements for fire safety, fire protection technology and related analytical techniques. The IAEA endeavours to provide assistance to Member States in improving fire safety in nuclear power plants. A task was launched by IAEA in 1993 with the purpose to develop guidelines and good practices, to promote advanced fire safety assessment techniques, to exchange state of the art information, and to provide engineering safety advisory services and training in the implementation of internationally accepted practices. This TECDOC addresses a systematic assessment of fire events using the root cause analysis methodology, which is recognized as an important element of fire safety assessment

  8. Trend analysis of fire events at nuclear power plants

    Shimada, Hiroki


    We performed trend analyses to compare fire events occurring overseas (1995-2005) and in Japan (1966-2006). We decided to do this after extracting data on incidents (storms, heavy rain, tsunamis, fires, etc.) occurring at overseas nuclear power plants from the Events Occurred at Overseas Nuclear Power Plants recorded in the Nuclear Information Database at the Institute of Nuclear Safety System (INSS) and finding that fires were the most common of the incidents. Analyses compared the number of fires occurring domestically and overseas and analyzed their causes and the effect of the fires on the power plants. As a result, we found that electrical fires caused by such things as current overheating and electric arcing, account for over one half of the domestic and overseas incidents of fire, which indicates that maintenance management of electric facilities is the most important aspect of fire prevention. Also, roughly the same number of operational fires occurred at domestic and overseas plants, judging from the figures for annual occurrences per unit. However, the overall number of fires per unit at domestic facilities is one fourth that of overseas facilities. We surmise that, while management of operations that utilizes fire is comparable for overseas and domestic plants, this disparity results from differences in the way maintenance is carried out at facilities. (author)

  9. Locating techniques for nuclear power stations

    Hayashi, Masao


    The basic thought in locating nuclear power stations is to examine carefully the suitability of sites and the safety of plants, and in the end, to perfect the safety of public. In Japan, effort is exerted to obtain the trust of local people by carrying out investigation, research and examination from respective standpoints of the government, institutes and industries. The author has engaged in the standardization of the investigation, test and analysis regarding the aseismatic capability of ground, the verifying project in Tadotsu of the coupled vibration of ground and structures, the evaluation of the performance of large vibration tables, the future concept of new locating procedure and so on in the last more than ten years. The technological classification of ground, the technological meaning of active faults, the procedure of the aseismatic design of plants, the difference of earthquake input force according to various locating methods, 12 rules regarding the attenuation of vibration of ground, and the concept of new locating method in the 21st century are explained. As the new locating techniques applicable to central Japan, diluvial ground location, floating location in tunnels, underground location, offshore location and so on must be promoted. (Kako, I.)

  10. Carbon burnout of pulverised coal in power station furnaces

    R.I. Backreedy; L.M. Fletcher; J.M. Jones; L. Ma; M. Pourkashanian; A. Williams; K. Johnson; D.J. Waldron; P. Stephenson [University of Leeds, Leeds (United Kingdom)


    The degree of carbon burnout in pulverised fuel fired power stations is important because it is linked with power plant efficiency and coal ash suitability for construction purposes. The use of computational methods to calculate carbon burnout in such systems has been aided by the increasing availability of fast computers and improvements in computational methodologies. Despite recent advances in fluid flow, coal devolatilisation and coal combustion models, the use of CFD methods for detailed design purposes or for the selection of commercial coals is still limited. In parallel, industrial engineering codes, which combine simplified thermal models with advanced coal combustion models, are still undergoing development since they provide economic advantages over detailed CFD analysis. Although the major coal combustion processes are well established, an understanding regarding the role of coal macerals and the influence of ash on the combustion process is still lacking. A successful coal model must be able to handle all the complexities of combustion, from the details of the burner geometry through to the formation of unburnt carbon as well as NOx. The development of such a model is described here.

  11. Life cycle assessment of solar aided coal-fired power system with and without heat storage

    Zhai, Rongrong; Li, Chao; Chen, Ying; Yang, Yongping; Patchigolla, Kumar; Oakey, John E.


    Highlights: • The comprehensive performances of three kinds of different systems were compared through LCA. • The comprehensive results of all systems were evaluated by grey relation theory. • The effects of life span, coal price, and solar collector field cost, among other factors, on the results were explored. - Abstract: Pollutant emissions from coal-fired power system have been receiving increasing attention over the past few years. Integration of solar thermal energy can greatly reduce pollutant emissions from these power stations. The performances of coal-fired power system (S1), solar aided coal-fired power system with thermal storage (S2), and solar aided coal-fired power system without thermal storage (S3) with three capacities of each kind of system (i.e., nine subsystems) were analyzed over the entire life span. The pollutant emissions and primary energy consumptions (PECs) of S1, S2, and S3 were estimated using life cycle assessment (LCA). The evaluation value of global warming potential (GWP), acidification potential (AP), respiratory effects potential (REP) and PEC were obtained based on the LCA results. Furthermore, the system investments were estimated, and grey relation theory was used to evaluate the performance of the three types of systems comprehensively. Finally, in order to find the effect of some main factors on the solar aided coal-fired power system (SACFPS), uncertainty analysis has been carried out. The LCA results show that the pollutant emissions and PEC mainly take place in the fuel processing and operation stages for all three system types, and S2 performs the best among the three systems based on the grey relation analysis results. And the uncertainty analysis shows that with longer life span, the power system have better performance; with higher coal price, the power system will have worse performance; with lower solar collector field cost, the solar aided coal-fired power system will be more profitable than the base

  12. Fire extinguishing device for nuclear power plant

    Arakawa, Ken


    Fire extinguishing pipelines disposed in turbine buildings of low earthquake proof grade and fire extinguishing pipelines disposed in reactor buildings of high earthquakes proof grade have been used in common with each other. Accordingly, if the fire extinguishing device in the turbine buildings designed for low earthquake proof grade are partially destroyed upon occurrence of medium-scale earthquakes, there is a worry that fire extinguishing water can not be supplied to the inside of the reactor buildings. In view of the above, an emergency fire extinguishing water system using a fire extinguishing reservoir at the outdoor of low earthquake proof grade as a feedwater source and suitable to the low earthquake proof grade is disposed in the turbine buildings. Another emergency fire extinguishing water system using an emergency fire extinguishing water reservoir disposed in the reactor buildings as a feedwater source and suitable to the high earthquake proof grade is disposed in the reactor buildings. Then, ordinary fire extinguishing water system and the emergency fire extinguishing water system are connected to each other. Thus, upon occurrence of earthquakes if the function of the ordinary fire extinguishing water system of low earthquake proof grade is lost, fires breaking out in the reactor buildings can rapidly be extinguished. (N.H.)

  13. Nuclear power plant fire protection: fire detection (subsystems study Task 2)

    Berry, D.L.


    This report examines the adequacy of fire detection in the context of nuclear power plant safety. Topics considered are: (1) establishing area detection requirements, (2) selecting specific detector types, (3) locating and spacing detectors, and (4) performing installation tests and maintenance. Based on a thorough review of fire detection codes and standards and fire detection literature, the report concludes that current design and regulatory guidelines alone are insufficient to ensure satisfactory fire detection system performance. To assure adequate fire detection, this report recommends the use of in-place testing of detectors under conditions expected to occur normally in areas being protected

  14. 47 CFR 74.793 - Digital low power TV and TV translator station protection of broadcast stations.


    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator station... DISTRIBUTIONAL SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.793 Digital low power TV and TV translator station protection of broadcast stations. (a) An application to construct a new digital low power...

  15. Human reliability analysis of Lingao Nuclear Power Station

    Zhang Li; Huang Shudong; Yang Hong; He Aiwu; Huang Xiangrui; Zheng Tao; Su Shengbing; Xi Haiying


    The necessity of human reliability analysis (HRA) of Lingao Nuclear Power Station are analyzed, and the method and operation procedures of HRA is briefed. One of the human factors events (HFE) is analyzed in detail and some questions of HRA are discussed. The authors present the analytical results of 61 HFEs, and make a brief introduction of HRA contribution to Lingao Nuclear Power Station

  16. Reload shutdown for Nuclear Power Stations in spain in 2003


    Regarding time reductions in fuel reloading at Spanish nuclear power stations, the Spanish Nuclear Security Council (CSN), at the request of the Spanish Finance and Treasury Department of the Chamber of Deputies, delivered an instruction, by which power station's owners were urged to establish a detailed planning of reload operations. This article includes the results of this instruction. (Author) 6 refs

  17. Emergency protection and nuclear power station remote monitoring

    Nowak, K.; Wolf, H.


    The States of the Federal Republic of Germany are planning emergency protection measures for the environment of nuclear power stations based on their statutory duty of care. In this connection the paper explains to what extent remote monitoring of nuclear power stations practised by the Federal Supervisory Authorities may support the design and implementation of emergency protection measures. (orig.) [de

  18. Ash Deposition Trials at Three Power Stations in Denmark

    Laursen, Karin; Frandsen, Flemming; Larsen, Ole Hede


    Six full-scale trials were conducted at three power stations in Denmark: Ensted, Funen, and Vendsyssel power stations. During these trials, pulverized coal, bottom ash, fly ash, and deposits from cooled probes were sampled and analyzed with various techniques. On the basis of SEM analyses...

  19. Criteria for the design of the control room complex for a nuclear power generating station



    This Standard addresses the central control room of a nuclear power generating station and the overall complex in which this room is housed. It is not intended to cover special or normally unattended control rooms, such as those provided for radioactive waste handling or for emergency shutdown operations. The nuclear power generating station control room complex provides a protective envelope for plant operating personnel and for instrument and control equipment vital to the operation of the plant during normal and abnormal conditions. In this capacity, the control room complex must be designed and constructed to meet the following criteria contained in Appendix A of 10CFR50, General Design criteria for Nuclear Power Plants: (1) Criterion 2: design bases for protection against natural phenomena; (2) Criterion 3: fire protection; (3) Criterion 4: environmental and missile design bases; (4) Criterion 5: sharing of structures, systems and components (multiunit stations only); and (5) Criterion 19: control room

  20. Environmental protection in coal utilization and its problems at Sultan Salahuddin Abdul Aziz Power Station, Kapar

    Bock, L.C. (Tenaga Nasional Berhad (Malaysia). Research and Development Dept.)


    Efforts to prevent and minimise pollution as well as to enhance the quality of the environment around the new coal-fired Sultan Salanuddin Power Station are described. Malaysian environmental regulations are mentioned and pollution-reducing elements designed into the power plant are listed. A Public Participation Forum was held to inform the public of the planned power station and the environmental considerations. An Environmental Audit was conducted which compared the measured impacts of the operational station with the predicted expectations. On-going air quality and wastewater discharge monitoring procedures are outlined. Measures to control coal dust and spontaneous combustion of coal, and methods used to dispose of coal ash are described. 3 figs.

  1. Fire protection of safe shutdown capability at commercial nuclear power plants

    Sullivan, K.


    The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the US are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and components important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50). Since 1983, various members of the Department of Nuclear Energy (DNE) at Brookhaven National Laboratory (BNL) have provided technical assistance to the Nuclear Regulatory Commission (NRC) in support of its evaluations of fire protection features implemented at commercial nuclear power stations operated in the US. This paper presents a discussion of the insights gained by the author during his active participation in this area

  2. Internal fire analysis screening methodology for the Salem Nuclear Generating Station

    Eide, S.; Bertucio, R.; Quilici, M.; Bearden, R.


    This paper reports on an internal fire analysis screening methodology that has been utilized for the Salem Nuclear Generating Station (SNGS) Probabilistic Risk Assessment (PRA). The methodology was first developed and applied in the Brunswick Steam Electric Plant (BSEP) PRA. The SNGS application includes several improvements and extensions to the original methodology. The SNGS approach differs significantly from traditional fire analysis methodologies by providing a much more detailed treatment of transient combustibles. This level of detail results in a model which is more usable for assisting in the management of fire risk at the plant

  3. Cables for nuclear power generating stations, (6)

    Kakuta, Tsunemi; Asakawa, Naoki; Yamamoto, Tomotaka; Watanabe, Mikio; Shingo, Yoshioki.


    New inorganic material insulated flexible triaxial cables have been developed for the purpose of applying around the primary circuit of fast breeder reactor (FBR). These cables were tested at high temperature and high #betta#-ray radiation environment, and they showed good electrical properties. Other noted results were that they showed good fire proof and flame resistant properties. (author)

  4. Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

    Jones, T. D.


    A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

  5. Environmental radiation monitoring system in nuclear power station

    Matsuoka, Sadazumi; Tadachi, Katsuo; Endo, Mamoru; Yuya, Hiroshi


    At the time of the construction of nuclear power stations, prior to their start of operation, the state of environmental radiation must be grasped. After the start of the power stations, based on those data, the system of environmental radiation monitoring is established. Along with the construction of Kashiwazaki-Kariwa Nuclear Power Station, The Tokyo Electric Power Co., Inc. jointly with Fujitsu Ltd. has developed a high-reliability, environmental radiation monitoring system, and adopted ''optical data highways'' using optical fiber cables for communication. It consists of a central monitoring station and 11 telemeter observation points, for collecting both radiation and meteorological data. The data sent to the central station through the highways are then outputted on a monitoring panel. They are analyzed with a central processor, and the results are printed out. (Mori, K.)

  6. Fire protection of safe shutdown capability at commercial nuclear power plants

    Sullivan, K.


    The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the U.S. are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and composites important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50)

  7. Numerical simulation methods of fires in nuclear power plants

    Keski-Rahkonen, O.; Bjoerkman, J.; Heikkilae, L.


    Fire is a significant hazard to the safety of nuclear power plants (NPP). Fire may be serious accident as such, but even small fire at a critical point in a NPP may cause an accident much more serious than fire itself. According to risk assessments a fire may be an initial cause or a contributing factor in a large part of reactor accidents. At the Fire Technology and the the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) fire safety research for NPPs has been carried out in a large extent since 1985. During years 1988-92 a project Advanced Numerical Modelling in Nuclear Power Plants (PALOME) was carried out. In the project the level of numerical modelling for fire research in Finland was improved by acquiring, preparing for use and developing numerical fire simulation programs. Large scale test data of the German experimental program (PHDR Sicherheitsprogramm in Kernforschungscentral Karlsruhe) has been as reference. The large scale tests were simulated by numerical codes and results were compared to calculations carried out by others. Scientific interaction with outstanding foreign laboratories and scientists has been an important part of the project. This report describes the work of PALOME-project carried out at the Fire Technology Laboratory only. A report on the work at the Nuclear Engineering Laboratory will be published separatively. (au)

  8. Fire safety study of Dodewaard and Borssele nuclear power plants


    From the nuclear and conventional fire safety audits of both Dutch nuclear power plants performed under supervision of the Nuclear Safety Inspectorate and the Inspectorate for the Fire Services it turns out that the fire safety is sufficient however amenable for improvement. Besides a detailed description of the method of examination, the study 'Fire Safety' contains the results of the audit and 14 respectively 15 recommendations for improvement of the fire safety in Dodewaard and Borssele. The suggested recommendations which are applicable to both power plants are the following: fire fighting training for operators and guards, a complete emergency ventilation system of the control room, increase in the number of detectors and alarms, an increase in the quantity of water available for high-pressure fire fighting, improvement of fire barriers between several redundancies of nuclear safety systems, an investigation and possible improvement of the heat and radiation protection offered by presently used fire fighting suits. For Dodewaard a closed emergency staircase in the reactor building (secondary containment) is deemed necessary for personnel emergency escape routes and continued fire fighting if required

  9. Review of radioactive discharges from nuclear power stations


    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

  10. Principle simulator for a PWR nuclear power station

    Wahlstroem, B.


    A report is given on a simulator developed for the training of operational and planning staff for the Lovisa nuclear power station in Finland. All main components of the power station are illustrated and trainees can operate the simulator in the power range 3-100 %. The model was originally developed for planning the control system of Lovisa I, for which reason the simulator project could be carried out on a relatively limited budget. (author)

  11. Electricity supplies in a French nuclear power station


    As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

  12. Load control on nuclear power station

    Hattori, Takuya; Tsukuda, Yoshiaki.


    Power generation control is required for the nuclear power plants to meet electric power demand. In BWRs, power generation control can be achieved by arranging the coolant flow rate and control rod operation. In PWRs, power generation can be regulated by the control rods automatically controled with the steam valves. As a result of the experiments, it is confirmed that the operational function is normal, and safety of reactor components, pressure vessel and fuel elments are assured. (Katagiri, S)

  13. Station set requirements document. Volume 82: Fire support. Book 2: Preliminary functional fire plan

    Gray, N. C.


    The fire prevention/protection requirements for all shuttle facility and ground support equipment are presented for the hazardous operations. These include: preparing the orbiter for launch, launch operations, landing operations, safing operations, and associated off-line activities.

  14. Station planning and design incorporating modern power system practice

    Martin, PC


    The planning and design of new power stations can involve complex interaction between the many engineering disciplines involved as well as environmental, planning, economical, political and social pressures. This volume aims to provide a logical review of the procedures involved in power station development. The engineering aspects are outlined in detail, with examples, showing the basis of the relationships involved together with ""non-engineering"" factors so that the engineer can draw on the information provided for specific projects. The civil engineering and building of power stations are

  15. Argentinian experience in selecting sites for nuclear power stations

    Csik, B.J.


    One nuclear power station is in operation in the Republic of Argentina, a second is under construction, and the decision to build a third has been taken. According to existing plans, about ten nuclear power stations should go into operation during the next decade. The present paper analyses the experience acquired in selecting sites for the first units, commenting on the criteria and methods applied, the studies that were carried out, the specific problems encountered and the solutions adopted, as well as on the question of acceptance of the chosen sites by the public. It goes on to describe the current programme of selection and study of sites for future nuclear power stations

  16. 78 FR 55765 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...


    ... Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Draft..., ``Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN-FIRE).'' In... caused by impaired fire protection features at nuclear power plants. The report documents the history of...

  17. 78 FR 45573 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...


    ... Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... Nuclear Power Plant Fire Protection (CARMEN-FIRE), Draft Report for Comment.'' DATES: Comments on this... caused by impaired fire protection features at nuclear power plants. The report documents the history of...

  18. Exergy Analysis of Operating Lignite Fired Thermal Power Plant

    K. Murugesan


    Full Text Available The energy assessment must be made through the energy quantity as well as the quality. But the usual energy analysisevaluates the energy generally on its quantity only. However, the exergy analysis assesses the energy on quantity as well asthe quality. The aim of the exergy analysis is to identify the magnitudes and the locations of real energy losses, in order toimprove the existing systems, processes or components. The present paper deals with an exergy analysis performed on anoperating 50MWe unit of lignite fired steam power plant at Thermal Power Station-I, Neyveli Lignite Corporation Limited,Neyveli, Tamil Nadu, India. The exergy losses occurred in the various subsystems of the plant and their components havebeen calculated using the mass, energy and exergy balance equations. The distribution of the exergy losses in several plantcomponents during the real time plant running conditions has been assessed to locate the process irreversibility. The Firstlaw efficiency (energy efficiency and the Second law efficiency (exergy efficiency of the plant have also been calculated.The comparison between the energy losses and the exergy losses of the individual components of the plant shows that themaximum energy losses of 39% occur in the condenser, whereas the maximum exergy losses of 42.73% occur in the combustor.The real losses of energy which has a scope for the improvement are given as maximum exergy losses that occurredin the combustor.

  19. Fire protection guidelines for nuclear power plants, June 1976



    Guidelines acceptable to the NRC staff for implementing in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. Suitable bases and justification should be provided for alternative approaches to establish acceptable implementation of General Design Criterion 3

  20. Power station impacts: socio-economic impact assessment

    Glasson, John; Elson, Martin; Barrett, Brendan; Wee, D. Van der


    The aim of this study is to assess the local social and economic impacts of a proposed nuclear power station development at Hinkley Point in Somerset. The proposed development, Hinkley Point C, would be an addition to the existing Hinkley Point A Magnox station, commissioned in 1965, and the Hinkley Point B Advanced Gas Cooled Reactor (AGR) station, commissioned in 1976. It is hoped that the study will be of assistance to the CEGB, the Somerset County and District Councils and other agencies in their studies of the proposed development. In addition, the study seeks to apply and further develop the methodology and results from previous studies by the Power Station Impacts (PSI) team for predicting the social and economic effects of proposed power station developments on their localities. (author)

  1. Prospect and problems of gas based power stations of NTPC

    Suryanarayana, A.


    The policy of the Government of India concerning utilisation of natural gas resources of the country has undergone changes over the last few years. The government decided in 1985 to allocate natural gas for power generation and in the year 1986 approved the setting up of the first series of three gas based combined cycle power projects of National Thermal Power Corporation (NTPC). The problems of gas power stations of NTPC are discussed. These are high cost of generation, completion of transmission line works to match with the commissioning of gas power stations, high price of natural gas, and fixation of tariff for sale of power from gas based power stations. (N.B.)

  2. Corrosion and Materials Performance in biomass fired and co-fired power plants

    Montgomery, Melanie; Larsen, OH; Biede, O


    not previously encountered in coal-fired power plants. The type of corrosion attack can be directly ascribed to the composition of the deposit and the metal surface temperature. In woodchip boilers, a similar corrosion rate and corrosion mechanism has on some occasions been observed. Co-firing of straw (10...... and 20% energy basis) with coal has shown corrosion rates lower than those in straw-fired plants. With both 10 and 20% straw, no chlorine corrosion was seen. This paper will describe the results from in situ investigations undertaken in Denmark on high temperature corrosion in biomass fired plants....... Results from 100% straw-firing, woodchip and co-firing of straw with coal will be reported. The corrosion mechanisms observed are summarized and the corrosion rates for 18-8 type stainless steels are compared....

  3. Electrical power systems for Space Station

    Simon, W. E.


    Major challenges in power system development are described. Evolutionary growth, operational lifetime, and other design requirements are discussed. A pictorial view of weight-optimized power system applications shows which systems are best for missions of various lengths and required power level. Following definition of the major elements of the electrical power system, an overview of element options and a brief technology assessment are presented. Selected trade-study results show end-to-end system efficiencies, required photovoltaic power capability as a function of energy storage system efficiency, and comparisons with other systems such as a solar dynamic power system.

  4. Fire safety in atomic power plants

    Kench, R.L.; British Insurance


    The main reactor types are described briefly - Magnox, advanced gas cooled, pressurized water and fast reactors. Fire risks exist at fuel stores and spent fuel storage facilities. Simple fire prevention measures are suggested. Solid radioactive wastes can also be combustible. Various fire prevention measures for the different storage methods, eg compaction, are given. Gaseous and liquid wastes are also considered. The main types of reactor accident are described and the causes of four incidents - at Chernobyl, Windscale, Brownsferry and Three Mile Island, are examined. (U.K.)

  5. Coal-Fired Power Plant Heat Rate Reductions

    View a report that identifies systems and equipment in coal-fired power plants where efficiency improvements can be realized, and provides estimates of the resulting net plant heat rate reductions and costs for implementation.

  6. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Henderson, B.


    Architectural concepts and design proposals associated with the proposed Sizewell B power station are outlined. The figures are in a separate volume. They consist of the site layout plan, an axonometric drawing of the site, an elevations drawing and a colour perspective drawing of 'A', 'B' and 'C' stations. (U.K.)

  7. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    McInerny, P.T.


    A description is given of the policy and practices that would be adopted in the commissioning, operation and maintenance of the proposed Sizewell B PWR power station. The system of personnel recruitment and training required to staff the station is discussed. (U.K.)

  8. 76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations


    ... Draft Regulatory Guides in the ``Regulatory Guides'' collection of the NRC's Library at http://www.nrc... Stations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment... draft regulatory guide (DG), DG-4016, ``Terrestrial Environmental Studies for Nuclear Power Stations...

  9. Literature study regarding fire protection in nuclear power plants. Part I: Fire rated separations

    Isaksson, S.


    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Conventional building codes can not give guidance on where to make fire rated separations in order to separate redundant trains of safety systems. The separation must originate in functional demands from the authorities on what functions are essential during and after a fire, and under what circumstances these functions shall be retained, i.e. the number of independent faults and initiating events. As a basic demand it is suggested to rate the strength of separations according to conventional building code, based on fire load. The whole separating construction shall have the same fire rating, including the ventilation system. Deviations from the basic demand can de done in case it can be proven that it is possible to compensate some or all of the fire rating with other measures. There is a general lack of statistical information regarding the reliability of fire separating constructions such as walls, fire doors, penetration seals and fire dampers. The amount of cables penetrating a seal is in many cases much higher in real installations than what has been tested for type approval. It would therefore be valuable to perform a furnace test with a more representative amount of cables passing through a penetration seal. Tests have shown that the 20 foot horizontal separation distance stipulated by NRC is not a guarantee against fire damage. Spatial separations based on general requirements shall not be allowed, but considered from case to case based on actual circumstances. For fire protection by isolation or coatings, it is of great importance to choose the method of protection carefully, to be compatible with the material it shall be applied on, and the environment and types of fire that may occur. 48 refs, 2 figs, 5 tabs

  10. Bidding Strategy of Virtual Power Plant with Energy Storage Power Station and Photovoltaic and Wind Power

    Zhongfu Tan


    Full Text Available For the virtual power plants containing energy storage power stations and photovoltaic and wind power, the output of PV and wind power is uncertain and virtual power plants must consider this uncertainty when they participate in the auction in the electricity market. In this context, this paper studies the bidding strategy of the virtual power plant with photovoltaic and wind power. Assuming that the upper and lower limits of the combined output of photovoltaic and wind power are stochastically variable, the fluctuation range of the day-ahead energy market and capacity price is stochastically variable. If the capacity of the storage station is large enough to stabilize the fluctuation of the output of the wind and photovoltaic power, virtual power plants can participate in the electricity market bidding. This paper constructs a robust optimization model of virtual power plant bidding strategy in the electricity market, which considers the cost of charge and discharge of energy storage power station and transmission congestion. The model proposed in this paper is solved by CPLEX; the example results show that the model is reasonable and the method is valid.

  11. Why do we build nuclear power stations

    Keppler, E.


    The author discusses some aspects of interest in the context of opposition to nuclear power in Switzerland. The part played and to be played by nuclear power in Switzerland is discussed, criticisms and objections are countered, the implications of power generation without further nuclear contribution are examined, and requests in certain quarters for a tax on power generation except from alternative sources are rejected. (P.G.R.)

  12. Fire Protection Engineering Design Brief Template. Hydrogen Refueling Station.

    LaFleur, Angela Christine [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Muna, Alice Baca [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Groth, Katrina M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)


    Building a hydrogen infrastructure system is critical to supporting the development of alternate- fuel vehicles. This report provides a methodology for implementing a performance-based design of an outdoor hydrogen refueling station that does not meet specific prescriptive requirements in NFPA 2, The Hydrogen Technologies Code . Performance-based designs are a code-compliant alternative to meeting prescriptive requirements. Compliance is demonstrated by comparing a prescriptive-based fueling station design with a performance-based design approach using Quantitative Risk Assessment (QRA) methods and hydrogen risk assessment tools. This template utilizes the Sandia-developed QRA tool, Hydrogen Risk Analysis Models (HyRAM), which combines reduced-order deterministic models that characterize hydrogen release and flame behavior with probabilistic risk models to quantify risk values. Each project is unique and this template is not intended to account for site-specific characteristics. Instead, example content and a methodology are provided for a representative hydrogen refueling site which can be built upon for new hydrogen applications.

  13. Evolutionary growth for Space Station Freedom electrical power system

    Marshall, Matthew Fisk; Mclallin, Kerry; Zernic, Mike


    Over an operational lifetime of at least 30 yr, Space Station Freedom will encounter increased Space Station user requirements and advancing technologies. The Space Station electrical power system is designed with the flexibility to accommodate these emerging technologies and expert systems and is being designed with the necessary software hooks and hardware scars to accommodate increased growth demand. The electrical power system is planned to grow from the initial 75 kW up to 300 kW. The Phase 1 station will utilize photovoltaic arrays to produce the electrical power; however, for growth to 300 kW, solar dynamic power modules will be utilized. Pairs of 25 kW solar dynamic power modules will be added to the station to reach the power growth level. The addition of solar dynamic power in the growth phase places constraints in the initial Space Station systems such as guidance, navigation, and control, external thermal, truss structural stiffness, computational capabilities and storage, which must be planned-in, in order to facilitate the addition of the solar dynamic modules.

  14. Fire protection of nuclear power plant cable ducts

    Kandrac, J.; Lukac, L.


    Fire protection of cable ducts in the Bohunice and Dukovany V-2 nuclear power plants is of a fourtier type. The first level consists in preventive measures incorporated in the power plant design and layout. The second level consists in early detection and a quick repressive action provided by an electric fire alarm system and a stationary spray system, respectively. Fire partitions and glands represent the third level while special spray, paint and lining materials represent the fourth level of the protection. Briefly discussed are the results of an analysis of the stationary spray system and the effects reducing the efficiency of a fire-fighting action using this system. The analysis showed the need of putting off cable duct fires using mobile facilities in case the stationary spray system cannot cope any longer. (Z.M.). 3 figs., 2 refs

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

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


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

  16. Radiation protection organization in Guangdong Nuclear Power Station (GNPS)

    Yang Maochun


    The French way of radiation protection management has been adopted by Guangdong Nuclear Power Station (GNPS) but there are some differences. In this paper author describes radiation protection organization in GNPS, special measures having been taken and the present status

  17. Application of nuclear power station design criteria to non-nuclear installations

    Regan, J.D.; Hughes, D.J.


    The nuclear industry is multi faceted, in that it includes large and complex chemical plants, a large number of different types of nuclear power stations, and on shore ship maintenance facilities, each with its own unique problems. Since the early days the industry has been aware of the additional problem which is superimposed on what may be classed as traditional fire risks, that is, the risk of an uncontrolled release of radioactivity. This has led to the development of sophisticated fire prevention and control techniques which are applied to new plants, and to the backfitting of older plants. The techniques of analysis, design and operation can be applied to both nuclear and non-nuclear installations. Passive protection is preferred backed up by active techniques. Segregation of essential plant to increase the probability of sufficient surviving to ensure safety systems operate and the provision of smoke free, protected escape routes are important aspects of layout and design. Reliability assessments, venting of smoke and hot gases, fire severity analysis, application of mathematical models contribute to the final design to protect against fires. Experiences built up in the fire fighting profession is integrated into the numerical approach by frequent involvement of the local Fire Officers at each stage of the design and layout of installations. (author)

  18. Safety guide on fire protection in nuclear power plants


    The purpose of the Safety Guide is to give specific design and operational guidance for protection from fire and explosion in nuclear power plants, based on the general guidance given in the relevant sections of the 'Safety Code of Practice - Design' and the 'Safety Code of Practice - Operation' of the International Atomic Energy Agency. The guide will confine itself to fire protection of safety systems and items important to safety, leaving the non-safety matters of fire protection in nuclear power plants to be decided upon the basis of the various available national and international practices and regulations. (HP) [de

  19. Safety and exportation of nuclear power stations

    Coudray, M.; Perrais, J.P.


    Safety problems arising from exportation are especially handled through the French exportation of PWR stations. Regulations differ widely from one country to another. However, very large use of American regulations is made and frequently there is a tendency to harden such or such clause in the quotation. Industry must be ready to give satisfaction to such demands of customers. Sometimes also, it is a mere duplication of French stations which is above all looked for. In that case, it is the problem of using French regulations abroad which arises. Desirable changes in examination proceedings are analyzed together with a French regulation effort aiming to make easier the promotion of their use abroad. Finally, safety may be a factor of success for exportation attempts. It is shown how useless some outbiddings may be, but also how, on the contrary, speeding up of research and development effort towards specific safety problems in case of exportation, is to be promoted [fr

  20. Reload Startup Physics Tests for Tianwan Nuclear Power station

    Yang Xiaoqiang; Li Wenshuang; Li Youyi; Yao Jinguo; Li Zaipeng Jiangsu


    This paper briefly describes the test purposes, test items, test schedules and test equipment's for reload startup physics test's on Unit 1 and 2 of Tianwan Nuclear Power station. Then, an overview of the previous thrice tests and evaluations on the tests results are presented. In the end, the paper shows the development and work direction of optimization project for reload startup physics tests on Unit 1 and 2 of Tianwan Nuclear Power station. (Authors)

  1. Safety principles and design criteria for nuclear power stations

    Gazit, M.


    The criteria and safety principles for the design of nuclear power stations are presented from the viewpoint of a nuclear engineer. The design, construction and operation of nuclear power stations should be carried out according to these criteria and safety principles to ensure, to a reasonable degree, that the likelihood of release of radioactivity as a result of component failure or human error should be minimized. (author)

  2. Electric machinery and drives in thermal power stations


    The following subjects were dealt with during the VDE meeting: 1) Requirements made by the electric network on the generators and their excitation equipment, and the influence thereof on their design; 2) requirements made by the power station process on the electric drives and the influence thereof on type and design; 3) requirements made on protective measures from the point of the electric power station machinery. (TK) [de

  3. The plant efficiency of fusion power stations

    Darvas, J.; Foerster, S.


    Due to the circulating energy, lower efficiencies are to be expected with fusion power plants than with nuclear fission power plants. According to the systems analysis, the mirror machine is not very promising as a power plant. The plant efficiency of the laser fusion strongly depends on the laser efficiency about which one can only make speculative statements at present. The Tokamak requires a relatively low circulating energy and is certainly able to compete regarding efficiency as long as the consumption time can be kept large (> 100 sec) and the dead time between the power pulses small ( [de

  4. Design of photovoltaic central power station concentrator array


    A design for a photovoltaic central power station using tracking concentrators has been developed. The 100 MW plant is assumed to be located adjacent to the Saguaro Power Station of Arizona Public Service. The design assumes an advanced Martin Marietta two-axis tracking fresnel lens concentrator. The concentrators are arrayed in 5 MW subfields, each with its own power conditioning unit. The photovoltaic plant output is connected to the existing 115 kV switchyard. The site specific design allows detailed cost estimates for engineering, site preparation, and installation. Collector and power conditioning costs have been treated parametrically.

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

    Thomson, R.; Muzzarelli, J.


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

  6. Simulation of the energy - environment economic system power generation costs in power-stations

    Weible, H.


    The costs of power generation are an important point in the electricity industry. The present report tries to supply a model representation for these problems. The costs of power generation for base load, average and peak load power stations are examined on the basis of fossil energy sources, nuclear power and water power. The methods of calculation where dynamic investment calculation processes are used, are given in the shape of formulae. From the point of view of long term prediction, power generation cost sensitivity studies are added to the technical, economic and energy-political uncertainties. The sensitivity of models for calculations is examined by deterministic and stochastic processes. In the base load and average region, power generation based on nuclear power and water power is economically more favourable than that from fossilfired power stations. Even including subsidies, this cost advantage is not in doubt. In the peak load region, pumped storage power stations are more economic than fossilfired power stations. (orig.) [de

  7. Gas-fired Power Generation in India: Challenges and opportunities



    India's fast growing economy needs to add 100,000 MW power generating capacity between 2002-2012. Given limitations to the use of coal in terms of environmental considerations, quality and supply constraints, gas is expected to play an increasingly important role in India's power sector. This report briefs NMC Delegates on the potential for gas-fired power generation in India and describes the challenges India faces to translate the potential for gas-fired power generation into reality.

  8. Construction costs of nuclear power stations

    Mandel, H


    It is assumed that the demand for electrical energy will continue to rise and that nuclear power will increasingly supply the base-load of electricity generation in the industrialized world. The author identifies areas where techniques and practices to control costs can be improved. Nuclear power offers an alternative to liquid and gaseous fossil fuels and contributes to a relative stability in the price of electric energy. Nuclear power plants can now generate power more cheaply than other thermal power plants down into the upper middle load sector, as indicated in calculations based on a construction time of six years for nuclear plants and four years for others. Special legal provisions, different conditions of financing and taxation, varying methods of power generation cost accounting, and the nonuniform layout of the plant in the various countries make it difficult to compare power generation costs. The author uses mostly experiences gained in the Federal Republic of Germany for some calculations for comparison; he cites lack of standardization and over-long licensing times as major factors in the recent rapid escalation of nuclear power costs and suggests that adoption of standard reactor designs, encouragement of a vigorous and competitive European nuclear industry, and streamlining of licensing procedures to improve the situation. (MCW)

  9. Nuclear power stations. Information paper no. 1. Controls on the building and running of nuclear power stations


    Controls and constraints which govern the development and running of nuclear power stations are briefly examined. Government policy, permission to build, authority to start building, site acquisition building, running and public opinion are briefly discussed.

  10. Sizewell 'B' power station - engineering and construction

    Walker, A.


    The Sizewell 'B' design is based on the Callaway PWR station in Missouri, USA. There have been many papers describing the additional criteria covering safety, operational experience and design and manufacturing practices which were applied to the Callaway reference design and which led to the Sizewell 'B' design concept. This paper describes the implementation of some of these design criteria leading to the layout related design features. Comparisons are drawn with the reference design. This paper concludes by describing various aspects of the design and construction process and the progress which has been made on the Sizewell site. (author)

  11. Hinkley Point 'C' power station public inquiry: statement of case


    This Statement of Case contains full particulars of the case which the Central Electricity Generating Board (CEGB) proposes to put forward at the Hinkley Point ''C'' Inquiry. It relates to the planning application made by the CEGB for the construction of a 1200 MW Pressurized Water Reactor (PWR) power station at Hinkley Point in the United Kingdom, adjacent to an existing nuclear power station. The inquiry will consider economic, safety, environmental and planning matters relevant to the application and the implications for agriculture and local amenities of re-aligning two power transmission lines. The Statement contains submissions on the following matters: Topic 1 The Requirement for the Station; Topic 2 Safety and Design, including Radioactive Discharges; Topic 3 The On-Site Management of Radioactive Waste and Decommissioning of the Station; Topic 4 Emergency Arrangements; Topic 5 Local and Environmental Issues. (author)

  12. Station black out of Fukushima Daiichi Nuclear Power Station Unit 1 was not caused by tsunamis

    Ito, Yoshinori


    Station black out (SBO) of Fukushima Daiichi Nuclear Power Station Unit 1 would be concluded to be caused before 15:37 on March 11, 2011 because losses of emergency ac power A system was in 15:36 and ac losses of B system in 15:37 according to the data published by Tokyo Electric Power Co. (TEPCO) in May 10, 2013. Tsunami attacked the site of Fukushima Daiichi Nuclear Power Station passed through the position of wave amplitude meter installed at 1.5 km off the coast after 15:35 and it was also recognized tsunami arrived at the coast of Unit 4 sea side area around in 15:37 judging from a series of photographs taken from the south side of the site and general knowledge of wave propagation. From a series of photographs and witness testimony, tsunami didn't attack Fukushima Daiichi Nuclear Power Station uniformly and tsunami's arrival time at the site of Unit 1 would be far later than arrival time at the coast of Unit 4 sea side area, which suggested it would be around in 15:39. TEPCO insisted tsunami passed through 1.5 km off the coast around in 15:33 and clock of wave amplitude meter was incorrect, which might be wrong. Thus SBO of Fukushima Daiichi Nuclear Power Station Unit 1 occurred before tsunami's arrival at the site of Unit 1 and was not caused by tsunami. (T. Tanaka)

  13. Hydroelectric power stations and ecological energy policy

    Novakova, R.


    The report discusses the place of hydroenergy in solving the power and ecological problems of Bulgaria: level of building up of the hydroelectric capacity of the country; possibilities for new hydro electric construction; environmental problems of design, construction and operation of the hydroelectric units; advantages of the hydroelectric engineering. The possibilities of the hydroelectric power plants as an alternative of the other more or less conventional electicity producers are shown in order to help in decision making as regards the problems of the economic, power and environmental crisis. (author)

  14. Recent advances in automated ultrasonic inspection of Magnox power stations

    Wooldridge, A.B.


    Magnox Electric operates a number of Magnox nuclear power stations, some of which have presented difficult inspection challenges. This paper will describe recent advances in automated ultrasonic techniques which have enabled additional, fully effective and qualified inspections to be introduced. The examples chosen involve phased array inspection of fillet welds and the introduction of 3D data display and analysis using NDT Workbench. Ultrasonic phased arrays have been optimised for inspection of fillet welded structures where physical access for the operator is very awkward and the surfaces available for probe scanning are very restricted. In addition to controlling the beam direction and focus depth, the systems have also optimised the depth of field by varying the number of phased array elements fired at a given time. These phased array inspections are substantially superior in quality, reliability and speed compared with that achievable by conventional manual inspection. Analysis of automated ultrasonic data can be very time-consuming if defects are complex. NDT Workbench significantly improves data analysis for complex geometries and defects primarily because of the 3D data displays of multiple beams and automated logging of measurements. This system has been used in 2005 for data analysis of complex defects where sizing accuracy was particularly important. Both these inspection procedures have been formally qualified using the ENIQ (European Network for Inspection Qualification) Methodology. Such qualification was achieved more easily because of the rigorous in house training programmes established in each case and because the Technical Justifications referred to evidence from previous related qualifications whenever appropriate. The timely achievement of inspection qualification demonstrates that the new systems have reached sufficient maturity to be used with confidence for high quality inspections. (orig.)

  15. case study of afam power station


    documentation system, increased training programme for local manpower, privatization of the electric power ... transmission voltage level ad year of installation. b) .... This has led to a drop in the ... and distribution of electrical Energy Houdder.

  16. Experience gained from fires in nuclear power plants: Lessons learned


    In 1993, the IAEA launched a programme to assist Member States in improving fire safety in nuclear power plants (NPPs). The review of fire safety assessment in many plants has shown that fire is one of the most important risk contributors for NPPs. Moreover, operational experience has confirmed that many events have a similar root cause, initiation and development mechanism. Therefore, many States have improved the analysis of their operational experience and its feedback. States that operate NPPs play an important role in the effort to improve fire safety by circulating their experience internationally - this exchange of information can effectively prevent potential events. When operating experience is well organized and made accessible, it can feed an improved fire hazard assessment on a probabilistic basis. The practice of exchanging operational experience seems to be bearing fruit: serious events initiated by fire are on the decline at plants in operating States. However, to maximize this effort, means for communicating operational experience need to be continuously improved and the pool of recipients of operational experience data enlarged. The present publication is the third in a series started in 1998 on fire events, the first two were: Root Cause Analysis for Fire Events (IAEA-TECDOC-1112) and Use of Operational Experience in Fire Safety Assessment of Nuclear Power Plants (IAEA-TECDOC-1134). This TECDOC summarizes the experience gained and lessons learned from fire events at operating plants, supplemented by specific Member State experiences. In addition, it provides a possible structure of an international fire and explosion event database aimed at the analysis of experience from fire events and the evaluation of fire hazard. The intended readership of this is operators of plants and regulators. The present report includes a detailed analysis of the most recent events compiled with the IAEA databases and other bibliographic sources. It represents a

  17. Trends of chemical monitoring in power stations

    Winkler, R.; Venz, H.


    Frequently, the state-of-the-art of chemical monitoring in power plants is still determined by conservative methods. A thorough rationalization requires not only modern analytical procedures, but also the consideration of chemically affected processes in complex process analyses and the combination of automatic analyzers with available process computers. Using some examples, ways of reducing monitoring efforts without impairing safety and economy of nuclear power plant operation are pointed out. (author)

  18. Fire safety assessment for the fire areas of the nuclear power plant using fire model CFAST

    Lee, Yoon Hwan; Yang, Joon Eon; Kim, Jong Hoon


    Now the deterministic analysis results for the cable integrity is not given in case of performing the fire PSA. So it is necessary to develop the assessment methodology for the fire growth and propagation. This document is intended to analyze the peak temperature of the upper gas layer using the fire modeling code, CFAST, to evaluate the integrity of the cable located on the dominant pump rooms, and to assess the CCDP(Conditional Core Damage Probability) using the results of the cable integrity. According to the analysis results, the cable integrity of the pump rooms is maintained and CCDP is reduced about two times than the old one. Accordingly, the fire safety assessment for the dominant fire areas using the fire modeling code will capable to reduce the uncertainty and to develop a more realistic model

  19. Core power distribution measurement and data processing in Daya Bay Nuclear Power Station

    Zhang Hong


    For the first time in China, Daya Bay Nuclear Power Station applied the advanced technology of worldwide commercial pressurized reactors to the in-core detectors, the leading excore six-chamber instrumentation for precise axial power distribution, and the related data processing. Described in this article are the neutron flux measurement in Daya Bay Nuclear Power Station, and the detailed data processing

  20. Feasibility study on floating nuclear power station

    Kajima, Ryoichi


    It is stipulated that nuclear power plants are to be built on solid rock bases on land in Japan. However, there are a limited number of appropriate siting grounds. The Central Research Institute of Electric Power Industry has engaged since 1981 in the studies on the construction technology of power plants, aiming at establishing new siting technology to expand the possible siting areas for nuclear power plants. Underground siting is regarded as a proven technology due to the experience in underground hydroelectric power plants. The technology of siting on quaternary ground is now at the stage of verification. In this report, the outline of floating type offshore/inshore siting technology is introduced, which is considered to be feasible in view of the technical and economical aspects. Three fixed structure types were selected, of which the foundations are fixed to seabed, plant superstructures are above sea surface, and which are floating type. Aiming at ensuring the aseismatic stability of the plant foundations, the construction technology is studied, and the structural concept omitting buoyancy is possible. The most practical water depth is not more than 20 m. The overall plant design, earthquake isolation effect and breakwater are described. (Kako, I.)

  1. Space Station Freedom power - A reliability, availability, and maintainability assessment of the proposed Space Station Freedom electric power system

    Turnquist, S. R.; Twombly, M.; Hoffman, D.


    A preliminary reliability, availability, and maintainability (RAM) analysis of the proposed Space Station Freedom electric power system (EPS) was performed using the unit reliability, availability, and maintainability (UNIRAM) analysis methodology. Orbital replacement units (ORUs) having the most significant impact on EPS availability measures were identified. Also, the sensitivity of the EPS to variations in ORU RAM data was evaluated for each ORU. Estimates were made of average EPS power output levels and availability of power to the core area of the space station. The results of assessments of the availability of EPS power and power to load distribution points in the space stations are given. Some highlights of continuing studies being performed to understand EPS availability considerations are presented.

  2. Environmental impact of nuclear power stations

    Kellermann, O.; Balfanz, H.P.


    Following a comparative consideration of the present and future environmental impact by coal, oil, and nuclear power plants, the special risks connected with the use of the latter are dealt with. A distinction is made in considering the risk between public exposure, in the environment of a plant due to operational leakage and radiation exposure in the plant under normal operation and in the case of an accident. The accident risk consideration is the basis of the Rasmussen study where the different containment construction of german plants as well as the higher population density for sites in the FRG are considered. Evaluation parameters are given to quantify the risks and using this, the risks of various cases of impact of nuclear power plants are compared. The comparison shows that the risks of nuclear power plant operation according to the value in normal operation are comparable to those in the case of an accident. (ORU/LH) [de

  3. Tarapur Atomic Power Station - - an overview of experience

    Shah, J.C.


    A broad overview of the experience and performance of the Tarapur Atomic Power Station (TAPS) in its role as the developing world's first foray in commercial atomic power has been attempted. The prime objective was not just generation of power but assimilation of an advanced technology on an economically viable basis in the underdeveloped environment compounded with governmental organisational culture. Scientific and technical advances registered through the TAPS experience in the area of design, operation and maintenance are mentioned. Aspects of station performance, management and even economics are also covered. (auth.)

  4. Environmental implications of fossil-fuelled power stations

    Robson, A.


    The public health and environmental implications of electricity generation by fossil-fuelled power stations are discussed with respect to pollutant emission and the disposal of waste products. The following conclusions were deduced. The policy of using tall chimney stacks has ensured that acceptable concentrations of potential pollutants are observed in the vicinity of power stations. Large scale carbon dioxide emission may represent a problem in the future due to its effect on the climate. The effects of sulphur dioxide and the oxides of nitrogen need to be kept under review but it is likely that sources other than power stations will be of greater importance in this context. Pulverised fuel ash is a safe and useful by product of power production. Finally the radiation dose to man caused by the release of naturally occurring radioisotopes is negligible compared to the natural background levels. (UK)

  5. Nuclear power stations and their environmental hazards

    Jansen, P.


    Starting from a consideration of the energy demand up to the year 2000, the author points out the necessity of nuclear power plant operation for electricity generation and discusses the possible danger to human populations. An assessment of the emission rate of radionuclides in nuclear power plant operation and the possible health hazards to the total population is based on a survey of the U.S. EPA of February 1972. The discussion of the accident risk is based on the results of Rasmussen's study of reactor safety. (ORU/AK) [de

  6. Protection against fire hazards in French nuclear power plants

    Chapus, J.


    The prevention of fire in French nuclear power plants has followed the evolution of safety regulations. Today fire hazards are no longer considered as classical industrial risks but as specific risks that deserve to be studied thoroughly and in a more formalized form. In the beginning of the eighties EDF was committed to the redaction of a technical referential against fire gathering all the directives applicable to the N4-type plant (1450 MW). In 1994 this technical referential was reconsidered and enlarged in order to involve 900 MW and 1300 MW units. In each nuclear power plant a PAI (plan against fire) has been elaborated so that the installation can be progressively upgraded according to the last standard defined by the technical referential. (A.C.)

  7. Biomass Co-Firing in Suspension-Fired Power Plants

    Kær, Søren Knudsen; Hvid, Søren Lovmand; Baxter, Larry

    , in the future it is expected to become relevant to cofire in more advanced plants as the trend in the power plant structure is towards older plants having fewer operating hours or being decommissioned. A major product of this project is an experimentally validated computational fluid dynamics (CFD) based...... modelling tool adapted to accommodate biomass cofiring combustion features. The CFD tool will be able to predict deposit accumulation, particle conversion, fly ash composition, temperatures, velocities, and composition of furnace gases, etc. The computer model will primarily be used in the development...

  8. Life Cycle Assessment of Coal-fired Power Production

    Spath, P. L.; Mann, M. K.; Kerr, D. R.


    Coal has the largest share of utility power generation in the US, accounting for approximately 56% of all utility-produced electricity (US DOE, 1998). Therefore, understanding the environmental implications of producing electricity from coal is an important component of any plan to reduce total emissions and resource consumption. A life cycle assessment (LCA) on the production of electricity from coal was performed in order to examine the environmental aspects of current and future pulverized coal boiler systems. Three systems were examined: (1) a plant that represents the average emissions and efficiency of currently operating coal-fired power plants in the US (this tells us about the status quo), (2) a new coal-fired power plant that meets the New Source Performance Standards (NSPS), and (3) a highly advanced coal-fired power plant utilizing a low emission boiler system (LEBS).

  9. Model of fire spread around Krsko Power Plant

    Vidmar, P.; Petelin, S.


    The idea behind the article is how to define fire behaviour. The work is based on an analytical study of fire origin, its development and spread. The study is based on thermodynamics, heat transfer and the study of hydrodynamics and combustion, which represent the bases of fire dynamics. The article shows a practical example of a leak of hazardous chemicals from a tank. Because of the inflammability of the fluid, fire may start. We have tried to model fire propagation around the Krsko power plant, and show what extended surrounding area could be affected. The model also considers weather conditions, in particular wind speed and direction. For this purpose we have used the computer code Safer Trace, which is based on zone models. That means that phenomena are described by physical and empirical equations. An imperfection in this computer code is the inability to consider ground topology. However in the case of the Krsko power plant, topology is not so important, as the plan is located in a relatively flat region. Mathematical models are presented. They show the propagation of hazardous fluid in the environment considering meteorological data. The work also shows which data are essential to define fire spread and shows the main considerations of Probabilistic Safety Assessment for external fire event.(author)

  10. Physics Experiments at the Agesta Power Station

    Apelqvist, G.; Bliselius, P. Aa.; Blomberg, P.E.; Jonsson, E.; Aakerhielm, F.


    Part A. Dynamic measurements have been performed at the Aagesta reactor at power levels from 0.3 to 65 MW(th). The purposes of the experiments have been both to develop experimental methods and equipment for the dynamic studies and to measure the dynamic characteristics of the reactor in order to check the dynamic model. The experiments have been performed with four different perturbation functions: trapezoidal and step functions and two types of periodic multifrequency signals. Perturbations were introduced in the reactivity and in the load. The recordings were made of the responses of nuclear power, coolant inlet and outlet temperature and control rod position. The results are presented as step responses and transfer functions (Bode diagrams). Inmost cases the relative accuracy is ± 0.5 dB in amplitude and ± 5 deg in phase. The results from the experiments in general show rather good agreement with the results obtained from a dynamic model, which successively has been improved. Experience on reactor noise analysis based on measurements in the Agesta power reactor is discussed. It is shown that the noise measurements have given complementary dynamic information of the reactor. Part B. Static measurements of the physics parameters in the Agesta reactor are carried out to confirm theoretical methods for reactor calculations and to form a good basis for safe operation of the reactor. The reactivity worth of groups of control rods are determined with different methods and compared with calculations with the three-dimensional code HETERO. The excess reactivity as a function of burn up is obtained from the control rod positions. The temperature coefficient of the moderator is measured by lowering the moderator temperature at constant power and observing the change in control rod insertion. As burn up increases the experiments are repeated in order to follow the changes in the coefficient. The xenon poisoning effects are measured by changing the power level and

  11. Physics Experiments at the Agesta Power Station

    Apelqvist, G [State Power Board, Stockholm (Sweden); Bliselius, P Aa; Blomberg, P E; Jonsson, E; Aakerhielm, F [AB Atomenergi, Nykoeping (Sweden)


    Part A. Dynamic measurements have been performed at the Aagesta reactor at power levels from 0.3 to 65 MW(th). The purposes of the experiments have been both to develop experimental methods and equipment for the dynamic studies and to measure the dynamic characteristics of the reactor in order to check the dynamic model. The experiments have been performed with four different perturbation functions: trapezoidal and step functions and two types of periodic multifrequency signals. Perturbations were introduced in the reactivity and in the load. The recordings were made of the responses of nuclear power, coolant inlet and outlet temperature and control rod position. The results are presented as step responses and transfer functions (Bode diagrams). Inmost cases the relative accuracy is {+-} 0.5 dB in amplitude and {+-} 5 deg in phase. The results from the experiments in general show rather good agreement with the results obtained from a dynamic model, which successively has been improved. Experience on reactor noise analysis based on measurements in the Agesta power reactor is discussed. It is shown that the noise measurements have given complementary dynamic information of the reactor. Part B. Static measurements of the physics parameters in the Agesta reactor are carried out to confirm theoretical methods for reactor calculations and to form a good basis for safe operation of the reactor. The reactivity worth of groups of control rods are determined with different methods and compared with calculations with the three-dimensional code HETERO. The excess reactivity as a function of burn up is obtained from the control rod positions. The temperature coefficient of the moderator is measured by lowering the moderator temperature at constant power and observing the change in control rod insertion. As burn up increases the experiments are repeated in order to follow the changes in the coefficient. The xenon poisoning effects are measured by changing the power level and

  12. Using fire dynamics simulator to reconstruct a hydroelectric power plant fire accident.

    Chi, Jen-Hao; Wu, Sheng-Hung; Shu, Chi-Min


    The location of the hydroelectric power plant poses a high risk to occupants seeking to escape in a fire accident. Calculating the heat release rate of transformer oil as 11.5 MW/m(2), the fire at the Taiwan Dajia-River hydroelectric power plant was reconstructed using the fire dynamics simulator (FDS). The variations at the escape route of the fire hazard factors temperature, radiant heat, carbon monoxide, and oxygen were collected during the simulation to verify the causes of the serious casualties resulting from the fire. The simulated safe escape time when taking temperature changes into account is about 236 sec, 155 sec for radiant heat changes, 260 sec for carbon monoxide changes, and 235-248 sec for oxygen changes. These escape times are far less than the actual escape time of 302 sec. The simulation thus demonstrated the urgent need to improve escape options for people escaping a hydroelectric power plant fire. © 2011 American Academy of Forensic Sciences.

  13. Ways to Improve Russian Coal-Fired Power Plants

    Tumanovskii, A. G.; Olkhovsky, G. G.


    Coal is an important fuel for the electric power industry of Russia, especially in Ural and the eastern part of the country. It is fired in boilers of large (200 – 800 MW) condensing power units and in many cogeneration power plants with units rated at 50 – 180 MW. Many coal-fired power plants have been operated for more than 40 – 50 years. Though serviceable, their equipment is obsolete and does not comply with the current efficiency, environmental, staffing, and availability standards. It is urgent to retrofit and upgrade such power plants using advanced equipment, engineering and business ideas. Russian power-plant engineering companies have designed such advanced power units and their equipment such as boilers, turbines, auxiliaries, process and environmental control systems similar to those produced by the world’s leading manufacturers. Their performance and ways of implementation are discussed

  14. Ways to Improve Russian Coal-Fired Power Plants

    Tumanovskii, A. G., E-mail:; Olkhovsky, G. G. [JSC “All-Russia Thermal Engineering Institute,” (Russian Federation)


    Coal is an important fuel for the electric power industry of Russia, especially in Ural and the eastern part of the country. It is fired in boilers of large (200 – 800 MW) condensing power units and in many cogeneration power plants with units rated at 50 – 180 MW. Many coal-fired power plants have been operated for more than 40 – 50 years. Though serviceable, their equipment is obsolete and does not comply with the current efficiency, environmental, staffing, and availability standards. It is urgent to retrofit and upgrade such power plants using advanced equipment, engineering and business ideas. Russian power-plant engineering companies have designed such advanced power units and their equipment such as boilers, turbines, auxiliaries, process and environmental control systems similar to those produced by the world’s leading manufacturers. Their performance and ways of implementation are discussed.

  15. Physical decommissioning of the Shippingport Atomic Power Station

    Crimi, F.P.


    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

  16. Solar-assisted MED treatment of Eskom power station waste water

    Roos, Thomas H.; Rogers, David E. C.; Gericke, Gerhard


    The comparative benefits of multi-effect distillation (MED) used in conjunction with Nano Filtration (NF), Reverse Osmosis (RO) and Eutectic Freeze Crystallization (EFC) are determined for waste water minimization for inland coal fired power stations for Zero Liquid Effluent Discharge (ZLED). A sequence of technologies is proposed to achieve maximal water recovery and brine concentration: NF - physico-chemical treatment - MED - EFC. The possibility of extending the concentration of RO reject arising from minewater treatment at the Lethabo power station with MED alone is evaluated with mineral formation modelling using the thermochemical modelling software Phreeq-C. It is shown that pretreatment is essential to extend the amount of water that can be recovered, and this can be beneficially supported by NF.

  17. The Creys-Malville Power Station

    Saitcevsky, B.; Broggiato, A.; Eitz, A.


    The Super Phenix 1, a fast neutron reactor of large power, which is under construction as the result of a European Cooperation at the Creys-Malville (Isere) site, enters its last building phase for commissioning in 1984. The main characteristics of the power plant, as also its site are presented. The nuclear boiler is described, and the studies carried on this boiler are briefly given. Then, an outline of the construction and of the installation of the boiler is given. Finally, after a summary of the stages and the lessons learned from the installation, the arrangements made for ensuring the training and the allocation of the operational team which will take over the plant progressively with the help of the tests, are described [fr

  18. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Gregory, A.R.


    The procedure for decommissioning a CEGB nuclear power station is described. Regulatory and licensing procedures in the UK are first listed. The principal sources of radioactivity in the station after final shutdown are classified. The three stages of the decommissioning procedure are then described. Finally the following topics are dealt with briefly: the management of decommissioning wastes, radiological protection during the operation, possible faults arising having radiological significance, design for decommissioning and costs. (U.K.)

  19. The closed-down nuclear power station

    Kutscheidt, E.


    The author deals with the decision of the Higher Administrative Court of Koblenz of October 6, 1986, in which the immediate execution of the operation licence for the nuclear power plant at Muelheim-Kaerlich is suspended. In his opinion the reasons for the judgement are controversial. But the decision is not subject to appeal, because in this case the Higher Administrative Court is the court of first and last instance. (WG) [de

  20. Nuclear power station - a living organism

    Stedry, B.


    The ABB-ZPA present here a very clear electronic scheme of the well know type I n =I cosφ (not the whole U.Icosφ product) in the typical modular design and respecting every demand. Very peculiar tests on running-down reactor and his power scheme proved that the simplified I.cosφ measuring was giving on the big asynchron motors practically the same decisions as the original mechanical induction relay. 2 figs

  1. Improvements in operational safety performance of the Magnox power stations

    Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)


    In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

  2. The modernization potential of gas turbines in the coal-fired power industry thermal and economic effectiveness

    Bartnik, Ryszard


    The opportunity of repowering the existing condensing power stations by means of  gas turbogenerators offers an important opportunity to considerably improvement of their energy efficiency. The Modernization Potential of Gas turbines in the Coal-Fired Power Industry presents the methodology, calculation procedures and tools used to support enterprise planning for adapting power stations to dual-fuel gas-steam combined-cycle technologies. Both the conceptual and practical aspects of the conversion of existing coal-fired power plants is covered. Discussions of the feasibility, advantages and disadvantages and possible methods are supported by chapters presenting equations of energy efficiency for the conditions of repowering a power unit by installing a gas turbogenerator in a parallel system and the results of technical calculations involving the selection heating structures of heat recovery steam generators. A methodology for analyzing thermodynamic and economic effectiveness for the selection of a structure...

  3. Lewis Research Center space station electric power system test facilities

    Birchenough, Arthur G.; Martin, Donald F.


    NASA Lewis Research Center facilities were developed to support testing of the Space Station Electric Power System. The capabilities and plans for these facilities are described. The three facilities which are required in the Phase C/D testing, the Power Systems Facility, the Space Power Facility, and the EPS Simulation Lab, are described in detail. The responsibilities of NASA Lewis and outside groups in conducting tests are also discussed.


    A. Hnatov


    Full Text Available The analysis of existing schemes for building solar power stations on photoelectric modules with the revealing of their operation principles and functionality has been conducted. The specified technical characteristics of each of the analyzed schemes are given. The structural scheme of the solar charging station for electric cars with determining its functional capabilities and operation features is proposed. The practical application of this scheme will help to reduce the dependence on the general electric power supply network and will create conditions for its total rejection.


    K. Sujatha


    Full Text Available Combustion quality in power station boilers plays an important role in minimizing the flue gas emissions. In the present work various intelligent schemes to infer the flue gas emissions by monitoring the flame colour at the furnace of the boiler are proposed here. Flame image monitoring involves capturing the flame video over a period of time with the measurement of various parameters like Carbon dioxide (CO2, excess oxygen (O2, Nitrogen dioxide (NOx, Sulphur dioxide (SOx and Carbon monoxide (CO emissions plus the flame temperature at the core of the fire ball, air/fuel ratio and the combustion quality. Higher the quality of combustion less will be the flue gases at the exhaust. The flame video was captured using an infrared camera. The flame video is then split up into the frames for further analysis. The video splitter is used for progressive extraction of the flame images from the video. The images of the flame are then pre-processed to reduce noise. The conventional classification and clustering techniques include the Euclidean distance classifier (L2 norm classifier. The intelligent classifier includes the Radial Basis Function Network (RBF, Back Propagation Algorithm (BPA and parallel architecture with RBF and BPA (PRBFBPA. The results of the validation are supported with the above mentioned performance measures whose values are in the optimal range. The values of the temperatures, combustion quality, SOx, NOx, CO, CO2 concentrations, air and fuel supplied corresponding to the images were obtained thereby indicating the necessary control action taken to increase or decrease the air supply so as to ensure complete combustion. In this work, by continuously monitoring the flame images, combustion quality was inferred (complete/partial/incomplete combustion and the air/fuel ratio can be automatically varied. Moreover in the existing set-up, measurements like NOx, CO and CO2 are inferred from the samples that are collected periodically or by

  6. Multivariable control in nuclear power stations

    Parent, M.; McMorran, P.D.


    Linear, state-space models of power plant systems tend to be of high order, leading to difficulties in the design of control systems by state-space methods. However, the control system has access only to the plant inputs and outputs, and the fast-responding internal variables may be masked by slower, dominant variables. Model order reduction applies modal analysis to eliminate the fast modes while retaining the character of the input-output response. Two alternative techniques are presented and demonstrated on a model of a nuclear steam generator. The preferred method is implemented in MVPACK, the computer-aided design package

  7. FIREDATA, Nuclear Power Plant Fire Event Data Base

    Wheelis, W.T.


    1 - Description of program or function: FIREDATA contains raw fire event data from 1965 through June 1985. These data were obtained from a number of reference sources including the American Nuclear Insurers, Licensee Event Reports, Nuclear Power Experience, Electric Power Research Institute Fire Loss Data and then collated into one database developed in the personal computer database management system, dBASE III. FIREDATA is menu-driven and asks interactive questions of the user that allow searching of the database for various aspects of a fire such as: location, mode of plant operation at the time of the fire, means of detection and suppression, dollar loss, etc. Other features include the capability of searching for single or multiple criteria (using Boolean 'and' or 'or' logical operations), user-defined keyword searches of fire event descriptions, summary displays of fire event data by plant name of calendar date, and options for calculating the years of operating experience for all commercial nuclear power plants from any user-specified date and the ability to display general plant information. 2 - Method of solution: The six database files used to store nuclear power plant fire event information, FIRE, DESC, SUM, OPEXPER, OPEXBWR, and EXPERPWR, are accessed by software to display information meeting user-specified criteria or to perform numerical calculations (e.g., to determine the operating experience of a nuclear plant). FIRE contains specific searchable data relating to each of 354 fire events. A keyword concept is used to search each of the 31 separate entries or fields. DESC contains written descriptions of each of the fire events. SUM holds basic plant information for all plants proposed, under construction, in operation, or decommissioned. This includes the initial criticality and commercial operation dates, the physical location of the plant, and its operating capacity. OPEXPER contains date information and data on how various plant locations are

  8. Complex Mobile Independent Power Station for Urban Areas

    Tunik, A. A.; Tolstoy, M. Y.


    A new type of a complex mobile independent power station developed in the Department of Engineering Communications and Life-Support Systems of Irkutsk National Research Technical University, is presented in this article. This station contains only solar panel, wind turbine, accumulator, diesel generator and microbial fuel cell for to produce electric energy, heat pump and solar collector to generate heat energy and also wastewater treatment plant and new complex control system. The complex mobile independent power station is intended for full power supply of a different kind of consumers located even in remote areas thus reducing their dependence from centralized energy supply systems, decrease the fossil fuel consumption, improve the environment of urban areas and solve the problems of the purification of industrial and municipal wastewater.

  9. On the troubles happened in nuclear power stations, 1995


    The troubles which happened at the nuclear power stations of Japan in the fiscal year of 1995 are described in this report. The number of troubles in those power stations reported from the corporations of electric industry to Nuclear Safety Commission according to The Law for Regulation of Nuclear Fertile Material, Nuclear Fuel Material and Reactors and Utility Industry Law were 14 in the year and so, the number per reactor was 0.3. The details of the trouble cases were as follows; one and nine cases for automatic and manual shutdowns in operation, respectively and 4 cases found during a down-time of the reactor. But, there was no influence on the environment surrounding those nuclear power stations by the radioactive materials in either of the cases. (M.N.)

  10. Preventive maintenance technology for nuclear power stations

    Miyazawa, Tatsuo


    With the increase of the number of nuclear power plants in operation and the number of years of operation, the improvement of reliability and the continuation of safe operation have become more important, and the expectation for preventive maintenance technology has also heightened. The maintenance of Japanese nuclear power plants is based on the time schedule maintenance mainly by the regular inspection carried out every year, but the monitoring of the conditions of various machinery and equipment in operation has been performed widely. In this report, the present state of checkup and inspection technologies and the monitoring and diagnostic technologies for operational condition, which are the key technologies of preventive maintenance, are described. As the checkup and inspection technologies, ultrasonic flow detection technology, phased array technology, Amplituden und Laufzeit Orts Kurven method and X-ray CT, and as the monitoring and diagnostic technologies for operational condition, the diagnosis support system for BWR plants 'PLADIS', those for rotary machines, those for turbogenerators, those for solenoid valves, the mechanization of patrol works and the systematizing technology are reported. (K.I.)

  11. Remerschen nuclear power station with BBR pressurized water reactor

    Hoffmann, J.P.


    On the basis of many decades of successful cooperation in the electricity supply sector with the German RWE utility, the Grand Duchy of Luxemburg and RWE jointly founded Societe Luxembourgeoise d'Energie Nucleaire S.A. (SENU) in 1974 in which each of the partners holds a fifty percent interest. SENU is responsible for planning, building and operating this nuclear power station. Following an international invitation for bids on the delivery and turnkey construction of a nuclear power station, the consortium of the German companies of Brown, Boveri and Cie. AG (BBC), Babcock - Brown Boveri Reaktor GmbH (BBR) and Hochtief AG (HT) received a letter of intent for the purchase of a 1,300 MW nuclear power station equipped with a pressurized water reactor. The 1,300 MW station of Remerschen will be largely identical with the Muelheim-Kaerlich plant under construction by the same consortium near Coblence on the River Rhine since early 1975. According to present scheduling, the Remerschen nuclear power station could start operation in 1981. (orig.) [de

  12. Predicting the emissive power of hydrocarbon pool fires

    Munoz, Miguel; Planas, Eulalia; Ferrero, Fabio; Casal, Joaquim


    The emissive power (E) of a flame depends on the size of the fire and the type of fuel. In fact, it changes significantly over the flame surface: the zones of luminous flame have high emittance, while those covered by smoke have low E values. The emissive power of each zone (that is, the luminous or clear flame and the non-luminous or smoky flame) and the portion of total flame area they occupy must be assessed when a two-zone model is used. In this study, data obtained from an experimental set-up were used to estimate the emissive power of fires and its behaviour as a function of pool size. The experiments were performed using gasoline and diesel oil as fuel. Five concentric circular pools (1.5, 3, 4, 5 and 6 m in diameter) were used. Appropriate instruments were employed to determine the main features of the fires. By superimposing IR and VHS images it was possible to accurately identify the luminous and non-luminous zones of the fire. Mathematical expressions were obtained that give a more accurate prediction of E lum , E soot and the average emissive power of a fire as a function of its luminous and smoky zones. These expressions can be used in a two-zone model to obtain a better prediction of the thermal radiation. The value of the radiative fraction was determined from the thermal flux measured with radiometers. An expression is also proposed for estimating the radiative fraction

  13. Proceedings of scientific-technical seminar: materials investigation for power stations and power grid


    This report is an assembly of the papers concerning the material problems occurring during the exploitation of power stations as well as power grid. The diagnostic methods are also discussed. (author)

  14. Refurbishment priorities at the Russian coal-fired power sector for cleaner energy production case studies

    P. Grammelis; N. Koukouzas; G. Skodras; E. Kakaras; A. Tumanovsky; V. Kotler [Centre for Research and Technology Hellas/Institute of Solid Fuels Technology and Applications (CERTH/ISFTA), Ptolemaida (Greece)


    The paper reviews the current status of the coal-fired power sector in Russia, the prospects for renovation activities based on Clean Coal Technologies (CCT) and presents two case studies on potential refurbishment projects. Data were collected for 180 thermoelectric units with capacity higher than 100 MWe and the renovation needs of the power sector, among the retrofitting, repowering and reconstruction options, were estimated through a multi-criteria analysis. The most attractive system to renovate a power plant between the Supercritical Combustion (SC) and the Fluidized Bed Combustion (FBC) technologies was evaluated. The application of each of the aforementioned technologies at the Kashirskaya and Shaturskaya power plants was studied and their replication potential in the Russian coal-fired power plant park was examined. Nowadays, the installed capacity of coal-fired power plants in the Russian Federation is 29.3 GWe, while they account for about 19% of the total electricity generation in the area. The low efficiency and especially the advanced age are the determinant factors for renovation applications at the Russian units. Even in the more conservative modernization scenario, over 30% of the thermoelectric units have to be repowered or reconstructed. Concrete proposals about the profitable and reliable operation of two Russian thermoelectric units with minimized environmental effects were elaborated. A new unit of 315 MWe with supercritical steam parameters and reburning for NOx abatement is envisaged to upgrade Unit 1 of Kashirskaya power station, while new circulating fluidized bed (CFB) boilers of the same steam generation is the most promising renovation option for the boilers of Unit 1 in Shaturskaya power station. 11 refs., 15 figs., 7 tabs.

  15. Allowable Residual Contamination Levels in soil for decommissioning the Shippingport Atomic Power Station site

    Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.


    As part of decommissioning the Shippingport Atomic Power Station, a fundamental concern is the determination of Allowable Residual Contamination Levels (ARCL) for radionuclides in the soil at the site. The ARCL method described in this report is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for unrestricted use of the land after decommissioning. In addition to naturally occurring radionuclides and fallout from weapons testing, soil contamination could potentially come from five other sources. These include operation of the Shippingport Station as a pressurized water reactor, operations of the Shippingport Station as a light-water breeder, operation of the nearby Beaver Valley reactors, releases during decommissioning, and operation of other nearby industries, including the Bruce-Mansfield coal-fired power plants. ARCL values are presented for 29 individual radionculides and a worksheet is provided so that ARCL values can be determined for any mixture of the individual radionuclides for any annual dose limit selected. In addition, a worksheet is provided for calculating present time soil concentration value that will decay to the ARCL values after any selected period of time, such as would occur during a period of restricted access. The ARCL results are presented for both unconfined (surface) and confined (subsurface) soil contamination. The ARCL method and results described in this report provide a flexible means of determining unrestricted-use site release conditions after decommissioning the Shippingport Atomic Power Station

  16. Use of expansion joints in power stations

    Birker; Rommerswinkel.


    The paper discusses the mode of action of different systems of expansion joints. Special regard is given to the problems of expansion of pipelines of high rated diameter as employed in today's large power plant turbines. Due to the limited space available, the important role of the spring rate of the bellows for the reaction forces and moments acting on the connection points is pointed out. Apart from this details are given on the fabrication and materials selection of expansion joint bellows, and problems are discussed which arise in connection with the mechanical or hydraulic deformation of bellows with one or more walls. The non-destructive methods now in use for the testing of expansion pipe joints are mentioned along with experiments to test their behaviour under changing loads. The paper concludes on some remarks concerning proper transport, storage and installation of expansion pipe joints. (orig./AK) [de

  17. Thermal power stations and environmental protection

    Gerking, E.


    In this book, the advantages of an optimum cooling concept for waters are compared with the disadvantages of an uncontrolled thermal pollution of waters by waste waters from thermal power plants. The book focuses on the problem of the cost of measures for environmental protection which has not yet received a detailed and complete treatment. The author suggests that perfectionist solutions and superfluos measures be abandoned in favour of a far-reaching, efficient environmental protection concept with a low expenditure of fuel and capital. A detailed treatment is given to false conclusions in the present estimations of the effects of thermal pollution of the waters and to the advantages of freshwater cooling and cooling in general. Also discussed are immission problems and attempts at their solution. (ORU/AK) [de

  18. Modern power station practice mechanical boilers, fuel-, and ash-handling plant

    Sherry, A; Cruddace, AE


    Modern Power Station Practice, Second Edition, Volume 2: Mechanical (Boilers, Fuel-, and Ash-Handling Plant) focuses on the design, manufacture and operation of boiler units and fuel-and ash-handling plants.This book is organized into five main topics-furnace and combustion equipment, steam and water circuits, ancillary plant and fittings, dust extraction and draught plant, and fuel-and ash-handling plant.In these topics, this text specifically discusses the influence of nature of coal on choice of firing equipment; oil-burner arrangements, ignition and control; disposition of the heating surf

  19. Daya Bay Nuclear Power Station equipment reliability management system innovation

    Gao Ligang; Wang Zongjun


    Daya Bay Nuclear Power Station has achieved good performance since its commercial operation in 1994. The equipment reliability management system that features Daya Bay characteristics has been established through constant technology introduction, digestion and innovation. It is also based on the success of operational system, equipment maintenance system and technical support system. The system lays a solid foundation for the long-term safe operation of power station. This article emphasizes on the innovation part of equipment reliability management system in Daya Bay. (authors)

  20. A Renewably Powered Hydrogen Generation and Fueling Station Community Project

    Lyons, Valerie J.; Sekura, Linda S.; Prokopius, Paul; Theirl, Susan


    The proposed project goal is to encourage the use of renewable energy and clean fuel technologies for transportation and other applications while generating economic development. This can be done by creating an incubator for collaborators, and creating a manufacturing hub for the energy economy of the future by training both white- and blue-collar workers for the new energy economy. Hydrogen electrolyzer fueling stations could be mass-produced, shipped and installed in collaboration with renewable energy power stations, or installed connected to the grid with renewable power added later.

  1. Design Provisions for Withstanding Station Blackout at Nuclear Power Plants


    International operating experience has shown that the loss of off-site power supply concurrent with a turbine trip and unavailability of the standby alternating current power system is a credible event. Lessons learned from the past and recent station blackout events, as well as the analysis of the safety margins performed as part of the ‘stress tests’ conducted on European nuclear power plants in response to the Fukushima Daiichi accident, have identified the station blackout event as a limiting case for most nuclear power plants. The magnitude 9.0 earthquake and consequential tsunami which occurred in Fukushima, Japan, in March 2011, led to a common cause failure of on-site alternating current electrical power supply systems at the Fukushima Daiichi nuclear power plant as well as the off-site power grid. In addition, the resultant flooding caused the loss of direct current power supply, which further exacerbated an already critical situation at the plant. The loss of electrical power resulted in the meltdown of the core in three reactors on the site and severely restricted heat removal from the spent fuel pools for an extended period of time. The plant was left without essential instrumentation and controls, and this made accident management very challenging for the plant operators. The operators attempted to bring and maintain the reactors in a safe state without information on the vital plant parameters until the power supply was eventually restored after several days. Although the Fukushima Daiichi accident progressed well beyond the expected consequences of a station blackout, which is the complete loss of all alternating current power supplies, many of the lessons learned from the accident are valid. A failure of the plant power supply system such as the one that occurred at Fukushima Daiichi represents a design extension condition that requires management with predesigned contingency planning and operator training. The extended loss of all power at a

  2. Need for a probabilistic fire analysis at nuclear power plants

    Calabuig Beneyto, J. L.; Ibanez Aparicio, J.


    Although fire protection standards for nuclear power plants cover a wide scope and are constantly being updated, the existence of certain constraints makes it difficult to precisely evaluate plant response to different postulatable fires. These constraints involve limitations such as: - Physical obstacles which impede the implementation of standards in certain cases; - Absence of general standards which cover all the situations which could arise in practice; - Possible temporary noncompliance of safety measures owing to unforeseen circumstances; - The fact that a fire protection standard cannot possibly take into account additional damages occurring simultaneously with the fire; Based on the experience of the ASCO NPP PSA developed within the framework of the joint venture, INITEC-INYPSA-EMPRESARIOS AGRUPADOS, this paper seeks to justify the need for a probabilistic analysis to overcome the limitations detected in general application of prevailing standards. (author)

  3. Grate-firing of biomass for heat and power production

    Yin, Chungen; Rosendahl, Lasse; Kær, Søren Knudsen


    bed on the grate, and the advanced secondary air supply (a real breakthrough in this technology) are highlighted for grate-firing systems. Amongst all the issues or problems associated with grate-fired boilers burning biomass, primary pollutant formation and control, deposition formation and corrosion......As a renewable and environmentally friendly energy source, biomass (i.e., any organic non-fossil fuel) and its utilization are gaining an increasingly important role worldwide Grate-firing is one of the main competing technologies in biomass combustion for heat and power production, because it can...... combustion mechanism, the recent breakthrough in the technology, the most pressing issues, the current research and development activities, and the critical future problems to be resolved. The grate assembly (the most characteristic element in grate-fired boilers), the key combustion mechanism in the fuel...

  4. Safety of CANDU nuclear power stations

    Snell, V.G.


    A nuclear plant contains a large amount of radioactive material which could be a potential threat to public health. The plant is therefore designed, built and operated so that the risk to the public is low. Careful design of the normal reactor systems is the first line of defense. These systems are highly resistant to an accident happening in the first place, and can also be effective in stopping it if it does happen. Independent and redundant safety sytems minimize the effects of an accident, or stop it completely. They include shutdown systems, emergency core cooling systems, and containment systems. Massive impairment of any one safety system together with an accident can be tolerated. This 'defence in depth' approach recognizes that men and machines are imperfect and that the unexpected happens. The nuclear power plant need not be perfect to be safe. To allow meaningful judgements we must know how safe the plant is. The Atomic Energy Control Board guidelines give one such measure, but they may overestimate the true risk. We interpret these guidelines as an upper limit to the total risk, and trace their evolution. (author)

  5. Solar Power Station Output Inverter Control Design

    J. Bauer


    Full Text Available The photovoltaic applications spreads in these days fast, therefore they also undergo great development. Because the amount of the energy obtained from the panel depends on the surrounding conditions, as intensity of the sun exposure or the temperature of the solar array, the converter must be connected to the panel output. The Solar system equipped with inverter can supply small loads like notebooks, mobile chargers etc. in the places where the supplying network is not present. Or the system can be used as a generator and it shall deliver energy to the supply network. Each type of the application has different requirements on the converter and its control algorithm. But for all of them the one thing is common – the maximal efficiency. The paper focuses on design and simulation of the low power inverter that acts as output part of the whole converter. In the paper the design of the control algorithm of the inverter for both types of inverter application – for islanding mode and for operation on the supply grid – is discussed. Attention is also paid to the design of the output filter that should reduce negative side effects of the converter on the supply network.

  6. Port construction works in the Sendai Nuclear Power Station

    Narahara, Akio; Minamata, Hisashi; Harada, Kensaku


    Sendai Nuclear Power Station is the second nuclear power station of Kyushu Electric Power Co., Inc., with two PWR plants of 890 MW each, and the operation of No.1 plant will be started in July, 1984, and that of No.2 plant in March, 1986. The civil engineering works for both plants were started in June, 1978, and March, 1981, respectively, and the rate of progress as of the end of September, 1982, was 97 % and 66 %, respectively. In the construction of this power station, the port facility was provided for the transport of construction materials and spent fuel, and for the intake of condenser cooling water. In order to make the construction by dry work, the double cofferdam structures with steel sheet piles were made offshore. The use of the wharf was started in March, 1980, though typhoons hit the area several times, and the dredging in the port was completed in May, 1982. The outline of the plan of this power station, the state of affairs before the start of construction, the outline of the port construction works, the topography, geological features and sea conditions, the design of the port such as breakwaters, unloading wharf and water intake, the manufacture and installation of caissons, dredging, and the temporary cofferdam works for water intake are described. (author)

  7. Research on application of knowledge engineering to nuclear power stations

    Umeda, Takeo; Kiyohashi, Satoshi


    Recently, the research on the software and hardware regarding knowledge engineering has been advanced eagerly. Especially the applicability of expert systems is high. When expert systems are introduced into nuclear power stations, it is necessary to make the plan for introduction based on the detailed knowledge on the works in nuclear power stations, and to improve the system repeatedly by adopting the opinion and request of those in charge upon the trial use. Tohoku Electric Power Co. was able to develop the expert system of practically usable scale 'Supporting system for deciding fuel movement procedure'. The survey and analysis of the works in nuclear power stations, the selection of the system to be developed and so on are reported. In No. 1 plant of Onagawa Nuclear Power Station of BWR type, up to 1/3 of the fuel is replaced at the time of the regular inspection. Some fuel must be taken to outside for ensuring the working space. The works of deciding fuel movement procedure, the development of the system and its evaluation are described. (K.I.)

  8. Probabilistic assessment of fire hazard: a contribution of power industry to the development of fire protection engineering

    Kandrac, J.; Skvarka, P.


    Draft methodology was developed for assessment of fire hazard in nuclear power plants. Named DIMEHORP, the methodology is based on fire hazard analyses and on the analyses of the possible ways of fire propagation and of the power plant systems. The former includes determining the spaces of the power plant in which a fire can arise. Fire propagation analysis deals with the probability that within a given section the fire will propagate and cause damage to the equipment before it is localized. The mathematical model used is based on probability theory in conjunction with expert estimates. The methodology was applied to the assessment of the effect of fire in the cable rooms of the Dukovany nuclear power plant on the safety and reliability of its operation. (Z.M.). 3 tabs., 6 refs

  9. Nuclear power stations: environmental surveillance of radioactivity

    Pellerin, P.


    circumstances at a level which is perfectly compatible with public health regulations. Far from constituting a hazard to the public, nuclear facilities can, by virtue of the strictness of the controls to which they are subjected, serve as a model for combating numerous unacceptable conventional pollutants of the environment, the most alarming of which, indeed, nuclear power will undoubtedly cause to disappear in the long run


    Dennis L. Laudal


    The 1990 Clean Air Act Amendments (CAAAs) required the U.S. Environmental Protection Agency (EPA) to determine whether the presence of mercury in the stack emissions from fossil fuel-fired electric utility power plants poses an unacceptable public health risk. EPA's conclusions and recommendations were presented in the Mercury Study Report to Congress (1) and the Utility Air Toxics Report to Congress (1). The first report addressed both the human health and environmental effects of anthropogenic mercury emissions, while the second addressed the risk to public health posed by the emission of mercury and other hazardous air pollutants from steam-electric generating units. Given the current state of the art, these reports did not state that mercury controls on coal-fired electric power stations would be required. However, they did indicate that EPA views mercury as a potential threat to human health. In fact, in December 2000, the EPA issued an intent to regulate for mercury from coal-fired boilers. However, it is clear that additional research needs to be done in order to develop economical and effective mercury control strategies. To accomplish this objective, it is necessary to understand mercury behavior in coal-fired power plants. The markedly different chemical and physical properties of the different mercury forms generated during coal combustion appear to impact the effectiveness of various mercury control strategies. The original Characterization and Modeling of the Forms of Mercury from Coal-Fired Power Plants project had two tasks. The first was to collect enough data such that mercury speciation could be predicted based on relatively simple inputs such as coal analyses and plant configuration. The second was to field-validate the Ontario Hydro mercury speciation method (at the time, it had only been validated at the pilot-scale level). However, after sampling at two power plants (the Ontario Hydro method was validated at one of them), the EPA issued

  11. Comparative funding consequences of large versus small gas-fired power generation units

    Johnson, N.G.


    Gas producers are increasingly looking to privately-owned gas-fired power generation as a major growth market to support the development of new fields being discovered across Australia. Gas-fired generating technology is more environmentally friendly than coal-fired power stations, has lower unit capital costs and has higher efficiency levels. With the recent downward trends in gas prices for power generation (especially in Western Australia) it is likely that gas will indeed be the consistently preferred fuel for generation in Australia. Gas producers should be sensitive to the different financial and risk characteristics of the potential market represented by large versus small gas-fired private power stations. These differences are exaggerated by the much sharper focus given by the private sector to quantify risk and to its allocation to the parties best able to manage it. The significant commercial differences between classes of generation projects result in gas producers themselves being exposed to diverging risk profiles through their gas supply contracts with generating companies. Selling gas to larger generation units results in gas suppliers accepting proportionately (i.e. not just prorata to the larger installed capacity) higher levels of financial risk. Risk arises from the higher probability of a project not being completed, from the increased size of penalty payments associated with non-delivery of gas and from the rising level of competition between gas suppliers. Gas producers must fully understand the economics and risks of their potential electricity customers and full financial analysis will materially help the gas supplier in subsequent commercial gas contract negotiations. (author). 1 photo

  12. Nuclear power stations in August: information and commentary

    Rogozhin, Yu.


    A summary of events at nuclear power stations in the USSR in August 1989 is given. There were 44 nuclear power units in service which had 9 unplanned shutdowns and 13 unsanctioned power reductions. Gosatomenergonadzor SSSR is also responsible for all research and marine reactors. It is reported that there are currently (1989) six nuclear vessels in the USSR and no major accidents or damage to nuclear steam-generating units on these were reported. On-site inspectors maintain a constant presence at nuclear power stations to supervise operation and make sure safety requirements are enforced. Glasnost is opening up previously forbidden areas to the public to enable it to obtain information to allow objective assessment to be made. (author)

  13. 75 FR 5355 - Notice of Extension of Comment Period for NUREG-1934, Nuclear Power Plant Fire Modeling...


    ..., Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Draft Report for Comment AGENCY... 1019195), Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Draft Report for Comment... exists in both the general fire protection and the nuclear power plant (NPP) fire protection communities...

  14. Coal fired power plant fireside problems

    Mayer, P.; Manolescu, A.V.


    This paper describes the recent experience with fireside problems in coal fired subcritical boilers at Ontario Hydro*, and is concerned with boiler tube wastage. Problems with other components such as burners, air pre-heaters and ''back-end'' ductwork are not discussed. In most utilities, boiler tube failures account for a sizable portion of the total forced outages (typically about25%) as well as a very large part of the maintenance outages. The failures shown under the external deterioration category are of interest because they indicate the proportion of problems caused by the tube metal wastage processes initiated on the fireside of the boilers. Fireside problems remain an important cause of boiler tube failures year after year in spite of concentrated efforts to mitigate them

  15. Improved monolithic reinforced concrete construction for nuclear power stations

    Guenther, P.; Fischer, K.


    Experience has shown that in applying monolithic reinforced concrete in nuclear power plant construction the following auxiliary means are useful: measuring sheets in assembling, welding gauges for reaching high tolerance accuracies of prefabricated reinforced concrete members, suitable lining materials, formwork anchorage and formwork release agents, concrete workability agents, mechanized procedures for finishing and assembling. These means were successfully tested in constructing the Greifswald nuclear power station

  16. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Youngman, P.


    The scenic effect of the proposed Sizewell B power station is considered. Offsite planting of trees, landscaping of the areas around the new access road and of the site itself are discussed. The landscape designs are in a separate volume. (U.K.)

  17. The glass model of Muelheim-Kaerlich nuclear power station

    Kuttruf, H.; Lemke, W.


    The glass model represents the nuclear steam generator system of Muelheim-Kaerlich nuclear power station on a scale of 1:25 and in simplified form, so that the thermohydraulic behaviour in both normal operational and fault conditions can be represented. A set-up time of about one hour results in a helpful aid to instruction. (orig.) [de

  18. Application of the minicomputer at Genkai Nuclear Power Station

    Kitamura, H [Kyushu Electric Power Co., Inc., Fukuoka (Japan)


    Genkai Nuclear Power Station introduced a minicomputer system for the data control purpose in addition to a process control computer introduced in the same manner as other PWR nuclear power stations. This system employs two computers; the one for on-line data aquisition, and another for data processing. The control system introduced includes four systems amoung various data control businesses in the nuclear power station. The language used is mainly an assembler language. The first is the meteorological control system which collects, edits and transmits the weather data sent from the observation instruments around the power station. The second is the personal radiation exposure control system which is designed to realize the labor-saving in book-keeping, the speed-up and the improvement of accuracy in the preparation of the reports to the authorities and the head office and the data for exposure control, and the unification of data processing. The third is the waste control system composed of three subsystems of gas, liquid and solid waste control. The fourth is the maintenance and repair control system which gives inputs to the computer according to the classification written in the slips for maintenance and repair, and prepares a number of statistical tables for maintenance control.

  19. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Smedley, G.P.


    A description is given of the role of Lloyd's Register of Shipping as Independent Inspection Agency for the primary circuit of the PWR for the proposed Sizewell B power station. Topics discussed include: Lloyd's Register of Shipping and its functions; the Independent Inspection Agency and its functions; fabrication of the reactor pressure vessel; inspection on site at Sizewell. (U.K.)

  20. Incinerators for radioactive wastes in Japanese nuclear power stations

    Karita, Yoichi


    As the measures of treatment and disposal of radioactive wastes in nuclear power stations, the development of the techniques to decrease wastes, to reduce the volume of wastes, to treat wastes by solidification and to dispose wastes has been advanced energetically. In particular, efforts have been exerted on the volume reduction treatment from the viewpoint of the improvement of storage efficiency and the reduction of transport and disposal costs. Incineration as one of the volume reduction techniques has been regarded as the most effective method with large reduction ratio, but it was not included in waste treatment system. NGK Insulators Ltd. developed NGK type miscellaneous solid incinerators, and seven incinerators were installed in nuclear power stations. These incinerators have been operated smoothly, and the construction is in progress in six more plants. The necessity of incinerators in nuclear power stations and the problems in their adoption, the circumstance of the development of NGK type miscellaneous solid incinerators, the outline of the incinerator of Karlsruhe nuclear power station and the problems, the contents of the technical development in NGK, the outline of NGK type incinerators and the features, the outline of the pretreatment system, incinerator system, exhaust gas treatment system, ash taking out system and accessory equipment, the operational results and the performance are described. (Kako, I.)

  1. Present status of maintenance in nuclear power stations

    Fueki, Kensuke


    For nuclear power stations, the improvement of the rate of facility utilization is indispensable. As its means, the shortening of regular inspection period, the adoption of long term cycle operation, the shortening of plant shutdown period by the improvement of the reliability of installed equipment and so on are conceivable. In this paper, the maintenance techniques in nuclear power stations which constitute the basis of reliability improvement are explained. In nuclear power stations, the use of nuclear fuel, accordingly the existence of radioactivity are the remarkable features. At the time of an accident, the nuclear reaction in a reactor must be stopped, and the excessive heat must be removed. The radioactivity in nuclear fuel must not be released outside. The regular inspection of once a year is provided by the law, and routine tests are performed during normal operation. The check-up by operators also is a part of the safety measures. For the early detection of abnormality, the diagnosis system is developed, and the maintenance techniques during operation are examined for being taken into the safety test and standard. The improvement of reliability is attempted by the redundancy of systems. The activity of quality assurance, the organization for the maintenance of nuclear power stations and maintenance works, and the measures to raise the rate of operation are reported. (Kako, I.)

  2. Prospects for solving environmental problems pertinent to thermal power stations

    A.G. Tumanovskii; V.R. Kotler [OAO All-Russia Thermal Engineering Institute, Moscow (Russian Federation)


    Possible ways to protect the atmosphere and water basin against harmful emissions and effluent waters discharged from thermal power stations are considered. Data on the effectiveness of different methods for removing NOx, SO{sub 2}, and ash particles, as well as heavy metals and CO{sub 2}, from these emissions and discharges are presented.

  3. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Baker, J.W.


    The case for Sizewell B in terms of the CEGB's overall duties, policies and objectives is presented. The discussion concentrates on the rationale of the CEGB's wish to proceed with Sizewell B and the implications which an eventual decision to proceed with a Pressurised Water Reactor at Sizewell could have for future power station orders. (U.K.)

  4. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    McFarlane, J.D.


    The NNC construction programme for the Sizewell B nuclear power station is outlined. The following topics are considered: constructability aspects of the Sizewell B design; overall project programme and organization; NNC target construction programme; construction planning; material quantities and installation rates; site construction manpowers; construction contracting policy; site industrial relations and productivity; site management. (U.K.)

  5. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Whittle, J.


    The non-destructive testing of components for the proposed Sizewell B nuclear power station is discussed. Issues considered include: non-destructive testing techniques available; inspection of ferritic steel components during fabrication; reliability of the ultrasonic inspection of ferritic structures; inspection of components of austenitic steel; in-service inspection of the reactor coolant system. (U.K.)

  6. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Pepper, R.B.


    The practice of radiological protection within the CEGB is described. Health physics at nuclear power stations is discussed. Radiation exposure of operational staff at a PWR and radiation exposure of members of the public are considered. Finally arrangements for dealing with radiological hazards arising during a site emergency are described. (U.K.)

  7. Fuel examination at SSEB Hunterston B power station

    Angell, I.; Oldfield, D.


    After a brief description of Hunterston 'B' Power Station and its fuel, the need for post irradiation examination is established. Means of providing this on site at various stages of the fuel route are described, i.e. refuelling machine, dismantling cell and storage pond. Techniques used include the human eye, video recording and endoscopy. (author)

  8. Smoke flow temperature beneath tunnel ceiling for train fire at subway station: Reduced-scale experiments and correlations

    Meng, Na; Wang, Qiang; Liu, Zhaoxia; Li, Xiao; Yang, He


    Highlights: • Reduced-scale experiments on train fire at subway station. • Smoke flow temperature beneath tunnel ceiling measured and correlated. • Effect of platform-tunnel conjunction door type on smoke temperature is clarified. - Abstract: This paper is to investigate the smoke flow temperature beneath tunnel ceiling for a train on fire stopping besides a subway station. Experiments were carried out in a reduced-scale (1:10) subway station model to study the maximum smoke temperature and the longitudinal temperature distribution beneath the tunnel ceiling by considering platform-tunnel conjunction doors of two types: the full-seal platform screen door (PSD) and the full-height safety door. For the maximum temperature beneath the tunnel ceiling, it is found to be well correlated non-dimensionally with heat release rate by a 3.65 and a 2.92 power law function for the full-seal platform screen door and the full-height safety door, respectively. For the longitudinal temperature distribution along the tunnel ceiling, it can be well correlated by an exponential function for both types of platform-tunnel conjunction doors. Concerning the effect of the door type, the maximum temperature is lower and the longitudinal temperature decays faster for full-height safety door than that for full-seal PSD. This is due to that with the full-height safety door, the effective width of the tunnel ceiling is widened, which results in more heat losses from the smoke flow to the ceiling.

  9. Gas to Power in China. Gas-fired Power in China. Clearing the policy bottleneck

    Chen, Xavier


    Policy for gas-fired power is the single most serious and common issue that needs urgent resolution for all China's current and future gas projects, including LNG projects. This was the main conclusion of a national seminar on gas industry development policy that was held in July 2004. At the time of writing this paper, such a policy is still missing. In order to reduce pollution, improve energy security and meet the needs of the ever-growing economy for high-quality energies, the Chinese government has declared its firm intention to develop a natural gas market. The official target is to develop a gas market of 200 bcm/a by 2020, five times of the current size of around 40 bcm/a. Domestic supply is expected to provide 120 bcm/a, with the rest (80 bcm/a) by gas imports either in the form of piped gas or LNG. Gas-fired power generation plays a critical role in developing a sizeable gas market, especially for large-scale pipeline and LNG projects. Similar to the Guangdong and Fujian LNG projects where gas-fired power accounts for approximately 60% and 70% respectively of the first phase gas volume, each of the proposed LNG projects has allocated a large portion of the gas off-take volume to the power sector. In addition to the first two commercial CCGT plants that were commissioned in 2005, there are over 20 projects totalling 18 GW of capacity under construction. By 2020, China's planners foresee a total gas-fired power capacity of 60 GW, accounting for around 6% of the total installed capacity in the country. Despite these impressive projections, gas-fired power faces significant uncertainties in China: (1) there is an ongoing debate on whether China should develop gas-fired power, given the relative scarcity and higher cost of gas; (2) high gas prices and imported equipment limit the competitiveness of gas-fired power relative to a coal-fired one; (3) it lacks policy support. For the moment, gas-fired power plants are required to participate in a yet

  10. Increased wheeze but not bronchial hyperreactivity near power stations.

    Halliday, J A; Henry, R L; Hankin, R G; Hensley, M J


    In a previous study a higher than expected prevalence of asthma was found in Lake Munmorah, a coastal town near two power stations, compared with another coastal control town. This study aimed to compare atopy, bronchial hyperreactivity, and reported symptoms of asthma in the power station town and a second control area with greater socioeconomic similarity. A cross sectional survey was undertaken. Lake Munmorah, a coastal town near two power stations, and Dungog, a country town in the Hunter Valley, NSW, Australia. All children attending kindergarten to year 6 at all schools in the two towns were invited to participate in 1990. The response rates for the questionnaire for reported symptoms and associated demographic data were 92% in Lake Munmorah and 93% in Dungog, with 84% and 90% of children respectively being measured for lung function, atopy, and bronchial reactivity. There were 419 boys and 432 girls aged 5 to 12 years. Main outcome measures were current wheeze and bronchial hyper-reactivity, defined as a fall in forced expiratory volume in 1 second (FEV1) or peak expiratory flow (PEF) of 20% or more. Current wheeze was reported in 24.8% of the Lake Munmorah children compared with 14.6% of the Dungog children. Bronchial hyper-reactivity was similar for both groups--25.2% in Lake Munmorah and 22.3% in Dungog. The mean baseline FEV1 was lower in Lake Munmorah than in Dungog (p power station town, but bronchial hyper-reactivity and skin test defined atopy were similar in the two communities. These results are consistent with the previous study and confirm the increased presence of reported symptomatic illness in the town near power stations.

  11. Total life cycle cost model for electric power stations

    Cardullo, M.W.


    The Total Life Cycle Cost (TLCC) model for electric power stations was developed to provide a technology screening model. The TLCC analysis involves normalizing cost estimates with respect to performance standards and financial assumptions and preparing a profile of all costs over the service life of the power station. These costs when levelized present a value in terms of a utility electricity rate. Comparison of cost and the pricing of the electricity for a utility shows if a valid project exists. Cost components include both internal and external costs. Internal costs are direct costs associated with the purchase, and operation of the power station and include initial capital costs, operating and maintenance costs. External costs result from societal and/or environmental impacts that are external to the marketplace and can include air quality impacts due to emissions, infrastructure costs, and other impacts. The cost stream is summed (current dollars) or discounted (constant dollars) to some base year to yield a overall TLCC of each power station technology on a common basis. While minimizing life cycle cost is an important consideration, it may not always be a preferred method for some utilities who may prefer minimizing capital costs. Such consideration does not always result in technology penetration in a marketplace such as the utility sector. Under various regulatory climates, the utility is likely to heavily weigh initial capital costs while giving limited consideration to other costs such as societal costs. Policy makers considering external costs, such as those resulting from environmental impacts, may reach significantly different conclusions about which technologies are most advantageous to society. The TLCC analysis model for power stations was developed to facilitate consideration of all perspectives

  12. Environmental Assessment for the Warren Station externally fired combined cycle demonstration project



    The proposed Penelec project is one of 5 projects for potential funding under the fifth solicitation under the Clean Coal Technology program. In Penelec, two existing boilers would be replaced at Warren Station, PA; the new unit would produce 73 MW(e) in a combined cycle mode (using both gas-fired and steam turbines). The project would fill the need for a full utility-size demonstration of externally fire combined cycle (EFCC) technology as the next step toward commercialization. This environmental assessment was prepared for compliance with NEPA; its purpose is to provide sufficient basis for determining whether to prepare an environmental impact statement or to issue a finding of no significant impact. It is divided into the sections: purpose and need for proposed action; alternatives; brief description of affected environment; environmental consequences, including discussion of commercial operation beyond the demonstration period.

  13. Risk of loss power for ATWT in Daya Bay and Ling'ao nuclear power stations

    Guo Cheng


    In order to analyze the differences between the Anticipated Transient Without Reactor Trip (ATWT) and other reactor protection methods, this paper analyzes in detail the realizing means of ATWT and the effect of lost of power supply on the units based on Daya Bay and Ling'ao Nuclear Power Stations by system wiring diagram. Based on the comprehensive analysis,this paper proposes the sequence for powering when recovering the power source after ATWT power supply (LCC/LNE) loss for Daya Bay and Ling'ao Nuclear Power Stations. (authors)

  14. Failure at Zainsk thermal power station: lesson for thermal and nuclear power stations

    Derkach, A.L.; Klyuchnikov, A.A.; Fedorenko, G.M.; Kuz'min, V.V.


    An account of system failure at Zainsk Thermal PS on January 1-st, 1979 is given. The cause of failure - sudden unauthorized energizing of block transformer which led to a direct asynchronous start of 200 MW turbine generator from grid. The failure resulted in the explosion and fire in generator, shaft destruction, and the damage of the machine hall's roof. The core roots of the failure have been scrutinised

  15. Energy economics of nuclear and coal fired power plant

    Lee, Kee Won; Cho, Joo Hyun; Kim, Sung Rae; Choi, Hae Yoon


    The upturn of Korean nuclear power program can be considered to have started in early 70's while future plants for the construction of new nuclear power plants virtually came to a halt in United States. It is projected that power plant systems from combination of nuclear and coal fired types might shift to all coal fired type, considering the current trend of construction on the new plants in the United States. However, with the depletion of natural resources, it is desirable to understand the utilization of two competitive utility technologies in terms of of invested energy. Presented in this paper is a comparison between two systems, nuclear power plant and coal fired steam power plant in terms of energy investment. The method of comparison is Net Energy Analysis (NEA). In doing so, Input-Output Analysis (IOA) among industries and commodities is done. Using these information, net energy ratios are calculated and compared. NEA is conducted for power plants in U.S. because the availability of necessary data are limited in Korea. Although NEA does not offer conclusive solution, this method can work as a screening process in decision making. When considering energy systems, results from such analysis can be used as a general guideline. 2 figs., 12 tabs., 5 refs. (Author)

  16. Ten years of KRB Gundremmingen demonstration power station

    Facius, H. von; Ettemeyer, R.


    In August 1976 the first large nuclear power station in the Federal Republic, the KRB Gundremmingen plant with a net power of 237 MWe, has been in operation ten years. The construction of KRB as a demonstration plant was a major step forward on the way to the economic utilization of nuclear power for German utilities. Design and operation of the plant have decisively influenced the further development of the technology of light water reactors in the Federal Republic. Unlike the Kahl Experimental Nuclear Power Station (VAK), which was a test facility designed to generate experience and to train personnel, the decision to build KRB from the outset was conditional upon the fulfillment of economic criteria. Here are some of the aspects in which KRB has greatly influenced the development of nuclear power station technology: first application of internal steam-water separation instead of a steam drum with a water content of the steam of less than 1%; construction of a reactor buildung with all the necessary safety factors; solution of the corrosion and erosion problems linked with the use of a saturated steam turbine; special measures taken to prevent the turbine from speeding up due to post-evaporation effects after shutdown. Detailed comments are devoted to the subjects of availability, causes of failure and repair work. (orig.) [de

  17. Experiences of operation for Ikata Nuclear Power Station

    Kashimoto, Shigeyuki


    No. 1 plant in the Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc., is a two-loop PWR unit with electric output of 566 MW, and it began the commercial operation on September 30, 1977, as the first nuclear power station in Shikoku. It is the 13th LWR and 7th PWR in Japan. The period of construction was 52 months since it had been started in June, 1973. During the period, it became the object of the first administrative litigation to seek the cancellation of permission to install the reactor, and it was subjected to the influence of the violent economical variation due to the oil shock, but it was completed as scheduled. After the start of operation, it continued the satisfactory operation, and generated about 2.35 billion KWh for 4300 operation hours. It achieved the rate of utilization of 96.7%. Since March 28, 1978, the first periodical inspection was carried out, and abnormality was not found in the reactor, the steam generator and the fuel at all. The period of inspection was 79 days and shorter than expected. The commercial operation was started again on June 14. The outline of the Ikata Nuclear Power Station, its state of operation, and the periodical inspection are reported. Very good results were able to be reported on the operation for one year, thanks to the valuable experiences offered by other electric power companies. (Kako, I.)

  18. Shippingport Atomic Power Station decommissioning program and applied technology

    Crimi, F P; Skavdahl, R E


    The Shippingport Station decommissioning project is the first decommissioning of a large scale nuclear power plant, and also the first nuclear power plant to be decommissioned which has continued the power operation as long as 25 years. The nuclear facilities which have been decommissioned so far have operated for shorter period and were small as compared with commercial power reactors, but the experience gained by those decommissionings as well as that gained by nuclear plant maintenance and modification has helped to establish the technology and cost basis for Shippingport and future decommissioning projects. In this paper, the current status of the preparation being made by the General Electric Co., its subcontractor and the US Department of Energy for starting the decommissioning phase of the Shippingport Atomic Power Station is described. Also remote metal cutting, decontamination, concrete removal, the volume reduction of liquids and solids and robotics which will be applied to the project are discussed. The Shippingport Station is a 72 MWe PWR plant having started operation in 1957, and permanently shut down in 1982, after having generated over 7.4 billion kWh of electricity.

  19. Operating experience and performance at Narora Atomic Power Station

    Mittal, Subhash; Gupta, J.P.


    Narora Atomic Power Station consists of two units of 220 MWe capacity each. These are Pressurized Heavy Water Reactors, fuelled by natural uranium, moderated and cooled by heavy water. The Station is owned by Nuclear Power Corporation of India Ltd., which is responsible for design, construction, commissioning, and operation of all nuclear power stations in the country. NAPS was the first opportunity to apply operating experiences in design, keeping in view the evolving safety and seismicity requirements, ease of maintenance, inservice inspection needs, improved construction ability and standardization. Both the units of NAPS are having improved safety standards of current international levels. All the equipment are indigenous with improved quality and reliability. The first unit of the station went critical in March 1989 and synchronized to the grid in July 1989. The second units followed with its criticality in October 1991 and synchronization in January 1992. Considering the initial stabilizing period, the performance of both units of NAPS has progressively improved over the years. The annual capacity factor for NAPS - 1 was 90.01% and for NAPS - 2 was 89.01% for the financial year 1997-1998. This paper presents an analysis of the performance during the last three years and measures taken to improve it. The stated enhanced performance could be achieved by improvement in human performance by training/re-training, scrupulous monitoring and review of equipment/systems, institution of adequate procedure and ensuring their adherence. (authors)

  20. Computer based training simulator for Hunterston Nuclear Power Station

    Bowden, R.S.M.; Hacking, D.


    For reasons which are stated, the Hunterston-B nuclear power station automatic control system includes a manual over-ride facility. It is therefore essential for the station engineers to be trained to recognise and control all feasible modes of plant and logic malfunction. A training simulator has been built which consists of a replica of the shutdown monitoring panel in the Central Control Room and is controlled by a mini-computer. This paper highlights the computer aspects of the simulator and relevant derived experience, under the following headings: engineering background; shutdown sequence equipment; simulator equipment; features; software; testing; maintenance. (U.K.)

  1. The Heysham 2 and Torness nuclear power station projects

    Cameron, P.J.


    At the beginning of the design of the Heysham 2 and Torness Nuclear Power Stations in the UK, it was agreed that the Hinkley Point B/Hunterston B Advanced Gas Cooled reactor design would be repeated. However, the Hinkley Point B/Hunterston B designs dated from 1964, and inevitably safety requirements had escalated in the intervening years. Furthermore, operating experience gained from Hinkley Point B/Hunterston B showed that it was desirable to make changes to particular features. Design changes were therefore included where it was considered essential to improve performance, to improve safety and to improve engineering. The resulting station designs are described. (author)

  2. Transwaal - economic district heat from the Beznau nuclear power station

    Schatzmann, G.


    Initial study phases of the Transwaal project for distribution of heat from the Beznau nuclear power station via pipe lines to Aare and Limmat valley regions in Switzerland are presented. 500 MW heat availability through heat exchangers providing forward flow water temperature of 120 0 C, pipe line network and pumping station aspects, and the system energy flow diagram, are described. Considerations based on specific energy requirements in the year 2000 including alternative schemes showed economic viability. Investment and consumer costs and savings compared with oil and gas heating are discussed. Heat supply is guaranteed well into the 21st century and avoids environmental disadvantages. (H.V.H.)

  3. Updating of the fire fighting systems and organization at the Embalse nuclear power plant, Argentina

    Acevedo, C.F.


    A brief description is given of the updating carried out at the Embalse NPP after commissioning, covering the station fire equivalent loads, the station weak points from the fire point of view, the possible upgrading of systems or technological improvements, early alarm and automatic actions, organizations, education and training, and drills. (author)

  4. Planning new coal-fired power plants

    Benesch, W.A. [STEAG encotec GmbH, Essen (Germany)


    When considering fossil energy sources, it can be seen that natural gas and oil will become much scarcer than coal. Therefore, one practical option is to investigate and further develop coal-based energy supplies for the future. However, the existing coal stocks must be used very sparingly. Consequently, the conversion efficiency of the chemically-bonded energy in power and heat needs to be improved. By these means, and also by modern environmental engineering, power can be generated from coal without harming the environment. (orig.)

  5. Strategy and system of fire protection at Guangdong Daya Bay Nuclear Power Plant

    Zhou Weihong


    The fire protection is an important safety issue of nuclear power utilities. The author depicts the strategy and management system of fire protection implemented successfully at Guangdong Daya Bay Nuclear Power Plant of China

  6. Advanced fire observation by the Intelligent Infrared Sensor prototype FOCUS on the International Space Station

    Oertel, D.; Haschberger, P.; Tank, V.; Lanzl, F.; Zhukov, B.; Jahn, H.; Briess, K.; Lorenz, E.; Roeser, H.-P.; Ginati, A.; Tobehn, C.; Schulte in den Bäumen, J.; Christmann, U.


    Current and planned operational space-borne Earth observation systems provide spatially, radiometrically or temporally crude data for the detection and monitoring of high temperature phenomena on the surface of our planet. High Temperature Events (HTE) very often cause environmental disasters. Such HTE are forest and savannah fires, fires of open coal mines, volcanic activities and others (e.g. fires of oil wells, pipelines etc.). A simultaneous co-registration of a combination of infrared (IR) and visible (VIS) channels is the key for a reliable autonomous on-board detection of High Temperature Events (HTE) on Earth surface, such as vegetation fires and volcano eruptions. This is the main feature of the FOCUS experiment. Furthermore there are ecology-oriented objectives of the FOCUS experiment mainly related to spectrometric/imaging remote inspection and parameter extraction of selected HTEs, and to the assessment of some ecological consequences of HTEs, such as aerosol and gas emission. Based on own experimental work and supported by Co-Investigators from Italy, Greece, France, Spain, Russia and Germany, DLR proposed in 1997 to use the International Space Station (ISS) in its early utilization phase as a platform and test-bed for an Intelligent Infrared Sensor prototype FOCUS of a future Environmental Disaster Recognition Satellite System. FOCUS is considered by ESA as an important mission combining a number of proven technologies and observation techniques to provide the scientific and operational user community with key data for the classification and monitoring of forest fires. FOCUS was selected as one of five European ``Groupings'' to be flown as an externally mounted payload during the early utilisation phase of the ISS. The FOCUS Phase A Study will be performed by OHB-System, DLR and Zeiss from September 1998 until May 1999.

  7. Inspection of fire protection measures and fire fighting capability at nuclear power plants. A publication within the NUSS programme


    The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire protection of nuclear power plants. The publication outlines practices for inspecting the fire protection measures at nuclear power plants in accordance with Safety Series No.50-SG-D2(Rev.1), Fire Protection in Nuclear Power Plants, and includes a comprehensive fire safety inspection checklist of the specific elements to be addressed when evaluating the adequacy and effectiveness of the fire protection measures and manual fire fighting capability available at operating nuclear power plants. The publication will be useful not only to regulators and safety assessors but also to operators and designers. The book addresses a specialized topic and it is recommended that it be used in conjunction with Safety Guide No.50-SG-D2(Rev.1)

  8. Radioactivity of combustion residues from coal-fired power stations

    Vom Berg, W.; Puch, K.H.


    Each year in Germany, about 18 mill. t of combustion residues are produced from the combustion of bituminous coal and lignite. They are utilized to a great extent in the construction industry and in mining. During the combustion of coal, the radio-nuclides remain predominantly in the ash. The radionuclide concentration in lignite ash is within the range of that in natural soil. The combustion residues of bituminous coal contain radio-nuclides of a similar order of magnitude as also can occur in natural rock. The utilization of combustion residues in construction materials makes a negligible contribution to radiation exposure through retention in buildings. (orig.) [de

  9. The state of art of internal fire PSA in nuclear power plant

    Yu Xinli; Zhao Bo; Zheng Xiangyang


    The operational experiences of nuclear power plants (NPPs) show that the internal fires challenge effectively the nuclear safety of NPPs. Thus, the authorities having jurisdiction in the world have enhanced the supervision on fire safety in NPPs, asking the licensees to perform fire hazard analysis and evaluate the fire risk. This article mainly describes the state of art of internal fire probabilistic safety assessment (PSA) in the world, and compares the main methods and standards for internal fire PSA. (authors)

  10. Preparation of sewage sludges for the thermal disposal in lignite power stations. Aufbereitung von Klaerschlaemmen zur thermischen Entsorgung in Braunkohlenkraftwerken

    Krone, C.; Koch, J.; Leidel, H.; Scheel, W. (VEAG Vereinigte Energiewerke AG, Ingenieurunternehmen fuer Kraftwerks-, Energie- und Umwelttechnik, Vetschau (Germany))


    The thermal disposal of communal sewage sludges as well as the additional combustion of such substances in furnaces of power station boilers are really no technical solutions. New are the consideration concerning the sludge preparation with the aid of the steam fluidized bed drying process and the additional combustion of the dried products in raw-brown-coal-fired large-scale steam generators. - The investigation proves the technical feasibility and points to problems which still have to be tackled. (orig.).

  11. Techno-Economic Analysis of Integration of Low-Temperature Geothermal Resources for Coal-Fired Power Plants

    Bearden, Mark D.; Davidson, Casie L.; Horner, Jacob A.; Heldebrant, David J.; Freeman, Charles J.


    Presented here are the results of a techno-economic (TEA) study of the potential for coupling low-grade geothermal resources to boost the electrical output from coal-fired power plants. This study includes identification of candidate 500 MW subcritical coal-fired power plants in the continental United States, followed by down-selection and characterization of the North Valmy generating station, a Nevada coal-fired plant. Based on site and plant characteristics, ASPEN Plus models were designed to evaluate options to integrate geothermal resources directly into existing processes at North Valmy. Energy outputs and capital costing are presented for numerous hybrid strategies, including integration with Organic Rankine Cycles (ORCs), which currently represent the primary technology for baseload geothermal power generation.

  12. Trace metal emissions from the Estonian oil shale fired power

    Aunela-Tapola, Leena A.; Frandsen, Flemming; Häsänen, Erkki K.


    Emission levels of selected trace metals from the Estonian oil shale fired power plant were studied. The plant is the largest single power plant in Estonia with an electricity production capacity of 1170 MWe (1995). Trace metals were sampled from the flue gases by a manual method incorporating...... in the flue gases of the studied oil shale plant contribute, however, to clearly higher total trace metal emission levels compared to modern coal fired power plants. Although the old electrostatic precipitators in the plant have been partly replaced by state-of-the-art electrostatic precipitators...... a two-fraction particle sampling and subsequent absorption of the gaseous fraction. The analyses were principally performed with ICP-MS techniques. The trace metal contents of Estonian oil shale were found to be in the same order of magnitude as of coal on average. The high total particle concentrations...

  13. Failure analysis of fire resistant fluid (FRF piping used in hydraulic control system at oil-fired thermal power generation plant

    Muhammad Akram


    Full Text Available This is a case study regarding frequent forced outages in an oil-fired power generating station due to failure of fire resistant fluid (FRF piping of material ASTM A-304. This analysis was done to find out the most probable cause of failure and to rectify the problem. Methods for finding and analyzing the cracks include nondestructive testing techniques such as visual testing (VT and dye penetrant testing (PT along with that periodic monitoring after rectification of problem. The study revealed that pitting and pit to crack transitions were formed in stainless steel piping containing high pressure (system pressure 115 bars fire resistant fluid. However, after replacement of piping the pitting and cracking reoccurred. It was observed that due to possible exposure to chlorinated moisture in surrounding environment pitting was formed which then transformed into cracks. The research work discussed in this paper illustrates the procedure used in detection of the problem and measures taken to solve the problem.

  14. A fire hazard analysis at the Ignalina nuclear power plant

    Joerud, F.; Magnusson, T.


    The fire hazard analysis (FHA) of the Ignalina Nuclear Power Plant (INPP) Unit no.1 was initiated during 1997 and is estimated to finalise in summer 1998. The reason for starting a FHA was a recommendation in the Safety Analysis Report and its review to prioritise a systematic FHA. Fire protection improvements had earlier been based on engineering assessments, but further improvements required a systematic FHA. It is also required by the regulator for licensing of unit no.1. In preparation of the analysis it was decided to perform a deterministic FHA to fulfil the requirements in the IAEA draft of a Safety Practice ''Preparation of Fire Hazard Analyses for Nuclear Power Plants''. As a supporting document the United States Department of Energy Reactor Core Protection Evaluation Methodology for Fires at RBMK and WWER Nuclear Power Plants (RCPEM) was agreed to be used. The assistance of the project is performed as a bilateral activity between Sweden and UK. The project management is the responsibility of the INPP. In order to transfer knowledge to the INPP project group, training activities are arranged by the western team. The project will be documented as a safety case. The project consists of parties from INPP, Sweden, UK and Russia which makes the project very dependent of good communication procedures. The most difficult problems is except from the problems with translation, the problems with different standards and lack of testing protocols of the fire protection installations and problems to set the right level of screening criteria. There is also the new dimension of making it possible to take credit for the fire brigade in the safety case, which can bring the project into difficulties. The most interesting challenges for the project are to set the most sensible safety levels in the screening phase, to handle the huge volume of rooms for survey and screening, to maintain the good exchange of fire- and nuclear safety information between all the parties involved

  15. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    Zagorski, J. F.


    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  16. Stade nuclear power station (KKS): four giants on tour

    Beverungen, M.; Viermann, J.


    The Stade nuclear power station was the first nuclear power plant in the Federal Republic of Germany to deliver heat in addition to electricity. Since 1984, district heat was distributed to a saltworks nearby. The power plant, which is situated on the banks of the river Elbe, was commissioned in 1972 after approximately 4 years of construction. Together with the Wuergassen plant, it was among the first commercial nuclear power plants in this country. E.ON Kernkraft holds a 2/3 interest, Vattenfall Europe a 1/3 interest in the nuclear power plant. The Stade nuclear power station was decommissioned on November 14, 2003 for economic reasons which, in part, were also politically motivated. In September 2005, the permit for demolition of the nuclear part was granted. The release from supervision under the Atomic Energy Act is expected for 2014. In the course of demolition, the 4 steam generators of the Stade nuclear power station were removed. These components, which have an aggregate weight of approx. 660 tons, are to be safely re-used in Sweden. In September 2007, the steam generators were loaded on board the Swedish special vessel, MS Sigyn, by means of a floating crane. After shipment to Sweden, heavy-duty trucks carried the components to the processing hall of Studsvik AB for further treatment. After 6 months of treatment, the contaminated inner surfaces of the tube bundles of the steam generators have been decontaminated successfully, among other items. This has increased the volume of material available for recycling and thus decreased the volume of residues. (orig.)

  17. 76 FR 81998 - Methodology for Low Power/Shutdown Fire PRA


    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0295] Methodology for Low Power/Shutdown Fire PRA AGENCY..., ``Methodology for Low Power/Shutdown Fire PRA--Draft Report for Comment.'' DATES: Submit comments by March 01... risk assessment (PRA) method for quantitatively analyzing fire risk in commercial nuclear power plants...

  18. The turbine oil fire in the nuclear power plant, Muehleberg

    Lutz, H.R.


    At 21.15 hours on the evening of the 28th July 1971, a turbine oil fire broke out in the Nuclear Power Plant Muehleberg of the Bernische Kraftwerke AG, resulting in damage amounting to around 20 million Swiss Francs and a delay of some ten months in putting the plant into operation. The plant is equipped with a General Electric boiling water reactor and two BBC saturated steam turbines. Up to the time of the fire, both turbo-sets had already been run singly up to their full capacity of 160 MWe and the initial trials with both sets working parallel were shortly due to be carried out. Following the outbreak of fire, the causes of which are described in the contributions of the authors Hagn, L. and H. Huppmann and Christian, H. and H. Grupp, fire fighting action was immediately taken, in line with the emergency measures laid down in the operating regulations. With the assistance of the Berne City Fire Brigade, the blaze in the roof of the turbine hall was first extinguished and the spreading cable conflagration then fought, using foam and water. (orig.) [de

  19. Occupational radiation exposures at Canadian CANDU nuclear power stations

    LeSurf, J.E.; Taylor, G.F.


    In Canada, methods to reduce the radiation exposure to workers at nuclear power reactors have been studied and implemented since the early days of the CANDU reactor program. Close collaboration between the designers, the operators, and the manufacturers has reduced the total exposure at each station, the dose requirement to operate and maintain each successive station compared with earlier stations, and the average annual exposure per worker. Specific methods developed to achieve dose reduction include water chemistry; corrosion resistant materials; low cobalt materials; decontamination; hot filtration, improved equipment reliability, maintainability, and accessibility; improved shielding design and location; planning of work for low exposure; improved operating and maintenance procedures; removal of tritium from D 2 O systems and work environments; improved protective clothing; on-power refuelling; worker awareness and training; and many other small improvements. The 1981 occupational dose productivity factors for Pickering A and Bruce A nuclear generating stations were respectively 0.43 and 0.2 rem/MW(e).a

  20. RAM investigation of coal-fired thermal power plants: A case study

    D. Bose


    Full Text Available Continuous generation of electricity of a power plant depends on the higher availability of its components/equipments. Higher availability of the components/equipments is inherently associated with their higher reliability and maintainability. This paper investigates the reliability, availability and maintainability (RAM characteristics of a 210 MW coal-fired thermal power plant (Unit-2 from a thermal power station in eastern region of India. Critical mechanical subsystems with respect to failure frequency, reliability and maintainability are identified for taking necessary measures for enhancing availability of the power plant and the results are compared with Unit-1 of the same Power Station. Reliability-based preventive maintenance intervals (PMIs at various reliability levels of the subsystems are estimated also for performing their preventive maintenance (PM. The present paper highlights that in the Unit-2, Economizer (ECO & Furnace Wall Tube (FWT exhibits lower reliability as compared to the other subsystems and Economizer (ECO & Baffle Wall Tube (BWT demands more improvement in maintainability. Further, it has been observed that FSH followed Decreasing Failure Rate (DFR and Economizer (ECO is the most critical subsystem for both the plants. RAM analysis is very much effective in finding critical subsystems and deciding their preventive maintenance program for improving availability of the power plant as well as the power supply.

  1. Converting Existing Copper Wire Firing System to a Fiber Optically Controlled Firing System for Electromagnetic Pulsed Power Experiments


    Pulsed Power Experiments by Robert Borys Jr Weapons and Materials Research Directorate, ARL Colby Adams Bowhead Total Enterprise Solutions...ARL-TN-0863 ● DEC 2017 US Army Research Laboratory Converting Existing Copper Wire Firing System to a Fiber-Optically Controlled...Firing System for Electromagnetic Pulsed Power Experiments by Robert Borys Jr and Colby Adams Approved for public release

  2. Design Provisions for Station Blackout at Nuclear Power Plants

    Duchac, Alexander


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

  3. (Shippingport Atomic Power Station). Quarterly operating report, fourth quarter 1980


    At the beginning of the fourth quarter of 1980, the Shippingport Atomic Power Station remained shutdown for the normally planned semiannual maintenance and testing program, initiated September 12, 1980. Operational testing began on November 7. Maximum power was achieved November 28 and was maintained throughout the remainder of the quarter except as noted. The LWBR Core has generated 19,046.07 EFPH from start-up through the end of the quarter. During this quarter, approximately 0.000025 curies of Xe 133 activity were released from the station. During the fourth quarter of 1980, 1081 cubic feet of radioactive solid waste was shipped out of state for burial. These shipments contained 0.037 curies of radioactivity.

  4. Quality assurance in the structural installations of nuclear power stations

    Schnellenbach, G.; Wrage, S.


    The concept of quality assurance distinguishes between self-monitoring of the design, manufacturing and executing firms and external monitoring by state institutions or by experts commissioned by them. The long-term control of structures is within the area of responsibility of the owner. This quality assurance concept is controlled in detail by statutes, which clearly define responsibilities. This structural engineering quality assurance system also forms the basis for the design, construction and utilization of structural installations of nuclear power stations; requirements emanating from the Atomic Energy Acts for the structural installations demand, however, to some extent a sharpening of self- and external monitoring. Therefore, today a quality concept has been developed for the important engineering safety-related buildings of nuclear power stations. This concept takes account of the strict requirements imposed and fulfils the requirement of KTA 1401. (orig.) [de

  5. Organization of radiation protection in German nuclear power stations


    Using the operating handbooks of the nuclear power stations in West Germany, an examination was carried out of how far the existing organisational structure for radiation protection fulfils the requirements for protection and whether a standardisation of the organisation would provide improvements for the protection of the personnel and for the practicability of the radiation protection organisation. In particular, the parts 'Personnel operating organisation', 'Radiation protection order' and 'Maintenance order' of the operating handbook were evaluated and an audit was made of the radiation protection organisation. In general, the result of the assessment is that the organisation of radiation protection does not contradict the orders, guidelines and regulations in any of the nuclear power stations examined. Corresponding to the possibilities of regulating details of the radiation protection organisation within the undertaking, the target of 'protection of the personnel against radioactive irradiation' is achieved by the various organisation structures which are largely equal to the given example. (orig./HP) [de

  6. High system-safety level of nuclear power stations

    Lutz, H.R.


    A bluntly worded disquisition contrasting the incidence of death and harm to persons in the chemical industry with the low hazards in nuclear power stations. Quotes conclusions from a U.S. accident study that the risk from 100 large power stations is 100 times smaller than from chlorine manufacture and transport. The enclosure of a reactor in a safety container, the well understood effects of radioactivity on man, and the ease of measuring leakage well below safe limits, are safety features which he considers were not matched in the products and plant of the Seveso factory which suffered disaster. Questions the usefulness of warnings about nuclear dangers when chemical dangers are much greater and road dangers very much greater still. (R.W.S.)

  7. Environmental qualification test of electrical penetration for nuclear power stations

    Kooziro, Tetsuya; Nakagawa, Akitoshi; Toyoda, Shigeru; Uno, Shunpei


    Environmental qualification test was conducted according to IEEE Std. 323-1974 in order to evaluate the safety and reliability of electrical penetration of PWR type nuclear power station. Electrical penetration is the assemblies of electric cables attached to the containment vessel and penetrate through the vessel. Since it is a part of the vessel, it is deemed to be one of the primary safety equipments that are important for the safety and reliability of nuclear power stations. Environmental tests were conducted continuously as to heat cycle, vibration and LOCA with the full size specimens of bushing type, pigtail type and triaxial cable type and at the same time thermal life and irradiation tests were conducted on the insulation materials used, in order to obtain the comprehensive evaluation of their electrical and mechanical characteristics. As the result, they all satisfied the requirements for the circuits for actual use during and after various environmental qualification tests according to IEEE Std. 323. (author)

  8. Evaluation of Shoreham Nuclear Power Station, Unit 1 technical specifications

    Baxter, D.E.; Bruske, S.J.


    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Shoreham Nuclear Power Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Shoreham T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Shoreham Nuclear Power Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  9. Radiator selection for Space Station Solar Dynamic Power Systems

    Fleming, Mike; Hoehn, Frank

    A study was conducted to define the best radiator for heat rejection of the Space Station Solar Dynamic Power System. Included in the study were radiators for both the Organic Rankine Cycle and Closed Brayton Cycle heat engines. A number of potential approaches were considered for the Organic Rankine Cycle and a constructable radiator was chosen. Detailed optimizations of this concept were conducted resulting in a baseline for inclusion into the ORC Preliminary Design. A number of approaches were also considered for the CBC radiator. For this application a deployed pumped liquid radiator was selected which was also refined resulting in a baseline for the CBC preliminary design. This paper reports the results and methodology of these studies and describes the preliminary designs of the Space Station Solar Dynamic Power System radiators for both of the candidate heat engine cycles.

  10. Safety aspects of station blackout at nuclear power plants


    The principal focus of this report is on existing light water reactor nuclear power plants. However, many of the considerations discussed herein can be equally applied to new plants, i.e. those not yet in construction. This report is organized to provide a description of design and procedural factors which safety assessments and reviews of operating experience have shown to be important. These are divided into the off-site power system, the on-site AC power systems and alternate (or nearby) sources of power. The latter may be used in the unlikely event that both normal off-site and on-site sources fail. It must be emphasized that first priority should be placed on designing and maintaining high reliability of both the off-site and on-site AC power systems. This basic concept also applies to the capabilities for restoring power sources which failed and making use of all available alternative and nearby power sources during an emergency, to restore AC power in a prompt manner. Discussions on these aspects are provided in chapters 2 and 3 of this report. Because the expected event frequency and associated confidence in such estimations of station blackout are uncertain, preparations should be made to deal with a station blackout. The nature of those preparations, whether they be optimizing emergency procedures to use existing equipment, modifying this equipment to enhance capabilities, or adding new components or systems to cope with station blackout, must be made in light of plant-specific assessments and regulatory safety philosophies/requirements. Discussions on these matters are provided in chapter 4. General and specific conclusions and recommendations are provided in chapter 5. Appendix A provides a description of several case studies on station blackout and loss of off-site power. Abstracts of papers and presentations are provided in Appendix B with authors and affiliations identified to facilitate personal contact. The References and Bibliography contain a

  11. The economic benefits of Koeberg nuclear power station

    Robb, W.


    The paper deals with the economics of the Koeberg power plant in 3 main parts, namely the economic benefit to Escom of going nuclear; the economic benefit to South Africa; and suggestions for the energy future in South Africa. In the first part, the cost of nuclear and coal-fired power plants is compared. Construction and operating costs are looked at as well as the cost of waste disposal. Other factors which are considered include security, insurance costs, personnel requirements and efficiency. In part two aspects such as the saving of coal and water; the prevention of environmental damage and health hazards; the stimulation of the economy and job creation; and the security of the power supply are considered. In the third part the author draws certain conclusions from the first two parts of the paper and makes suggestions to persons who would like to assess the situation

  12. Quality assurance at a German power station company

    Czychon, K.H.


    The Integrated Operational Management System of the Emsland nuclear power station is described, together with its aims and system architecture as well as the structure and modus operandi of the Integrated Operational Management System Manager. The completion of repair work and the processing of modification and maintenance reports are explained as examples. Experience gained in the introduction and use of the system is presented. figs., 6 refs

  13. Dungeness Power Station off-site emergency plan


    This off-site Emergency Plan in the event of an accidental release of radioactivity at the Dungeness Nuclear power station sets out the necessary management and coordination processes between Nuclear Electric, operators of the site, the emergency services and relevant local authorities. The objectives promoting the aim are identified and the activities which will be undertaken to protect the public and the environment in the event of an emergency are outlined. (UK)

  14. Legionella control in power station cooling towers using oxidising biocides

    Sailer, Christian; Rawlinson, Julia; Killeen, Paul [Ecolab PTY LTD, Ascot, WA (Australia)


    Power stations have used oxidising biocides such as chlorine or bromine for many years to control microbial growth in their cooling towers. In this paper Ecolab trademark looks at the direct effect halogen concentration has on Legionella populations in order to determine the most effective halogenation rate required to ensure that the site key performance indicator (KPI) of < 100 colony-forming units (cfu) per mL can be maintained. (orig.)

  15. Quality assurance grading of conventional equipment at nuclear power station

    Li Ping; Li Shichang


    Equipment QA grading with the systematic and standardized approach will benefit the concerned organizations by effective allocating of limited resources to guarantee the quality of essential equipment. This paper presents a new quality assurance grading system for the convention systems/equipment of nuclear power station, which is operative and at the same time could help the owner to allot resource reasonably through the analysis of the purpose of grading and the experience and lessons of LINGAO Phase I project. (authors)

  16. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Hawes, F.B.


    The biological consequences of using a direct cooled system at the proposed Sizewell B power station are dealt with. Problems caused by the impingement of organisms on the fine-mesh screens through which the water is pumped, by the entrainment of smaller organisms in the flow through the cooling system and by the discharge of warmed chlorinated water into the sea are discussed. The chlorination of cooling water is described. (U.K.)

  17. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Newell, J.E.


    A brief description is given of the design of the steam generators for the proposed Sizewell B power station. A review of the operational behaviour of earlier models is presented. The problem of degradation of steam generator tubes is considered in some detail. Model F steam generator, which has been incorporated into the Sizewell B reference design, is discussed. Finally the impact of steam generator tube degradation upon radiological safety is discussed. (U.K.)

  18. Notes on organization of nuclear power station construction

    Marsicanin, B.


    After a visite to some european nuclear power stations under construction and in operation, in this report a short general view on this subject is given. The progress in this in large, industrialised countries is considered as well as the relevant experience in developing countries. The new role of nuclear research institutes during construction and operation is pointed out and prospects of this cooperation evaluated. (author)

  19. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    Dutton, L.M.


    A description is given of the main sources of radioactivity and the barriers which would prevent their release at the proposed Sizewell B nuclear power station. The methods of calculating the radiological consequences associated with the most significant faults within the design are outlined. The following possibilities are considered: faults involving high fuel temperatures; loss of coolant accidents; secondary coolant circuit faults; waste processing system faults; irradiated fuel faults. (U.K.)

  20. Process for treating waste water containing hydrazine from power stations

    Hoffmann, W.


    A process for treating waste water containing hydrazine from nuclear power stations is proposed, characterized by the fact that the water is taken continuously through a water decomposition cell. If the water does not have sufficient conductivity itself, a substance raising the electrical conductivity is added to the water to be treated. The electrolysis is situated in the waste water tank. (orig./RB) [de

  1. An adaptive predictive controller and its applications in power stations

    Yang Zhiyuan; Lu Huiming; Zhang Xinggao [North China Electric Power University, Beijing (China); Song Chunping [Tsinghua University, Beijing (China). Dept. of Thermal Energy Engineering


    Based on the objective function in the form of integration of generalized model error, a globally convergent model reference adaptive predictive control algorithm (MRAPC) containing inertia-time compensators is presented in this paper. MRAPC has been successfully applied to control important thermal process of more than 20 units in many Chinese power stations. In this paper three representative examples are described. Continual operation results for years demonstrate that MRAPC is a successful attempt for the practical applications of adaptive control techniques. (author)

  2. 47 CFR 74.710 - Digital low power TV and TV translator station protection.


    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator station... SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.710 Digital low power TV and TV translator station protection. (a) An application to construct a new low power TV, TV translator, or TV...

  3. 47 CFR 74.792 - Digital low power TV and TV translator station protected contour.


    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator station... SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.792 Digital low power TV and TV translator station protected contour. (a) A digital low power TV or TV translator will be protected from...

  4. 47 CFR 74.707 - Low power TV and TV translator station protection.


    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Low power TV and TV translator station... SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.707 Low power TV and TV translator station protection. (a)(1) A low power TV or TV translator will be protected from interference from other...

  5. Axial power deviation control strategy and computer simulation for Daya Bay Nuclear Power Station

    Liao Yehong; Zhou Xiaoling, Xiao Min


    Daya Bay Nuclear Power Station has very tight operation diagram especially at its right side. Therefore the successful control of axial power deviation for PWR is crucial to nuclear safety. After analyzing various core characters' effect on axial power distribution, several axial power deviation control strategies has been proposed to comply with different power varying operation scenario. Application and computer simulation of the strategies has shown that our prediction of axial power deviation evolution are comparable to the measurement values, and that our control strategies are effective. Engineering experience shows that the application of our methodology can predict accurately the transient of axial power deviation, and therefore has become a useful tool for reactor operation and safety control. This paper presents the axial power control characteristics, reactor operation strategy research, computer simulation, and comparison to measurement results in Daya Bay Nuclear Power Station. (author)


    Eugênio P. Costa


    Full Text Available This study aimed to analyze aspects of fire use on urban areas around Águas Emendadas Ecological Station (ESECAE, in Distrito Federal, and to evaluate the foremost fire occurrences, equipment availability and tools for combatants and beyond decreasing forest fire incidences. The local population in town region around it (considering three kilometers as ray from the station, fire crew members units of conservation and the garrison body of firemen were interviewed in a representative form. Results had shown that most inclined areas to forest fire occurrence (33.4% highways edges and secondary roads had their localization related to urban environment, in which 34% of residents used fire as land cleanness. Machines availability, tools and equipment for execution of the activities on prevention and combat exist; however, there is not any equipment for individual protection for all fire crew members. As a solution, educative campaigns to emphasize the negative consequences of using fire (as a tool land and also to alert people for the risks caused by it should be done.

  7. Concrete works in Igata Nuclear Power Station Unit-2

    Yanase, Hidemasa


    The construction of Igata Nuclear Power Station Unit-2 was started in February, 1978, and is scheduled to start the commercial operation in March, 1982. Construction works are to be finished by August, 1981. The buildings of Igata Nuclear Power Station are composed of large cross section concrete for the purpose of shielding and the resistance to earth quakes. In response to this, moderate heat Portland cement has been employed, and in particular, the heat of hydration has been controlled. In this report, also fine and coarse aggregates, admixtures and chemical admixtures, and further, the techniques to improve the quality are described. Concrete preparation plant was installed in the power station site. Fresh concrete was carried with agitator body trucks from the preparation plant to the unloading point, and from there with pump trucks. Placing of concrete was carried out, striving to obtain homogeneous and dense concrete by using rod type vibrators. Further, concrete was placed in low slump (8 - 15 cm) to reduce water per unit volume, and its temperature was also carefully controlled, e.g., cold water (temperature of mixing water was about 10 deg C) was used in summer season (end of June to end of September). As a result, the control target was almost satisfied. As for testing and inspection, visual appearance test was done as well as material testing in compliance with JIS and other standards. (Wakatsuki, Y.)

  8. Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium



    The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper Refs, figs, tabs

  9. Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium


    The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper

  10. A list of abnormal occurences at Swedish nuclear power stations

    McHugh, B.


    This report consists of a list of extracts from documents belonging to Statens Kaernkraftinspektion (SKI) in Sweden. It deals with non-routine occurrences at the Swedish nuclear power stations which are in operation or where test operations of components and systems have started. The investigation has included matter about the following nuclear power plants: Barsebaeck-1, Oskarshamn-1, Oskarshamn-2, Ringhals-1, Ringhals-2, Aagesta. In all cases from the start of the test operations up to latest the 1st of June 1974. (M.S.)

  11. Fundamentals of asset management in an ageing nuclear power station

    Crook, B.


    In an ageing nuclear power station there are many challenges associated with implementing and refining an asset management program. Ageing nuclear power stations are faced with the formidable task of replacing and refurbishing major Structures, Systems, and Components (SSCs) in a managed and cost-effective way. This paper provides a brief background on equipment reliability and asset management, covers Bruce Power's methodology for implementing this complex and all-encompassing program, and describes one of the key challenges faced by Bruce Power and the industry. The effective scoping and identification of critical components is an on-going challenge which can affect the integrity of many processes built upon it. This is a fundamental building block to nearly all processes at Bruce Power and one that is at the centre of many improvement initiatives and projects. The consequences from lacking this baseline data, or worse relying upon incorrect data, can permeate the asset management process and hinder the organization's ability to assess risk properly and take the necessary steps to mitigate this risk in the short and long term. (author)

  12. Evaluating the Thermal Pollution Caused by Wastewaters Discharged from a Chain of Coal-Fired Power Plants along a River

    Marc A. Rosen


    Full Text Available Reliable and safe operation of a coal-fired power plant is strongly linked to freshwater resources, and environmental problems related to water sources and wastewater discharge are challenges for power station operation. In this study, an evaluation on the basis of a wastewater thermal pollution vector is reported for the environmental impact of residual water generated and discharged in the Jiu River during the operation of thermoelectric units of the Rovinari, Turceni and Craiova coal-fired power plants in Romania. Wastewater thermal pollutant vector Plane Projection is applied for assessing the water temperature evolution in the water flow lane created downstream of each power plant wastewater outlet channel. Simulation on the basis of an Electricity of France model, and testing validation of the results for thermoelectric units of 330 MW of these power plants are presented.

  13. Waste generation comparison: Coal-fired versus nuclear power plants

    LaGuardia, T.S.


    Low-level radioactive waste generation and disposal attract a great deal of attention whenever the nuclear industry is scrutinized by concerned parties, be it the media, the public, or political interests. It is therefore important to the nuclear industry that this issue be put into perspective relative to other current forms of energy production. Most of the country's fossil-fueled power comes from coal-fired plants, with oil and gas as other fuel sources. Most of the generated waste also comes from coal plants. This paper, therefore, compares waste quantities generated by a typical (1150-MW(electric)) pressurized water reactor (PWR) to that of a comparably sized coal-fired power plant

  14. Technologically enhanced natural radioactivity around the coal fired power plant

    Kovac, J.; Marovic, G.


    In some situations the exposure to natural radiation sources is enhanced as a result to technological developments. Burning of coal is one source of enhanced radiation exposure to naturally occurring elements, particularly radium, thorium and uranium. Most of the radioactive substances are concentrated in the ash and slag, which are heavy and drop to the bottom of a furnace. Lighter fly ash is carried up the chimney and into the atmosphere. The bottom ash and slag are usually deposited in a waste pile, from where some activity may leach into aquifers or be dispersed by wind.The main pathways through which the populations living around coal fired power plants are exposed to enhanced levels of natural radionuclides are inhalation and ingestion of the activity discharged into the Exosphere. For this reason, extensive investigations have been under way for several years in the coal fired power plant in Croatia, which uses an anthracite coal with a higher than usual uranium content. (authors)

  15. Corrosion Investigations in Straw-Fired Power Plants in Denmark

    Montgomery, Melanie; Frandsen, Flemming; Karlsson, A


    of accelerated corrosion. The type of corrosion attack can be directly ascribed to the composition of the deposit and the metal surface temperature. A series of field tests have been undertaken in the various straw-fired power plants in Denmark, namely the Masnedø, Rudkøbing and Ensted CHP plants. Three types......In Denmark, straw and other types of biomass are used for generating energy in power plants. Straw has the advantage that it is a "carbon dioxide neutral fuel" and therefore environmentally acceptable. Straw combustion is associated with corrosion problems which are not encountered in coal-fired...... of exposure were undertaken to investigate corrosion: a) the exposure of metal rings on water/air cooled probes, b) the exposure of test tubes in a test superheater, and c) the exposure of test tubes in existing superheaters. Thus both austenitic steels and ferritic steels were exposed in the steam...

  16. Life cycle assessment of sewage sludge co-incineration in a coal-based power station.

    Hong, Jingmin; Xu, Changqing; Hong, Jinglan; Tan, Xianfeng; Chen, Wei


    A life cycle assessment was conducted to evaluate the environmental and economic effects of sewage sludge co-incineration in a coal-fired power plant. The general approach employed by a coal-fired power plant was also assessed as control. Sewage sludge co-incineration technology causes greater environmental burden than does coal-based energy production technology because of the additional electricity consumption and wastewater treatment required for the pretreatment of sewage sludge, direct emissions from sludge incineration, and incinerated ash disposal processes. However, sewage sludge co-incineration presents higher economic benefits because of electricity subsidies and the income generating potential of sludge. Environmental assessment results indicate that sewage sludge co-incineration is unsuitable for mitigating the increasing pressure brought on by sewage sludge pollution. Reducing the overall environmental effect of sludge co-incineration power stations necessitates increasing net coal consumption efficiency, incinerated ash reuse rate, dedust system efficiency, and sludge water content rate. Copyright © 2013 Elsevier Ltd. All rights reserved.

  17. Application of ORC power station to increase electric power of gas compression ignition engine

    Mocarski Szymon


    Full Text Available The paper presents the calculation results of efficiency of the subcritical low temperature ORC power station powered by waste heat resulting from the process of cooling a stationary compression ignition engine. The source of heat to supply the ORC power station is the heat in a form of water jet cooling the engine at a temperature of 92°C, and the exhaust gas stream at a temperature of 420°C. The study considers three variants of systems with the ORC power stations with different ways of using heat source. The first variant assumes using just engine cooling water to power the ORC station. In the second variant the ORC system is powered solely by a heat flux from the combustion gases by means of an intermediary medium - thermal oil, while the third variant provides the simultaneous management of both heat fluxes to heat the water stream as a source of power supply to the ORC station. The calculations were made for the eight working media belonging both to groups of so-called dry media (R218, R1234yf, R227ea and wet media (R32, R161, R152a, R134a, R22.

  18. The Ordered Capacitated Multi-Objective Location-Allocation Problem for Fire Stations Using Spatial Optimization

    Samira Bolouri


    Full Text Available Determining the positions of facilities, and allocating demands to them, is a vitally important problem. Location-allocation problems are optimization NP-hard procedures. This article evaluates the ordered capacitated multi-objective location-allocation problem for fire stations, using simulated annealing and a genetic algorithm, with goals such as minimizing the distance and time as well as maximizing the coverage. After tuning the parameters of the algorithms using sensitivity analysis, they were used separately to process data for Region 11, Tehran. The results showed that the genetic algorithm was more efficient than simulated annealing, and therefore, the genetic algorithm was used in later steps. Next, we increased the number of stations. Results showed that the model can successfully provide seven optimal locations and allocate high demands (280,000 to stations in a discrete space in a GIS, assuming that the stations’ capacities are known. Following this, we used a weighting program so that in each repetition, we could allot weights to each target randomly. Finally, by repeating the model over 10 independent executions, a set of solutions with the least sum and the highest number of non-dominated solutions was selected from among many non-dominated solutions as the best set of optimal solutions.

  19. Cooperating expert systems for space station power distribution management

    Nguyen, T.A.; Chiou, W.C.


    In a complex system such as the manned Space Station, it is deemed necessary that many expert systems must perform tasks in a concurrent and cooperative manner. An important question to arise is: what cooperative-task-performing models are appropriate for multiple expert systems to jointly perform tasks. The solution to this question will provide a crucial automation design criteria for the Space Station complex systems architecture. Based on a client/server model for performing tasks, the authors have developed a system that acts as a front-end to support loosely-coupled communications between expert systems running on multiple Symbolics machines. As an example, they use the two ART*-based expert systems to demonstrate the concept of parallel symbolic manipulation for power distribution management and dynamic load planner/scheduler in the simulated Space Station environment. This on-going work will also explore other cooperative-task-performing models as alternatives which can evaluate inter and intra expert system communication mechanisms. It will serve as a testbed and a bench-marking tool for other Space Station expert subsystem communication and information exchange

  20. Cooperating Expert Systems For Space Station Power Distribution Management

    Nguyen, T. A.; Chiou, W. C.


    In a complex system such as the manned Space Station, it is deem necessary that many expert systems must perform tasks in a concurrent and cooperative manner. An important question arise is: what cooperative-task-performing models are appropriate for multiple expert systems to jointly perform tasks. The solution to this question will provide a crucial automation design criteria for the Space Station complex systems architecture. Based on a client/server model for performing tasks, we have developed a system that acts as a front-end to support loosely-coupled communications between expert systems running on multiple Symbolics machines. As an example, we use two ART*-based expert systems to demonstrate the concept of parallel symbolic manipulation for power distribution management and dynamic load planner/scheduler in the simulated Space Station environment. This on-going work will also explore other cooperative-task-performing models as alternatives which can evaluate inter and intra expert system communication mechanisms. It will be served as a testbed and a bench-marking tool for other Space Station expert subsystem communication and information exchange.

  1. Comparison of the economy of atomic power stations and fossil-fuel power stations under Danish conditions

    Daub, J.


    The report deals with the investment and financing aspects of extending the Danish electricity production system with central, base-load power stations. Technical and economic data for the plants are determined on the basis of an analysis of the information presently available. A description is given of the general problems connected with analysis of investment and finance relevant to power station expansion. Comparative calculations are given for alternative methods of expansion comprising a few stations to be put into operation in 1987 and for other alternative expansions that cover the period until 2000 as regards costs. For use in economic comparisons with a few plants, a new calculation method was developed that takes into account possible differences in the value of the plants in the electricity production system. This method is described in appendix 1. In a further two appendices are given the technical reasons for using, respectively, the present-value method in the investment analyses and the reserve power philosophy applied in the main report. (author)

  2. Papers of 6. Scientific-Technical Seminar Material Study for Electric Power Stations and Energetics


    The report is an assembly of the papers concerning the material problems occurring during the exploitation of power station. The normalization problems in power station and gas pipelines according to the prescription of UE are also discussed. (author)

  3. Water electrolysis plants for hydrogen and oxygen production. Shipped to Tsuruga Power Station Unit No.1, and Tokai No.2 power station, the Japan Atomic Power Co

    Ueno, Syuichi; Sato, Takao; Ishikawa, Nobuhide


    Ebara's water electrolysis plants have been shipped to Tsuruga Power Station Unit No.1, (H 2 generation rate: 11 Nm 3 /h), and Tokai No.2 Power Station (H 2 generation rate: 36 Nm 3 /h), Japan Atomic Power Co. An outcome of a business agreement between Nissho Iwai Corporation and Norsk Hydro Electrolysers (Norway), this was the first time that such water electrolysis plants were equipped in Japanese boiling water reactor power stations. Each plant included an electrolyser (for generating hydrogen and oxygen), an electric power supply, a gas compression system, a dehumidifier system, an instrumentation and control system, and an auxiliary system. The plant has been operating almost continuously, with excellent feedback, since March 1997. (author)

  4. Development of heavy load carrying vehicle for nuclear power station

    Terabayashi, Yasuharu; Oono, Hiroo; Aizu, Takao; Kawaguchi, Kaname; Yamanaka, Masayuki; Hirobe, Tamio; Inagaki, Yoshiaki.


    In nuclear power stations, in order to carry out sound and stable operation, the routine inspection and regular inspection of machinery and equipment are performed, therefore, the transportation of heavy things is frequently carried out. Especially, the transportation of heavy things over the steps of passages and stairs requires much labor. Therefore, Chubu Electric Power Co., Inc. and Chubu Plant Service Co., Ltd. carried out the research on the development of a vehicle for transporting heavy components of nuclear power plants. In this research, it was aimed at developing a vehicle which can carry heavy components and get over a step, climb and descend stairs, and run through a narrow passage having many curves as well as running on flat ground. For this purpose, the actual state of the transportation of heavy things was investigated during the regular inspection of a nuclear power station, and on the basis of this results, a prototype vehicle was made and tested. Thereafter, a transporting vehicle of actual scale was made and tested. The investigation of actual state and the examination of the fundamental concept, the design, trial manufacture and verifying test are reported. (Kako, I.)

  5. Station power supply by residual steam of Fugen

    Kamiya, Y.; Kato, H.; Hattori, S. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))


    In the advanced thermal reactor ''Fugen'', when the sudden decrease of load more than 40% occurs due to the failure of power system, the turbine regulating valve is rapidly shut, and the reactor is brought to scrum. However, the operation of turbo-generators is continued with the residual steam in the reactor, and the power for inside the station is supplied for 30 sec by the limiting timer, then the power-generating plant is automatically stopped. The reasons why such design was adopted are to reduce manual operation at the time of emergency, to continue water supply for cooling the reactor and to maintain the water level in the steam drum, and to reduce steam release from the safety valve and the turbine bypass valve. The output-load unbalance relay prevents the everspeed of the turbo-generator when load decreased suddenly, but when the failure of power system is such that recovers automatically in course of time, it does not work. The calculation for estimating the dynamic characteristics at the time of the sole operation within the station is carried out by the analysis code FATRAC. The input conditions for the calculation and the results are reported. Also the dynamic characteristics were actually tested to confirm the set value of the limiting timer and the safe working of turbine and generator trips. The estimated and tested results were almost in agreement.

  6. Literature study regarding fire protection in nuclear power plants. Part 2: Fire detection and -extinguishing systems

    Isaksson, S.


    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Detection and extinguishing systems in Swedish nuclear power plants have only to a limited extent been designed after functional demands, such as a maximum acceptable damage or a maximum time to detect a fire. The availability of detection systems is difficult to assess, partly because of lack of statistics. The user interface is very important in complex systems as nuclear plants. An extinguishing system designed according to the insurance companies' regulations will only fulfill the basic demands. It should be noted that normal sprinkler design does not aim for extinguishing fires, the objective is to control fire until manual extinguishment is possible. There is a great amount of statistics on wet and dry pipe sprinkler systems, while statistics are more scarce for deluge systems. The statistics on the reliability of gaseous extinguishing systems have been found very scarce. A drawback of these systems is that they are normally designed for one shot only. There are both traditional and more recent extinguishing systems that can replace halons. From now on there will be a greater need for a thorough examination of the properties needed for the individual application and a quantification of the acceptable damage. There are several indications on the importance of a high quality maintenance program as well as carefully developed routines for testing and surveillance to ensure the reliability of detection and extinguishing systems. 78 refs, 8 figs, 10 tabs

  7. The economic feasibility of renewable powered fast charging stations

    Benger, Ralf; Heyne, Raoul; Wenzl, Heinz; Beck, Hans-Peter


    Electric vehicles will make an important contribution for a sustainable energy supply in the public transport sector. Although it is not sure at the moment which role the different vehicle concepts and charging options will play, it is possible to act on following assumptions: There will be purely electrically operated vehicles (EV), which will need a charging infrastructure in the public domain. Even if the number of these vehicles in comparison with hybrid electric vehicles (HEV) or range extended electric vehicles (REV) will be low, in the long run an amount of some million vehicles can be reached (1 0 % of the vehicles in Germany corresponds to round about 4 million vehicles). Charging stations in parking areas, shopping malls, at home or at work do not require high charging power because the time available for charging is relative long. In contrast charging stations beside these in normal parking areas should have the ability to charge the car batteries in a very short time, e.g. 80% of the energy content in 15 minutes or less. Therefore every charging process requires 100-200 kW electric power. Such charging stations are necessary both in rural and in urban regions.

  8. Solid radwaste characterization at surry and North Anna Power Stations

    Lippard, D.W.


    This paper describes a characterization of the solid radwaste generated at Virginia Power's North Anna and Surry power stations. The primary focus of this characterization was dry active waste (DAW). The characterization, covering the 21-month period from January 1985 through September 1986, was based on information in the station's health physics procurement records, radwaste shipping records, and from interviews with station personnel. The procurement records were the principal source of information for DAW. They were reviewed to determine the quantities of various materials, purchased during the study period, that were expected to become DAW. This provides an upper limit on the quantity in the waste for several major DAW components and a basis for the total amount of other components in the waste. The approach to characterizing DAW discussed in this paper could be implemented and regularly updated by utilizing a computerized procurement records system. If a use code (i.e., contaminated or noncontaminated) is associated with each stock requisition, a characterization could be performed by a computer run. This approach would help track minimization effort effectiveness and would refine the characterization of DAW considerably

  9. Contamination awareness at the Dresden Nuclear Power Station

    Pagel, D.J.; Rath, W.C.


    Dresden Nuclear Power Station, which is located ∼ 60 miles southwest of Chicago near Morris, Illinois, has been generating electricity since 1960. Owned by Commonwealth Edison, Dresden was the nation's first privately financed nuclear station. On its site are three boiling water reactors (BWRs). Due to the contamination potential inherent with a reactor, a contamination trending program was created at the station. Studies had indicated a rise in contamination events during refueling outages. Further increases were due to specific work projects such as hydrolyzing operations. The investigations suggested that contract personnel also increased the number of events. In 1983, a contamination awareness program was created. The 1984 contamination awareness program was comprised of the following: (1) a statistical review in which trended contamination events were discussed. (2) A demonstration of protective clothing removal by an individual making various mistakes. (3) Scenarios were developed for use in mock work areas. (4) Upper management involvement. Because of the 1984 program, favorable attention has been focused on Dresden from the US Nuclear Regulatory Commission and the Institute of Nuclear Power Operations

  10. Review of fire behavior during passage of Sandy Lake Fire 13 (NWT) across a Northwest Territories Power Corporation transmission line

    Schroeder, D.; Thomasson, J.


    The Sandy Lake Fire 13 of July 2008 was an intense forest fire that burned up to and across a power line right-of-way in the Northwest Territories, approximately 160 km northwest of Fort Smith. The terrain in the area is flat and vegetation is characterized by boreal pine and black spruce uplands with black spruce and tamarack in lower areas and adjacent to wetlands. This report documented post fire conditions at locations where the fire crossed the power line. The towers on this line were made from an aluminum alloy and may not have had the same resistance to heat damage as steel towers, more commonly used on major transmission lines. The transmission line was de-energized during the fire. Therefore, the effects of fire on power transmission were not documented. Although the intense wildfire crossed sections of the power line, it did not result in observable damage to the towers or lines. Fire intensity was likely greater than 40,000 kw/m along some sections of the right-of-way. Although the management of the right-of-way may have reduced heat exposure to the transmission towers, it did not stop the fire. Pine mixed with an aspen component greater than 50 per cent had a mitigating effect on fire behaviour. The fire did not result in any immediate damage to the power line infrastructure. It was concluded that the use of power lines for fire operations should consider right-of-way width in order to assess equipment maneuverability, especially around tower guy wires. 5 refs., 1 tab., 12 figs.

  11. Contribution to nuclear power stations to environment conservation (EDF experience)

    Astolfi, J.F.


    It is a world scale opinion now, that industrial activities, such as power generation, and energy use which still heavily rely on fossil fuels, are disproportionately instrumental in affecting our environment, and changing earth's physical conditions. For example, sulphur and nitrogen oxides, generated by coal and oil combustion, which can be harmful for our health, are also supposed to induce acid rains which damage our lakes and forests. Carbon dioxide emissions, which are unavoidable in most of combustion facilities, are acknowledged as instrumental in the open-quotes greenhouse effectclose quotes, which is supposed to bring about significant changes in the climate during forthcoming centuries. Facing such problems, severe regulations are now issued in most of industralized countries, mainly in the EEC, the aim of which is to reduce drastically pollutant discharge to the atmosphere. They obviously apply to power plants and as a consequence, utilities which operate fossil-fired units, will be prompted in the next future, to carry out sophisticated and expensive technical solutions to limitate pollutant emission to an acceptable level. In this respect, clean combustion technologies, such as fluidized beds, pollutant abatement systems such as flue gas desulphurization or denoxification, or even natural gas-fired plants like combined cycles, shall be designed and implemented, which will unavoidably increase the cost of power generation without totally solving the problem. In such a context, EDF opinion is that safe operation of nuclear power plants can make a substantial contribution in reducing pollution of the atmosphere, and this is highlighted by the example of the French nuclear program

  12. The local economic and social effects of power station siting: anticipated, demonstrated and perceived

    Glasson, J.


    The paper discusses the economic and social effects of power station siting at a local level using material based on the interim research findings from a project commissioned by the Central Electricity Generating Board. The cases for and against power station development are outlined and a review of the actual economic and social effects is presented, drawn from a study of a conventional power station at Drax and a nuclear power station at Sizewell. (U.K.)

  13. Prediction of SO{sub 2} pollution incidents near a power station using partially linear models and an historical matrix of predictor-response vectors

    Prada-Sanchez, J.M.; Febrero-Bande, M.; Gonzalez-Manteiga, W. [Universidad de Santiago de Compostela, Dept. de Estadistica e Investigacion Operativa, Santiago de Compostela (Spain); Costos-Yanez, T. [Universidad de Vigo, Dept. de Estadistica e Investigacion Operativa, Orense (Spain); Bermudez-Cela, J.L.; Lucas-Dominguez, T. [Laboratorio, Central Termica de As Pontes, La Coruna (Spain)


    Atmospheric SO{sub 2} concentrations at sampling stations near the fossil fuel fired power station at As Pontes (La Coruna, Spain) were predicted using a model for the corresponding time series consisting of a self-explicative term and a linear combination of exogenous variables. In a supplementary simulation study, models of this kind behaved better than the corresponding pure self-explicative or pure linear regression models. (Author)

  14. Prediction of SO2 pollution incidents near a power station using partially linear models and an historical matrix of predictor-response vectors

    Prada-Sanchez, J.M.; Febrero-Bande, M.; Gonzalez-Manteiga, W.; Costos-Yanez, T.; Bermudez-Cela, J.L.; Lucas-Dominguez, T.


    Atmospheric SO 2 concentrations at sampling stations near the fossil fuel fired power station at As Pontes (La Coruna, Spain) were predicted using a model for the corresponding time series consisting of a self-explicative term and a linear combination of exogenous variables. In a supplementary simulation study, models of this kind behaved better than the corresponding pure self-explicative or pure linear regression models. (Author)

  15. Report on the accident at the Chernobyl Nuclear Power Station


    This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. The various authors are identified in a footnote to each chapter. An overview of the report is provided. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general

  16. Operational results in the Onagawa Nuclear Power Station

    Hasegawa, Kanichi; Kato, Katsuya; Terada, Hideo; Kamata, Takakage; Kaimura, Yoshiharu


    In the Onagawa Nuclear Power Station, Unit 1 (BWR type, with electric output 524 MW) started operation in June 1, 1984. The power plant has then continued non-stop operation up to April 2, 1985, thus exhibiting its base load plant. In fiscal 1984, the continuous operation is for 342 days; the capacity factor is about 96.1 %, which is the world's top. During the period, the radioactivity releases to the environment in both liquid and gaseous wastes are below the detection limits. The collective exposure dose for plant personnel is merely 6 man-rem. Subsequently, its 1st periodical inspection was started on April 3, 1985, and finished in July the same year. So, the power plant is now again in operation. (Mori, K.)

  17. 77 FR 10576 - Methodology for Low Power/Shutdown Fire PRA


    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0295] Methodology for Low Power/Shutdown Fire PRA AGENCY.../Shutdown Fire PRA.'' In response to request from members of the public, the NRC is extending the public... risk assessment (PRA) method for quantitatively analyzing fire risk in commercial nuclear power plants...

  18. Monitoring of the operation of a nuclear power station with design problems in an importing country: The Almaraz power station

    Reig, J.


    The purpose of this paper is to describe the regulatory activities carried out in Spain as a result of the design problem occurring in the steam generators during operation of Unit I of the Almaraz nuclear power station. First, a brief introduction is given to the operating history and characteristics of Unit I of Almaraz. Particular attention is paid to the specific licences issued subsequent to commercial operation which place limitations on the operation of the station and to the operational incidents of which the Nuclear Safety Council (CSN) has been notified. Next, a description is provided of the safety evaluation carried out by the CSN. Three aspects merit particular attention: methodology, evaluation and conclusions. The methodology applied by an importing country is normally based on that of the country of origin of the design, so that the overall evaluation by the NRC has been considered sufficiently representative of aspects specific to the Almaraz power station. In this regard the importance of international collaboration is clearly seen as a principal instrument for performing the evaluation. In the evaluation a distinction is made between general and specific aspects and between inspection programmes and quality assurance requirements. In addition, the conclusions leading to the requirement of the imposition of additional limitations on the operating licence are stated. Apart from the safety evaluation carried out by the CSN, other regulatory activities have been performed over this two-year period. These activities, which include site inspections, audits of the principal supplier company, other independent calculations and so on, are described. Lastly, the paper refers to the lessons learned from the operation of the above-mentioned unit, which are immediately applicable to other Spanish nuclear power stations. (author)

  19. Coal-fired high performance power generating system. Final report



    As a result of the investigations carried out during Phase 1 of the Engineering Development of Coal-Fired High-Performance Power Generation Systems (Combustion 2000), the UTRC-led Combustion 2000 Team is recommending the development of an advanced high performance power generation system (HIPPS) whose high efficiency and minimal pollutant emissions will enable the US to use its abundant coal resources to satisfy current and future demand for electric power. The high efficiency of the power plant, which is the key to minimizing the environmental impact of coal, can only be achieved using a modern gas turbine system. Minimization of emissions can be achieved by combustor design, and advanced air pollution control devices. The commercial plant design described herein is a combined cycle using either a frame-type gas turbine or an intercooled aeroderivative with clean air as the working fluid. The air is heated by a coal-fired high temperature advanced furnace (HITAF). The best performance from the cycle is achieved by using a modern aeroderivative gas turbine, such as the intercooled FT4000. A simplified schematic is shown. In the UTRC HIPPS, the conversion efficiency for the heavy frame gas turbine version will be 47.4% (HHV) compared to the approximately 35% that is achieved in conventional coal-fired plants. This cycle is based on a gas turbine operating at turbine inlet temperatures approaching 2,500 F. Using an aeroderivative type gas turbine, efficiencies of over 49% could be realized in advanced cycle configuration (Humid Air Turbine, or HAT). Performance of these power plants is given in a table.

  20. Introduction of Integrity Evaluation Criteria Developing during and after fire for Nuclear Power Plant Buildings

    Lee, Jin Woo


    The first project for nuclear power plant built in Korea to taking account the engineering based approach was started on October 2015 including the whole process such as fire hazard analysis, standard fire modeling, cable tray fire with multi spurious operation, structural fire integrity evaluation, and large area fire induced air craft crash. This paper covers the brief developing scheme and roadmap focusing on structural fire evaluation criteria. The meaningful first step for developing the structural fire integrity in nuclear power plant building is started with the series of fire related sub sections mentioned in earlier section. The recognition and sufficient effort of fire research leads to set up the safe and reliable design of nuclear power plant