Savannah River Plant airborne emissions and controls

International Nuclear Information System (INIS)

Dukes, E.K.; Benjamin, R.W.

1982-12-01

The Savannah River Plant (SRP) was established to produce special nuclear materials, principally plutonium and tritium, for national defense needs. Major operating facilities include three nuclear reactors, two chemical separations plants, a fuel and target fabrication plant, and a heavy-water rework plant. An extensive environmental surveillance program has been maintained continuously since 1951 (before SRP startup) to determine the concentrations of radionuclides in a 1200-square-mile area centered on the plant, and the radiation exposure of the population resulting from SRP operations. This report provides data on SRP emissions, controls systems, and airborne radioactive releases. The report includes descriptions of current measurement technology. 10 references, 14 figures, 9 tables

Probabilistic evaluation of risks associated with aviation, road, railway and river traffic adjacent to nuclear power plants in France

International Nuclear Information System (INIS)

Procaccia, H.; Gobert, T.

1978-01-01

Electricite de France has developed a methodology to calculate the potential impact of risks to a nuclear power plant subsequent to an accident occurring on transportation networks in the vicinity of a nuclear site. Risks entailed in aviation, and in road, rail, and river traffic have been estimated. This methodology has been applied to all sites planned in France

Monitoring and assessment of radionuclide discharges from Temelín Nuclear Power Plant into the Vltava River (Czech Republic).

Science.gov (United States)

Hanslík, Eduard; Ivanovová, Diana; Juranová, Eva; Simonek, Pavel; Jedináková-Krízová, Vĕra

2009-02-01

The paper summarizes impacts of the Temelín Nuclear Power Plant (NPP) on the Vltava and Labe River basins. The study is based on the results of long-term monitoring carried out before the plant operation (1989-2000), and subsequently during the plant operation (2001-2005). In the first period, the main objective was to determine background radionuclide levels remaining in the environment after global fallout and due to the Chernobyl accident. A decrease in the concentrations of (90)Sr, (134)Cs and (137)Cs, which was observed before the plant operation, continued also during the subsequent period. Apart from tritium, the results of the observation did not indicate any impacts of the plant on the concentrations of activation and fission products in the hydrosphere. The annual average tritium concentrations in the Vltava River were in agreement with predicted values. The maximum annual average tritium concentration (13.5 Bq L(-1)) was observed in 2004 downstream from the wastewater discharge in the Vltava River at Solenice. Estimated radiation doses for adults due to intakes of river water as drinking water contaminated by tritium are below 0.1 microSv y(-1).

Application of probabilistic risk assessment to nuclear fuel reprocessing at the Savannah River Plant

International Nuclear Information System (INIS)

Durant, W.S.

1980-01-01

The Savannah River Laboratory has developed an integrated risk assessment methodology that has been applied to systems in the nuclear fuel reprocessing facilities at the Savannah River Plant. The methodology can be applied to several types of design and operational problems. Basically, the analysis is subdivided into individual modules that can be either utilized separately or integrated into an overall risk analysis. Computer codes and computer data banks are utilized extensively to minimize the manual effort. The flow of information begins with a definition of the system to be analyzed followed by an evaluation of sources of fault information, storage of this information in data banks, design analysis and data treatment, risk calculations, and end product options

Expert robots in nuclear plants

International Nuclear Information System (INIS)

Byrd, J.S.; Fisher, J.J.; DeVries, K.R.; Martin, T.P.

1987-01-01

Expert robots enhance a safety and operations in nuclear plants. E.I. du Pont de Nemours and Company, Savannah River Laboratory, is developing expert mobile robots for deployment in nuclear applications at the Savannah River Plant. Knowledge-based expert systems are being evaluated to simplify operator control, to assist in navigation and manipulation functions, and to analyze sensory information. Development work using two research vehicles is underway to demonstrate semiautonomous, intelligence, expert robot system operation in process areas. A description of the mechanical equipment, control systems, and operating modes is presented, including the integration of onboard sensors. A control hierarchy that uses modest computational methods is being used to allow mobile robots to autonomously navigate and perform tasks in known environments without the need for large computer systems

Expert robots in nuclear plants

International Nuclear Information System (INIS)

Byrd, J.S.; Fisher, J.J.; DeVries, K.R.; Martin, T.P.

1987-01-01

Expert robots will enhance safety and operations in nuclear plants. E. I. du Pont de Nemours and Company, Savannah River Laboratory, is developing expert mobile robots for deployment in nuclear applications at the Savannah River Plant. Knowledge-based expert systems are being evaluated to simplify operator control, to assist in navigation and manipulation functions, and to analyze sensory information. Development work using two research vehicles is underway to demonstrate semiautonomous, intelligent, expert robot system operation in process areas. A description of the mechanical equipment, control systems, and operating modes is presented, including the integration of onboard sensors. A control hierarchy that uses modest computational methods is being used to allow mobile robots to autonomously navigate and perform tasks in known environments without the need for large computer systems

Thermal pollution of rivers and reservoirs by discharges of heated water from thermal and nuclear power plants

International Nuclear Information System (INIS)

Makarov, I.

1974-12-01

The problems are discussed of the thermal pollution of rivers and water reservoirs by discharges of heated water from thermal and nuclear power plants. The problems concerned are quantitative and qualitative changes in biocenoses, the disturbance or extinction of flora and fauna, physiological changes in organisms and changes in the hydrochemical regime. (Z.M.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-09-20

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

Remote sensing of wetlands at the Savannah River Plant

International Nuclear Information System (INIS)

Christensen, E.J.; Jensen, J.R.; Sharitz, R.R.

1985-01-01

The Savannah River Plant (SRP) occupies about 300 sq mi along a 10-mile stretch of the Savannah River. Large areas of wetlands cover the site, especially along tributary stream floodplains and the Savannah River. Some of these areas have been altered by cooling water discharges from nuclear production reactors onsite. To assess the effects of current and future plant operations on SRP and regional wetlands, an accurate quantitative survey was needed. Several studies were initiated to provide wetland acreage and distribution information: regional wetland inventories were provided from an analysis of LANDSAT multispectral scanner (MSS) satellite data. Wetlands were mapped throughout the entire Savannah River watershed and in the Savannah River floodplain. SRP wetlands were identified using a combination of LANDSAT MSS and Thematic Mapper satellite data and aerial photography. Wetlands in the SRP Savannah River swamp and thermally affected areas were mapped using high resolution MSS data collected from a low-flying aircraft. Vegetation communities in areas receiving cooling water discharges were then compared to surface temperatures measured from the airborne scanner at the same time to evaluate plant temperature tolerance. Historic changes to SRP wetlands from cooling water discharges were tabulated using aerial photography

Savannah River Plant/Savannah River Laboratory radiation exposure report

International Nuclear Information System (INIS)

Rogers, C.D.; Hyman, S.D.; Keisler, L.L.; Reeder, D.F.; Jolly, L.; Spoerner, M.T.; Schramm, G.R.

1989-01-01

The protection of worker health and safety is of paramount concern at the Savannah River Site. Since the site is one of the largest nuclear sites in the nation, radiation safety is a key element in the protection program. This report is a compendium of the results in 1988 of the programs at the Savannah River Plant and the Savannah River Laboratory to protect the radiological health of employees. By any measure, the radiation protection performance at this site in 1988 was the best since the beginning of operations. This accomplishment was made possible by the commitment and support at all levels of the organizations to reduce radiation exposures to ALARA (As Low As Reasonably Achievable). The report provides detailed information about the radiation doses received by departments and work groups within these organizations. It also includes exposure data for recent years to allow Plant and Laboratory units to track the effectiveness of their ALARA efforts. Many of the successful practices and methods that reduced radiation exposure are described. A new goal for personnel contamination cases has been established for 1989. Only through continual and innovative efforts to minimize exposures can the goals be met. The radiation protection goals for 1989 and previous years are included in the report. 27 figs., 58 tabs

Study of the long-range effects of radioactive effluents from nuclear power plants in the Rhine river using 58Co and 60Co as tracers

International Nuclear Information System (INIS)

Mundschenk, H.

1992-01-01

58 Co and 60 Co were used to trace the long-range effects of nuclear power plants in the aquatic environment of the Rhine river basin. 60 Co, preferentially originating from Swiss installations, could be detected in suspended matter along the river over several hundreds of kilometres, even to the Lower Rhine. This nuclide was transferred to the bottom layer by sedimentation along the whole stretch, especially in high-sedimentation zones, which must be considered to be the so-called 'critical impact areas' for estimation of the radiological effects of the nuclear power plants in the aquatic environment. 58 Co, mainly discharged by French and Swiss installations, could be measured in suspended matter. In sediment samples, however, this nuclide could not, or only occasionally, be detected because transfer to the sediment layer proceeded at a rather low rate relative to the decay rate of 58 Co. From these findings, it follows that impact control of these nuclear power plants should not be restricted to their immediate aquatic environments but should be extended to the whole river. Estimation of the resulting radiation exposure, based on the measured concentrations of 60 Co and 58 Co in sediment assuming standard conditions, showed that the dose rates generated by the most sensitive pathway, and indeed by other nuclides and different pathways, were far below the dose limit defined in German legal regulations and therefore were negligible. (author)

Contribution to evaluating nuclear power plant accidents

International Nuclear Information System (INIS)

Razga, J.; Horacek, P.

1990-01-01

Large-scale accidents pose the highest risk in the use of nuclear power. They are the major factor that has to be taken into account when assessing the effect of nuclear power plants on human health and on the environment. In Czechoslovak conditions, the effectiveness of provisions made to reduce the hazard of large-scale nuclear power plant accidents must be considered from the following aspects: effect on human health, consequences of long-term disabling of the infrastructure, potential of human and material reserves in coping with the accident, consequences of power failure for the electricity system, effect on agricultural production and catering, risk of ground and surface water contamination in the Labe or Danube river basin, and international political aspects. (Z.M.). 3 tabs., 18 refs

Experience with ALARA and ALARA procedures in a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Abrahamse, J.C. [N.V. Elektriciteits-Produktiemaatschappij Zuid-Nederland (Netherlands)

1995-03-01

The nuclear power plant Borssele is a Siemens two-loop Pressurized Water Reactor having a capacity of 480 MWe and in operation since 1973. The nuclear power plant Borssle is located in the southwest of the Netherlands, near the Westerschelde River. In the first nine years of operation the radiation level in the primary system increased, reaching a maximum in 1983. The most important reason for this high radiation level was the cobalt content of the grid assemblies of the fuel elements. After resolving this problem, the radiation level decreased to a level comparable with that of other nuclear power plants.

Remote sensing analysis of thermal plumes at the Savannah River Plant

International Nuclear Information System (INIS)

Doak, E.L.

1985-01-01

The nuclear reactors of the Savannah River Plant (SRP) in Aiken, South Carolina, use cold water diverted from the Savannah River to dissipate unused thermal energy. This water is heated by heat exchangers of the reactors during the materials production process, and then returned to the natural drainage system. Thermal effluents were monitored by an airborne thermal infrared scanner during predawn overlights. Images were generated to show the surface temperature distribution of the thermal outfall plumes into the Savannah River. The thermal analysis provides information related to compliance with permit requirements of the regulatory agencies

Macrophytes control on a stretch of the Ebro River flowing through the Asco Nuclear Power Plant; Control de macrofitos en un tramo del rio Ebro a su paso por la Central Nuclear Asco

Energy Technology Data Exchange (ETDEWEB)

Munte Clua, L.; Fernandez Alentorn, E.; Beltran Grau, A.

2010-07-01

The objective of this paper is to evaluate the time evolution of the different macrophytes populations in the stretch of the Ebro River between the town of Flix and the Asco Nuclear Power Plant, and the effects observed by the programmed flood for their control.

Directory of nuclear power plants in the world, 1985

International Nuclear Information System (INIS)

Fujii, Haruo

1985-01-01

This book presents technical information and estimates trends of load factors and construction costs of nuclear power plants. Particularly road maps indicating plants are drawn in, which would be practical in visiting them. The data used here are directly confirmed by operators in every part of the world. Therefore, they reflect up-to-date nuclear power developments and its future. This allows wide and exact understanding of world's nuclear power. Chapter 1 presents nuclear power growth around the world and estimates forecasts based on information from electric power companies: nuclear power growths and the growths in the number of reactors around the world, in WOCA (World outside the Centrally Planned Economies Area), in CPEA (Centrally Planned Economies Area) are analyzed in detail. Chapter 2 presents nuclear power plants on maps by country. The maps show exact locations of nuclear power plants with local cities around them, rivers and lakes. For convenience, symbols are given to aid in identifying the types of reactors. Chapter 3 presents general information of nuclear power plants. Also the addresses of operators, all segments of nuclear power supply industries and nuclear organizations are included. For convenience, the index of nuclear power plants is added. Chapter 4 presents technical information, road maps in large scales and photographs of nuclear power plants in the world. The road maps show exact locations of plants. Chapter 5 presents operating experiences, load factors, refuelling and maintenance outages. The trends of data are analyzed both regionally (WOCA, CPEA) and world-widely. Chapter 6 presents trends of construction costs, component costs as percent of total construction costs and direct costs, and construction durations. (J.P.N.)

Nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

Radioecological monitoring of the Tom' river ecosystem within zone of nuclear fuel cycle plants influence

International Nuclear Information System (INIS)

Leonova, G.A.; Bobrov, V.A.; Malikov, Yu.I.; Mel'gunov, M.S.; Makarova, I.V.; Toropov, A.V.

2005-01-01

According to the results of 2000-2002 expeditions the estimation of radioactive contamination scales in water ecosystems within zone of Siberian Chemical Industrial Complex (SCC) influence was performed. The accumulation levels of short-lived artificial radionuclides in biota components of SCC technological channel (Romashka river), and spatial radionuclide distribution in biota of ecosystem of the Tom' and Ob' rivers at different distances from the local source have been determined using biochemical indication method. The most frequently occurring species of plants, filamentous green algae and fish were selected as indicator bioobjects for the monitoring. In spectrum of radioisotopes revealed in water plants, fish and water of the Romashka river there were determined twelve short-living isotopes that denoted continuing river burial. (author)

Hydrogeological modelling of the eastern region of Areco river locally detailed on Atucha I and II nuclear power plants area

International Nuclear Information System (INIS)

Grattone, Natalia I.; Fuentes, Nestor O.

2009-01-01

Water flow behaviour of Pampeano aquifer was modeled using Visual Mod-flow software Package 2.8.1 with the assumption of a free aquifer, within the region of the Areco river and extending to the rivers of 'Canada Honda' and 'de la Cruz'. Steady state regime was simulated and grid refinement allows obtaining locally detailed calculation in the area of Atucha I and II Nuclear power plants, in order to compute unsteady situations as the consequence of water flow variations from and to the aquifer, enabling the model to study the movement of possible contaminant particles in the hydrogeologic system. In this work the effects of rivers action, the recharge conditions and the flow lines are analyzed, taking always into account the range of reliability of obtained results, considering the incidence of uncertainties introduced by data input system, the estimates and interpolation of parameters used. (author)

Ecology of Legionella within water cooling circuits of nuclear power plants along the French Loire River

International Nuclear Information System (INIS)

Jakubek, Delphine

2012-01-01

The cooling circuits of nuclear power plants, by their mode of operating, can select thermophilic microorganisms including the pathogenic organism Legionella pneumophila. To control the development of this genus, a disinfection treatment of water cooling systems with monochloramine can be used. To participate in the management of health and environmental risks associated with the physico-chemical and microbiological modification of water collected from the river, EDF is committed to a process of increasing knowledge about the ecology of Legionella in cooling circuits and its links with its environment (physical, chemical and microbiological) supporting or not their proliferation. Thus, diversity and dynamics of culturable Legionella pneumophila were determined in the four nuclear power plants along the Loire for a year and their links with physico-chemical and microbiological parameters were studied. This study revealed a high diversity of Legionella pneumophila subpopulations and their dynamic seems to be related to the evolution of a small number of subpopulations. Legionella subpopulations seem to maintain strain-specific relationships with biotic parameters and present different sensitivities to physico-chemical variations. The design of cooling circuits could impact the Legionella community. The use of monochloramine severely disrupts the ecosystem but does not select biocide tolerant subpopulations. (author)

Environmental monitoring in the vicinity of the Savannah River Plant. Annual report, 1977

International Nuclear Information System (INIS)

1977-01-01

The concentration of radioactivity added by the Savannah River Plant operations to the environs during 1977 was, for the most part, too small to be distinguished from natural background radiation and fallout from worldwide nuclear weapon tests. Beta activity in particulate air filters was about two times the 1976 level and was due entirely to global fallout. Tritium oxide in air at the plant perimeter was greater than in air at more distant locations; the average concentration at the plant perimeter (65 pCi/m 3 ) was 0.03% of the Concentration Guide (CG). Tritium, 137 Cs, and 90 Sr were the only radionuclides of plant origin detectable in Savannah River water by routine analyses. None of these had an average concentration exceeding 0.2% of the CG in river water sampled 8 mi downstream from the plant. The tritium concentration in river water immediately downstream of the plant (4.8 pCi/ml, including 0.5 pCi/ml background river contribution) represented the highest CG percentage (0.16) of the three radionuclides measured in river water. Special research programs using ultra-low-level techniques may detect trace quantities of other radionuclides of plant origin. Radioactive materials in river fish also continued very low (0.2 pCi/g 137 Cs maximum). Annual analyses of plant perimeter soil samples 0-5 cm deep) showed deposition of 137 Cs (52 mCi/km 2 ) and 239 Pu (1.2 mCi/km 2 ) within the range normally found in global fallout. 238 Pu in all soil samples was near the sensitivity of the analysis (approximately 0.1 mCi/km 2 ). For 1977, the calculated annual average dose from atmospheric releases of radioactive materials from SRP was 0.8 millirem (mrem) at the plant perimeter

Geomorphologic specificities of selected sites for nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Kalvoda, J.; Demek, J.

1991-01-01

The contribution of geomorphology to the complex evaluation of properties of sites for the construction and operation of nuclear facilities is demonstrated. The unique manifestation of the present geodynamics at the Jaslovske Bohunice nuclear power plant locality and the spatial correlations of annals of the specific morphotectonic development of georeliefs of that nuclear power plant with the location of the epicentral earthquake zones are shown. The results of the geomorphological survey in the surroundings of the Temelin nuclear power plant construction site are described and a drawing is reproduced showing how the georelief of this locality divides into areas with different categories of occurrence of morpho-structural formations. For the Tetov locality, where the construction of a nuclear power plant is planned, the changes in the course of the Labe (Elbe) river which occurred in the Pleistocene are of importance in the assessment of the intensity of geodynamic processes. The geomorphological and geotectonic complexity of the planned Blahutovice nuclear power plant construction site is demonstrated. A drawing shows the morphotectonic situation in the surroundings of that construction site. (Z.S.). 4 figs

Savannah River Plant environment

International Nuclear Information System (INIS)

Dukes, E.K.

1984-03-01

On June 20, 1972, the Atomic Energy Commission designated 192,323 acres of land near Aiken, SC, as the nation's first National Environmental Research Park. The designated land surrounds the Department of Energy's Savannah River Plant production complex. The site, which borders the Savannah River for 17 miles, includes swampland, pine forests, abandoned town sites, a large man-made lake for cooling water impoundment, fields, streams, and watersheds. This report is a description of the geological, hydrological, meteorological, and biological characteristics of the Savannah River Plant site and is intended as a source of information for those interested in environmental research at the site. 165 references, 68 figures, 52 tables

Ecological investigation of Hudson River macrozooplankton in the vicinity of a nuclear power plant

International Nuclear Information System (INIS)

Ginn, T.C.

1977-01-01

Studies were conducted on selected Hudson River macrozooplankton species to determine temporal and spatial distributions and responses to power plant operation. Distinguishing morphological and habitat characteristics were determined for the three gammarid amphipods (Gammarus daiberi, G. tigrinus, and G. fasciatus) occurring in the Hudson River. The oedicerotid amphipod Monoculodes edwardsi and the mysid Neomysis americana, in addition to the gammarid amphipods, displayed characteristic diel and seasonal abundances which affect their potential availability for power plant entrainment. The selected macrozooplankton species were utilized in temperature and chlorine bioassays in order to predict responses to cooling water entrainment. Although amphipods (Gammarus spp. and M. edwardsi) survived typical Indian Point cooling water temperatures, N. americana had high mortalities during a 30-minute, 8.3 0 C ΔT at 25 0 C ambient temperature. The bioassay results were substantiated by generally high survivals of entrained amphipods at the Indian Point plant. Neomysis americana were more heat sensitive, as indicated in bioassays, with average entrainment mortalities ranging from 30 to 60 percent during the summer. All species examined had higher immediate and latent mortalities during plant condenser chlorination. The ability of Gammarus to survive condenser passage and exposure to the Indian Point thermal discharge plume indicates that power plant operation on the lower Hudson River Estuary has no adverse impact on local gammarid amphipod populations. Entrained N. americana experience considerable mortalities; however, the impact on Atlantic Coast populations is minimized by the limited exposure of the population fringe to the Indian Point power plant

Nuclear plants near borders: environmental, legal, economic and political aspects

International Nuclear Information System (INIS)

Carle, R.

1990-01-01

Over the last few years, the legal framework of the development of nuclear energy within Europe has focussed on the special problems posed by nuclear plants located near national boundaries. The problems which may be caused by such plants must clearly be handled in the same way as for any other installations and the governments concerned need to define mutually acceptable conditions. Joint committees have already been formed between some countries, most notably to deal with nuclear plant safety issues. Special agreements have been reached covering the use of river water, public information and mutual assistance in case of accident. The key to the whole process is a progressive standardization of regulations concerning the environment, safety, radiological protection, non-proliferation, public information and emergency plans in case of accidents. (UK)

Analysis of extreme hydrometric values in the nuclear power plants siting

International Nuclear Information System (INIS)

Gomez, H.R.; Maggio, G.E.; Tripoli, C.R.

1983-01-01

The atucha nuclear power plants are located on the right shore of the Parana de las Palmas river in the entire transition between a fluvial regime and other of tides. Since the disponibility of cooling water is one of the factors to take into account when choosing the nuclear power plant site, it is essential to perform a probabilistic study of extreme hydrometric values. Deterministic and historical analysis should be done to complete the studies already mentioned, in order to establish the values of probable maximum floods. From the application of these methods, it is concluded that the site of the Atucha nuclear power plants constitutes a hydrometric singularity, so that, an optimization has been obtained from that point of view. (Author) [es

Design data and safety features of commerical nuclear power plant

International Nuclear Information System (INIS)

Heddleson, F.A.

1976-06-01

Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537

Arbuscular mycorrhizal fungi associations of vascular plants confined to river valleys: towards understanding the river corridor plant distribution.

Science.gov (United States)

Nobis, Agnieszka; Błaszkowski, Janusz; Zubek, Szymon

2015-01-01

The group of river corridor plants (RCP) includes vascular plant species which grow mainly or exclusively in the valleys of large rivers. Despite the long recognized fact that some plant species display a corridor-like distribution pattern in Central Europe, there is still no exhaustive explanation of the mechanisms generating this peculiar distribution. The main goal of this study was therefore to investigate whether arbuscular mycorrhizal fungi (AMF) and fungal root endophytes influence the RCP distribution. Arbuscular mycorrhizae (AM) were observed in 19 out of 33 studied RCP. Dark septate endophytes (DSE) and Olpidium spp. were recorded with low abundance in 15 and 10 plant species, respectively. The spores of AMF were found only in 32% of trap cultures established from the soils collected in the river corridor habitats. In total, six widespread AMF species were identified. Because the percentage of non-mycorrhizal species in the group of RCP is significant and the sites in river corridors are characterized by low AMF species diversity, RCP can be outcompeted outside river valleys by the widespread species that are able to benefit from AM associations in more stable plant-AMF communities in non-river habitats.

Use of aquatic mosses for monitoring artificial radionuclides downstream of the nuclear power plant of Bugey (River Rhone, France)

International Nuclear Information System (INIS)

Beaugelin-Seiller, K.; Brottet, D.

1994-01-01

The detection of radionuclides in water, downstream of nuclear installations located on river banks, is often very difficult notably because of their low concentrations. Thus the use of biological indicators is an interesting process to detect radioactive contamination of an aquatic ecosystem. From 1986 to 1990, artificial radionuclides were measured in freshwater mosses sampled downstream of the nuclear power station of Bugey. These field data on the whole, have shown a comparatively good qualitative and quantitative relationship between radioactive composition of liquid waste and radionuclides detected in mosses. In other respects, the results showed up a relatively clear hierarchical structure in the affinity of the different radionuclides for the mosses. To specify these relations, mesh bags containing allochtonous mosses were immersed at four stations downstream of the power plant and regularly sampled during a 10-h waste discharge period. (author)

Chemical fractionation of radionuclides and stable elements in aquatic plants of the Yenisei River.

Science.gov (United States)

Bolsunovsky, Alexander

2011-09-01

The Yenisei River is contaminated with artificial radionuclides released by one of the Russian nuclear plants. The aquatic plants growing in the radioactively contaminated parts of the river contain artificial radionuclides. The aim of the study was to investigate accumulation of artificial radionuclides and stable elements by submerged plants of the Yenisei River and estimate the strength of their binding to plant biomass by using a new sequential extraction scheme. The aquatic plants sampled were: Potamogeton lucens, Fontinalis antipyretica, and Batrachium kauffmanii. Gamma-spectrometric analysis of the samples of aquatic plants has revealed more than 20 radionuclides. We also investigated the chemical fractionation of radionuclides and stable elements in the biomass and rated radionuclides and stable elements based on their distribution in biomass. The greatest number of radionuclides strongly bound to biomass cell structures was found for Potamogeton lucens and the smallest for Batrachium kauffmanii. For Fontinalis antipyretica, the number of distribution patterns that were similar for both radioactive isotopes and their stable counterparts was greater than for the other studied species. The transuranic elements (239)Np and (241)Am were found in the intracellular fraction of the biomass, and this suggested their active accumulation by the plants.

Savannah River Plant Separations Department mixed waste program

International Nuclear Information System (INIS)

Wierzbicki, W.M.

1988-01-01

The Department of Energy's (DOE) Savannah River Plant (SRP) generates radioactive and mixed waste as a result of the manufacture of nuclear material for the national defense program. The radioactive portion of the mixed waste and all nonhazardous radioactive wastes would continue to be regulated by DOE under the Atomic Energy Act. The Separations Department is the largest generator of solid radioactive waste at the Savannah River Plant. Over the last three years, the Separations Department has developed and implemented a program to characterize candidate mixed-waste streams. The program consisted of facility personnel interviews, a waste-generation characterization program and waste testing to determine whether a particular waste form was hazardous. The Separations Department changed waste-handling practices and procedures to meet the requirements of the generator standards. For each Separation Department Facility, staging areas were established, inventory and reporting requirements were developed, operating procedures were revised to ensure proper waste handling, and personnel were provided hazardous waste training. To emphasize the importance of the new requirements, a newsletter was developed and issued to all Separations supervisory personnel

Flood hazards for nuclear power plants

International Nuclear Information System (INIS)

Yen, B.C.

1988-01-01

Flooding hazards for nuclear power plants may be caused by various external geophysical events. In this paper the hydrologic hazards from flash floods, river floods and heavy rain at the plant site are considered. Depending on the mode of analysis, two types of hazard evaluation are identified: 1) design hazard which is the probability of flooding over an expected service period, and 2) operational hazard which deals with real-time forecasting of the probability of flooding of an incoming event. Hazard evaluation techniques using flood frequency analysis can only be used for type 1) design hazard. Evaluation techniques using rainfall-runoff simulation or multi-station correlation can be used for both types of hazard prediction. (orig.)

Nuclear fuels accounting interface: River Bend experience

International Nuclear Information System (INIS)

Barry, J.E.

1986-01-01

This presentation describes nuclear fuel accounting activities from the perspective of nuclear fuels management and its interfaces. Generally, Nuclear Fuels-River Bend Nuclear Group (RBNG) is involved on a day-by-day basis with nuclear fuel materials accounting in carrying out is procurement, contract administration, processing, and inventory management duties, including those associated with its special nuclear materials (SNM)-isotopics accountability oversight responsibilities as the Central Accountability Office for the River Bend Station. As much as possible, these duties are carried out in an integrated, interdependent manner. From these primary functions devolve Nuclear Fuels interfacing activities with fuel cost and tax accounting. Noting that nuclear fuel tax accounting support is of both an esoteric and intermittent nature, Nuclear Fuels-RBNG support of developments and applications associated with nuclear fuel cost accounting is stressed in this presentation

Nuclear power plants

International Nuclear Information System (INIS)

Margulova, T.Ch.

1976-01-01

The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

Improvements MOIRA system for application to nuclear sites Spanish river

International Nuclear Information System (INIS)

Gallego Diaz, E.; Iglesias Ferrer, R.; Dvorzhak, A.; Hofman, D.

2011-01-01

Possible consequences of a nuclear accident must have radioactive contamination in the medium and long-term freshwater aquatic systems. Faced with this problem, it is essential to have a realistic assessment of the radiological impact, ecological, social and economic potential management strategies, to take the best decisions rationally. MOIRA is a system of decision support developed in the course of the European Framework Programmes with participation of the UPM, which has been improved and adapted to Spanish nuclear sites in recent years in the context ISIDRO Project, sponsored by the Council Nuclear, with the participation of CIEMAT and UPM. The paper focuses on these advances, primarily related to complex hydraulic systems such as rivers Tajo, Ebro and Jucar, which are located several Spanish plants.

Water management of the Dukovany nuclear power plant

International Nuclear Information System (INIS)

Rabusic, P.

1990-01-01

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

Experience with confirmatory measurements at the Savannah River Plant

International Nuclear Information System (INIS)

Deason, P.T.; Cadieux, J.R.; Denard, C.D.

1985-01-01

Confirmatory measurements are performed on all category I and II plutonium shipments to the Savannah River Plant (SRP). The primary technique employed has been neutron coincidence counting using three instruments; two slab counters, and a well counter. These measurements have provided the required safeguards features to support the physical security measures already in place for inter-site shipments of special nuclear material (SNM). Similar confirmatory measurements have also been performed on a variety of scrap mixed-oxide materials stored at SRP for later processing. The data handling and results for several categories of material will be examined in addition to planned uses of the Rocky Flats Plant (RFP)/SRP Confirmatory Measurements Counter (CMC). 2 refs., 4 figs

Entrainment of larval fishes at two nuclear power plants on the Missouri River in Nebraska

International Nuclear Information System (INIS)

Cada, G.F.

1977-01-01

A sampling program to assess the effects of entrainment in the cooling water systems at the Fort Calhoun and Cooper Nuclear Stations on larval fishes was carried out in the months of May, June, and July of 1974--1976. Fish larvae were collected with 2.3 m long, 0.5 m diameter Nitex plankton nets. The samples were taken to laboratory facilities where the living and dead larvae were separated from the debris, counted, and preserved for later identification and measurement. Samples collected above the intake structures of the power plants were used to determine the seasonal patterns, species composition, and abundance of ichthyoplankton in this region of the Missouri River. Relatively low larval fish densities throughout May and early June were generally followed by a single 2 to 3 week long peak in density in late June and early July, due primarily to the larvae of Aplodinotus grunniens. The observed densities then declined to near zero by the end of July. The horizontal distribution of ichthyoplankton was determined by dividing the river above the intake into three sections and sampling the sites sequentially. The highest concentrations of larvae were generally found along the cutting bank (Nebraska shore) and the lowest in the middle of the river. Twenty-four hour sampling was conducted to identify possible diurnal differences in the ichthyoplankton densities above the intake. On six occasions, collections were made every two hours over a 24-hour period. Although great variations in densities were noted over the sampling period, significant differences between mean day and night densities were demonstrated only once, and no recurring temporal pattern in drift rates was identified. Net-induced sampling mortality was found to be a significant factor in the analysis of entrainment mortality

Release and transport of artificial radionuclides from nuclear weapons related activities in the Ob River, Siberia over the course of the nuclear age

International Nuclear Information System (INIS)

Sayles, F.L.; Kenna, T.C.; Livingston, H.D.

1999-01-01

Studies of sediment cores from lakes on the flood plain of the Ob River, Siberia have been used to develop a history of the release, transport, and deposition of artificial radionuclides related to the development and testing of nuclear weapons over the duration of the nuclear age (∼1950 to the present) in this major Arctic river system. The Ob is of particular importance in this regard as two of the former Soviet Union's major weapons production plants, Mayak and Tomsk-7, and the Semipalatinsk test site are located within the Ob drainage basin. Accidents and intentional releases of radionuclides at both plants have been substantial, raising the issue of transport throughout this extensive river system as well as delivery to the Arctic Ocean. Our studies have included determining sediment profiles of 239,240 Pu, 137 Cs, and the natural nuclide 210 Pb and its parent 226 Ra in a number of cores from the Ob delta, as well as analysis of 239 Pu, 240 Pu, and 237 Np. The latter provide sensitive measures of the presence of non-fallout materials derived from weapons production activities

Tsunami hazard assessment on nuclear power plant site evaluation accordance on DS 417

International Nuclear Information System (INIS)

Akhmad Khusyairi

2011-01-01

Nuclear power plant site evaluation should conduct the hazard evaluation on tsunami. Global climate changes and particularly extreme meteorology and hydrology phenomena have an impact on the structure, systems and important components related to safety. Therefore, IAEA makes efforts to revise the IAEA Safety Standard Series NS-G 3.4, Meteorological Events in Site Evaluation for Nuclear Power Plants and IAEA safety standard series NS-G 3.5 Flood Hazard For Nuclear Power Plants On Coastal And River Sites, in order to provide protection against the public and the environment safety due to operation of nuclear power plants. There are two methods used in assessing tsunami hazard, probabilistic and deterministic methods. In the tsunami hazard assessment, some necessary information and data should be obtained to determine the basic design of tsunami hazard during designing nuclear power plants, especially the cooling system design. Flooding caused tsunami must be evaluated to determine the site protection system. Furthermore, There must be an evaluation on either coincident event or meteorological simultaneously tsunami event that caused the worst effect on the site. Therefore, the protection of the site from extreme tsunami can be planned. (author)

Nuclear safety at the Paks Plant

International Nuclear Information System (INIS)

Bajsz, Jozsef; Vamos, Gabor

1991-01-01

The Paks Nuclear Power Plant is located on the Danube river 114 km south of Budapest. It consists of four PWR units of the Soviet VVER-440 design. These are of the second generation design VVER 440 (model 213) with safety features as of 1975. It should be emphasized that these are two different generations of VVER 440 units. This is not always clear, not only to the general public, but sometimes even to people working in the nuclear industry. The widespread criticism of the first generation type 230 reactors is often extended to model 213 reactors, as the differences between the two models are often not sufficiently emphasized. In this situation it is very important to provide balanced information about the advantages and disadvantages of this reactor type. This paper attempts to do that. (author)

Use of a dam break model to assess flooding at Haddam Neck Nuclear Power Plant

International Nuclear Information System (INIS)

Scherrer, J.S.; Chery, D.L. Jr.

1984-01-01

Because of their proximity to necessary supplies of cooling water, nuclear power plants are susceptible to riverine flooding. Greater flood hazards exist where plants are located downstream of larger dams. The consequences of the Quabbin Reservoir dam failure on the Haddam Neck Nuclear Power Plant situated on the Connecticut River were investigated using a dam break flood routing model. Reasons for selecting a particular model are presented and the input assumption for the modeling process are developed. Relevant information concerning the level of manpower involvement is presented. The findings of this analysis demonstrate that the plant is adequately protected from the consequences of the postulated flood event

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

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

Examples of Savannah River water dilution between the Savannah River Plant and the Beaufort-Jasper and Port Wentworth water-treatment plants

International Nuclear Information System (INIS)

Hayes, D.W.

1983-01-01

A substantial dilution of the river water occurs between the Savannah River Plant (SRP) and the two treatment plants. This dilution results from inflow of surface and groundwater and from direct rainfall. The amount of dilution was estimated to be approximately 20% and 54% down to the Port Wentworth and Beaufort-Jasper plants, respectively

Inductively coupled plasma for atomic emission spectroscopy at the Savannah River Plant

International Nuclear Information System (INIS)

Coleman, J.T.

1986-01-01

The Savannah River Plant atomic emission spectroscopy laboratory has been in operation for over 30 years. Routine analytical methods and instrumentation are being replaced with current technology. Laboratory renovation will include the installation of contained dual excitation sources (inductively coupled plasma and d-c arc) with a direct reading spectrometer. The instrument will be used to provide impurity analyses of plutonium, uranium, and other nuclear fuel cycle materials

Integrated Nuclear Recycle Plant

International Nuclear Information System (INIS)

Patodi, Anuj; Parashar, Abhishek; Samadhiya, Akshay K.; Ray, Saheli; Dey, Mitun; Singh, K.K.

2017-01-01

Nuclear Recycle Board (NRB), Tarapur proposes to set up an 'Integrated Nuclear Recycle Plant' at Tarapur. This will be located in the premises of BARC facilities. The project location is at coastal town of Tarapur, 130 Km north of Mumbai. Project area cover of INRP is around 80 hectares. The plant will be designed to process spent fuel received from Pressurized Heavy Water Reactors (PHWRs). This is the first large scale integrated plant of the country. INRP will process spent fuel obtained from indigenous nuclear power plants and perform left over nuclear waste disposal

High level waste vitrification at the SRP [Savannah River Plant] (DWPF [Defense Waste Processing Facility] summary)

International Nuclear Information System (INIS)

Weisman, A.F.; Knight, J.R.; McIntosh, D.L.; Papouchado, L.M.

1988-01-01

The Savannah River Plant has been operating a nuclear fuel cycle since the early 1950's. Fuel and target elements are fabricated and irradiated to produce nuclear materials. After removal from the reactors, the fuel elements are processed to extract the products, and waste is stored. During the thirty years of operation including evaporation, about 30 million gallons of high level radioactive waste has accumulated. The Defense Waste Processing Facility (DWPF) under construction at Savannah River will process this waste into a borosilicate glass for long-term geologic disposal. The construction of the DWPF is about 70% complete; this paper will describe the status of the project, including design demonstrations, with an emphasis on the melter system. 9 figs

Nuclear plant simulation using the Nuclear Plant Analyzer

International Nuclear Information System (INIS)

Beelman, R.J.; Laats, E.T.; Wagner, R.J.

1984-01-01

The Nuclear Plant Analyzer (NPA), a state-of-the-art computerized safety analysis and engineering tool, was employed to simulate nuclear plant response to an abnormal transient during a training exercise at the US Nuclear Regulatory Commission (USNRC) in Washington, DC. Information relative to plant status was taken from a computer animated color graphics display depicting the course of the transient and was transmitted to the NRC Operations Center in a manner identical to that employed during an actual event. Recommendations from the Operations Center were implemented during on-line, interactive execution of the RELAP5 reactor systems code through the NPA allowing a degree of flexibility in training exercises not realized previously. When the debriefing was conducted, the RELAP5 calculations were replayed by way of the color graphics display, adding a new dimension to the debriefing and greatly enhancing the critique of the exercise

Nuclear power plant outages

International Nuclear Information System (INIS)

1998-01-01

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

Environmental monitoring in the vicinity of the Savannah River Plant. Annual report, 1976

International Nuclear Information System (INIS)

1976-01-01

A continuous monitoring program has been maintained since 1951 (before plant start-up) to determine concentrations of radioactive materials in a 1200-square-mile area outside SRP. Although some gaseous and liquid radioactive materials are discharged from SRP operations, concentrations and doses to the surrounding population continued to be far below levels considered significant from a public health viewpoint. The concentration of radioactivity added by SRP to its environs during 1976 was too small to be distinguished from natural background radiation and fallout from worldwide nuclear weapons tests. Beta activity in particulate air filters was about 1.5 times the 1975 level and was due entirely to global fallout. This concentration, both at the plant perimeter and 25 miles away (0.07 pCi/m 3 ), represents 0.07% of the Concentration Guide (CG) (defined in the Applicable Standards section which follows). Tritium oxide in air at the plant perimeter was greater than in air at more distant locations; the average concentration at the plant perimeter (50 pCi/m 3 ) was less than 0.1 of the Concentration Guide. Tritium, cesium-137, and strontium-90 were the only radionuclides of plant origin detectable in river water by routine analyses.Special research programs using ultra-low-level techniques have detected trace quantities of other radionuclides of plant origin. Radioactive materials in river fish also continued very low. Monitoring in a five-square-mile swamp bordering the Savannah River immediately below the SRP boundary has shown radioactivity (primarily cesium-137) above the natural background level in soil and vegetation

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

International Nuclear Information System (INIS)

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

1994-05-01

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

Potential impact of thermal effluents from Chongqing Fuling nuclear power plant to the Three Gorges Reservoir

International Nuclear Information System (INIS)

Han Baohua; Li Jianguo; Ma Binghui; Zhang Yue; Sun Qunli; Hu Yuping

2012-01-01

This study is based on the hydrological data near Chongqing Fuling Nuclear Power Plant along the Yangtze River, the present situation of the ecological environment of the Three Gorges Reservoir and the predicted results of thermal effluents from Chongqing Fuling Nuclear Power Plant. The standards of cooling water and the thermal tolerances indexes of aquatic organisms were investigated. The effects of thermal effluents on aquatic organisms were analyzed. The potential impact of Chongqing Fuling nuclear power plant to the Three Gorges Reservoir was explained. The results show that in the most adverse working conditions, the surface temperature near the outfall area is not more than 1℃, the temperature of thermal effluents do not exceed the suitable thermal range of fish breeding, growth and other thermal tolerances indexes. Thermal effluents from nuclear power plant have no influence about fish, plankton and benthic organisms in the Three Gorges Reservoir. (authors)

Biological surveys on the Savannah River in the vicinity of the Savannah River Plant (1951-1976)

Energy Technology Data Exchange (ETDEWEB)

Matthews, R. A.

1982-04-01

In 1951, the Academy of Natural Sciences of Philadelphia was contracted by the Savannah River Plant to initiate a long-term monitoring program in the Savannah River. The purpose of this program was to determine the effect of the Savannah River Plant on the Savannah River aquatic ecosystem. The data from this monitoring program have been computerized by the Savannah River Laboratory, and are summarized in this report. During the period from 1951-1976, 16 major surveys were conducted by the Academy in the Savannah River. Water chemistry analyses were made, and all major biological communities were sampled qualitatively during the spring and fall of each survey year. In addition, quantitative diatom data have been collected quarterly since 1953. Major changes in the Savannah River basin, in the Savannah River Plant's activities, and in the Academy sampling patterns are discussed to provide a historical overview of the biomonitoring program. Appendices include a complete taxonomic listing of species collected from the Savannah River, and summaries of the entire biological and physicochemical data base.

Safety-Evaluation Report related to the construction of the Clinch River Breeder Reactor Plant. Docket No. 50-537

International Nuclear Information System (INIS)

1983-03-01

The Safety-Evaluation Report for the application by the United States Department of Energy, Tennessee Valley Authority, and the Project Management Corporation, as applicants and owners, for a license to construct the Clinch River Breeder Reactor Plant (docket No. 50-537) has been prepared by the Office of Nuclear Reactor Regulation of the United States Nuclear Regulatory Commission. The facility will be located on the Clinch River approximately 12 miles southwest of downtown Oak Ridge and 25 miles west of Knoxville, Tennessee. Subject to resolution of the items discussed in this report, the staff concludes that the construction permit requested by the applicants should be issued

Nuclear power plant siting

International Nuclear Information System (INIS)

Sulkiewicz, M.; Navratil, J.

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

Determination of {sup 90}Sr, {sup 63}Ni and {sup 55}Fe activities by liquid scintillation counting in the environmental samples close to French nuclear power plants located on Loire and Garonne rivers

Energy Technology Data Exchange (ETDEWEB)

Rousseau, G.; Mokili, M.B.; Le Roy, C.; Deniau, I. [SUBATECH, IN2P3 (France); Gontier, G.; Boyer, C. [EDF-DPI-DIN-CIDEN (France); Hemidy, P.Y. [EDF-DPN-UNIE-GPRE-IEV (France); Chardon, P. [CNRS/IN2P3 (France)

2014-07-01

The protection of the aquatic and terrestrial environment from a wide range of radioactive contaminants released by nuclear industry requires continuous monitoring of radionuclides released into the environment. Specific measurement methods depending of the radionuclide are used to determinate this contribution. A lot of radionuclide can easily be measured at low level by gamma spectrometry, like {sup 137}Cs, {sup 60}Co..., but others like {sup 90}Sr, {sup 63}Ni or {sup 55}Fe require prior specific radiochemical separations. Activity of {sup 90}Sr values in environmental samples are available but only few measurements of {sup 63}Ni and {sup 55}Fe activities have been carried out in samples collected in the environment close to French nuclear power plants located on the Loire and Garonne rivers despite they represent 12% to 24% for {sup 63}Ni activity and <1% for {sup 55}Fe + other minor radionuclides of total activity of their liquid effluent discharges. {sup 90}Sr is not rejected by the liquid effluent discharges of Nuclear Power Plants and can be found in the environmental samples because of thermonuclear test and subsequently after the Chernobyl nuclear power plant accident. Considering the French Nuclear Power Plant located on Loire and Garonne rivers, the determination of {sup 90}Sr, {sup 63}Ni and {sup 55}Fe levels in the environmental samples around French nuclear power plants is carried out to detect the traces of these radionuclides originating from nuclear technology activities. The environment around five French nuclear Power Plants was investigated for 4 years between 2009 and 2014. The radionuclide activities determined by liquid scintillation counting after chemical steps were performed on a large set of various matrix samples likely to be encountered in environmental monitoring as soils, sediments, terrestrial and aquatic bio-indicators. It was found that the mean activity concentration of the most frequently detected was for the radionuclide {sup 90

Images of nuclear power plants

International Nuclear Information System (INIS)

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

1995-01-01

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

River channel morphology and hydraulics properties due to introduction of plant basket hydraulic structures for river channel management

Science.gov (United States)

Kałuża, Tomasz; Radecki-Pawlik, Artur; Plesiński, Karol; Walczak, Natalia; Szoszkiewicz, Krzysztof; Radecki-Pawlik, Bartosz

2016-04-01

In the present time integrated water management is directly connected with management and direct works in river channels themselves which are taking into account morphological processes in rivers and improve flow conditions. Our work focused on the hydraulic and hydrodynamic consequences upon the introduction of the concept of the improvement of the hydromorphological conditions of the Flinta River in a given reach following river channel management concept. Based on a comprehensive study of the hydromorphological state of the river, four sections were selected where restoration measures can efficiently improve river habitat conditions in the river. For each section a set of technical and biological measures were proposed and implemented in practice. One of the proposed solutions was to construct plant basket hydraulic structures (PBHS) within the river channel, which are essentially plant barriers working as sediment traps, changing river channel morphology and are in line with concepts of Water Framework Directive. These relatively small structures work as crested weirs and unquestionably change the channel morphology. Along our work we show the results of three-year long (2013-2015) systematic measurements that provided information on the morphological consequences of introducing such structures into a river channel. Our main conclusions are as follows: 1. Plant basket hydraulic structures cause changes in hydrodynamic conditions and result in sediment accumulation and the formation of river backwaters upstream and downstream the obstacle; 2. The introduced plant basket hydraulic structures cause plant debris accumulation which influences the hydrodynamic flow conditions; 3. The installation of plant basket hydraulic structures on the river bed changes flow pattern as well as flow hydrodynamic conditions causing river braiding process; 4. The erosion rate below the plant basket hydraulic structures is due to the hydraulic work conditions of the PBHS and its

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2003-01-01

This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

Westinghouse Savannah River Company (WSRC) approach to nuclear facility maintenance

International Nuclear Information System (INIS)

Harrison, D.W.

1991-01-01

The Savannah River Site (SRS) in South Carolina is a 300+ square mile facility owned by the US Department of Energy (DOE) and operated by Westinghouse Savannah River Company (WSRC), the prime contractor; Bechtel Savannah River, Incorporated (BSRI) is a major subcontractor. The site has used all of the five nuclear reactors and it has the necessary nuclear materials processing facilities, as well as waste management and research facilities. The site has produced materials for the US nuclear arsenal and various isotopes for use in space research and nuclear medicine for more than 30 years. In 1989, WSRC took over as prime contractor, replacing E.I. du Pont de Nemours and Company. At this time, a concentrated effort began to more closely align the operating standards of this site with those accepted by the commercial nuclear industry of the United States. Generally, this meant acceptance of standards of the Institute of Nuclear Power Operations (INPO) for nuclear-related facilities at the site. The subject of this paper is maintenance of nuclear facilities and, therefore, excludes discussion of the maintenance of non-nuclear facilities and equipment

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

Science.gov (United States)

2011-01-10

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

Twenty-five years of environmental radionuclide concentrations near a nuclear power plant.

Science.gov (United States)

Harris, Charles; Kreeger, Danielle; Patrick, Ruth; Palms, John

2015-05-01

The areas in and along a 262-km length of the Susquehanna River in Pennsylvania were monitored for the presence of radioactive materials. This study began two months after the 1979 Three Mile Island (TMI) partial reactor meltdown; it spanned the next 25 y. Monitoring points included stations at the PPL Susquehanna and TMI nuclear power plants. Monthly gamma measurements document concentrations of radionuclides from natural and anthropogenic sources. During this study, various series of gamma-emitting radionuclide concentration measurements were made in many general categories of animals, plants, and other inorganic matter. Sampling began in 1979 before the first start-up of the PPL Susquehanna power plant. Although all species were not continuously monitored for the entire period, an extensive database was compiled. In 1986, the ongoing measurements detected fallout from the Chernobyl nuclear accident. These data may be used in support of dose or environmental transport calculations.

Province of Ontario nuclear emergency plan part V - Chalk River

International Nuclear Information System (INIS)

1991-10-01

The aim of Part 5 of the Provincial Nuclear Emergency Plan is to describe the measures that shall be undertaken to deal with a nuclear emergency caused by the Chalk River Laboratories. This plan deals mainly with actions at the Provincial level and shall by supplemented by the appropriate Municipal Plan. The Townships of Rolph, Buchanan, Wylie, and McKay, the Town of Deep River and the Village of Chalk River are the designated municipalities with respect to CRL. 2 tabs., 5 figs

Province of Ontario nuclear emergency plan part V - Chalk River

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-10-01

The aim of Part 5 of the Provincial Nuclear Emergency Plan is to describe the measures that shall be undertaken to deal with a nuclear emergency caused by the Chalk River Laboratories. This plan deals mainly with actions at the Provincial level and shall by supplemented by the appropriate Municipal Plan. The Townships of Rolph, Buchanan, Wylie, and McKay, the Town of Deep River and the Village of Chalk River are the designated municipalities with respect to CRL. 2 tabs., 5 figs.

Life management plants at nuclear power plants PWR

International Nuclear Information System (INIS)

Esteban, G.

2014-01-01

Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

Benchmarking Nuclear Power Plants

International Nuclear Information System (INIS)

Jakic, I.

2016-01-01

One of the main tasks an owner have is to keep its business competitive on the market while delivering its product. Being owner of nuclear power plant bear the same (or even more complex and stern) responsibility due to safety risks and costs. In the past, nuclear power plant managements could (partly) ignore profit or it was simply expected and to some degree assured through the various regulatory processes governing electricity rate design. It is obvious now that, with the deregulation, utility privatization and competitive electricity market, key measure of success used at nuclear power plants must include traditional metrics of successful business (return on investment, earnings and revenue generation) as well as those of plant performance, safety and reliability. In order to analyze business performance of (specific) nuclear power plant, benchmarking, as one of the well-established concept and usual method was used. Domain was conservatively designed, with well-adjusted framework, but results have still limited application due to many differences, gaps and uncertainties. (author).

Solidification of Savannah River Plant high-level waste

International Nuclear Information System (INIS)

Maher, R.; Shafranek, L.F.; Stevens, W.R. III.

1983-01-01

The Department of Energy, in accord with recommendations from the Du Pont Company, has started construction of a Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The facility should be completed by the end of 1988, and full-scale operation should begin in 1990. This facility will immobilize in borosilicate glass the large quantity of high-level radioactive waste now stored at the plant plus the waste to be generated from continued chemical reprocessing operations. The existing wastes at the Savannah River Plant will be completely converted by about 2010. 21 figures

Chemical aspects of gadolinium nitrate as soluble nuclear poison in Savannah River Plant reactors

International Nuclear Information System (INIS)

Baumann, E.W.

1978-01-01

The aqueous solution chemistry of gadolinium nitrate was studied to identify conditions that interfere with successful cleanup of gadolinium in Savannah River Plant reactor systems. Injecting a gadolinium nitrate solution into the D 2 O coolant-moderator constitutes a supplementary mode of reactor shutdown. The resulting approximately 0.001M gadolinium nitrate solution is then deionized by recirculation through mixed-bed ion exchange resins before reactor operation is resumed

Movement of radionuclides from river to ground water in vicinity of location for nuclear power plant

International Nuclear Information System (INIS)

Knezevic, Lj.; Lazic, S.; Vukovic, Z.

1984-01-01

The possibility of ground water contamination caused by radionuclide from river water to which liquid effluents were released from a nuclear power station was estimated using one-dimensional transport model. This model is suitable for a homogeneous medium and takes into account hydraulic convection and dispersion as well as physical-chemical retardation for the various radionuclides. (author)

Are atomic power plants saver than nuclear power plants

International Nuclear Information System (INIS)

Roeglin, H.C.

1977-01-01

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

Environmental monitoring and ecological studies program. 1974 annual report for the Prairie Island Nuclear Generating Plant near Red Wing, Minnesota. Volume II

International Nuclear Information System (INIS)

1975-06-01

Data are presented from studies on the effects of thermal effluents from the Prairie Island nuclear power plant on fish and invertebrate populations in the Mississippi River in the vicinity of the plant. Populations of aquatic and terrestrial plants and birds in the immediate vicinity of the plant were also characterized. (U.S.)

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2005-01-01

This 2005 edition of the Elecnuc booklet summarizes in tables all numerical data relative to the nuclear power plants worldwide. These data come from the PRIS database managed by the IAEA. The following aspects are reviewed: 2004 highlights; main characteristics of reactor types; map of the French nuclear power plants on 2005/01/01; worldwide status of nuclear power plants at the end of 2004; units distributed by countries; nuclear power plants connected to the grid by reactor-type group; nuclear power plants under construction on 2004; evolution of nuclear power plant capacities connected to the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear power plants by country at the end 2004; performance indicator of PWR units in France; trend of the generation indicator worldwide; 2004 load factor by owners; units connected to the grid by countries at 12/31/2004; status of licence renewal applications in USA; nuclear power plants under construction at 12/31/2004; shutdown reactors; exported nuclear capacity in net MWe; exported and national nuclear capacity connected to the grid; exported nuclear power plants under construction or order; exported and national nuclear capacity under construction or order; recycling of plutonium in LWR; Mox licence plant projects; Appendix - historical development; acronyms, glossary

Nuclear power plant operator licensing

International Nuclear Information System (INIS)

1997-01-01

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

Organizing nuclear power plant operation

International Nuclear Information System (INIS)

Adams, H.W.; Rekittke, K.

1987-01-01

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

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2003-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2002 was made up on bases of answers on questionnaires from 65 electric power companies and other nuclear organizations in 28 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

On nuclear power plant uprating

International Nuclear Information System (INIS)

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

2004-01-01

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

Plant Design Nuclear Fuel Element Production Capacity Optimization to Support Nuclear Power Plant in Indonesia

International Nuclear Information System (INIS)

Bambang Galung Susanto

2007-01-01

The optimization production capacity for designing nuclear fuel element fabrication plant in Indonesia to support the nuclear power plant has been done. From calculation and by assuming that nuclear power plant to be built in Indonesia as much as 12 NPP and having capacity each 1000 MW, the optimum capacity for nuclear fuel element fabrication plant is 710 ton UO 2 /year. The optimum capacity production selected, has considered some aspects such as fraction batch (cycle, n = 3), length of cycle (18 months), discharge burn-up value (Bd) 35,000 up 50,000 MWD/ton U, enriched uranium to be used in the NPP (3.22 % to 4.51 %), future market development for fuel element, and the trend of capacity production selected by advances country to built nuclear fuel element fabrication plant type of PWR. (author)

Nuclear security - New challenge to the safety of nuclear power plants

International Nuclear Information System (INIS)

Li Ganjie

2008-01-01

The safety of nuclear power plants involves two aspects: one is to prevent nuclear accidents resulted from systems and equipments failure or human errors; the other is to refrain nuclear accidents from external intended attack. From this point of view, nuclear security is an organic part of the nuclear safety of power plants since they have basically the same goals and concrete measures with each other. In order to prevent malicious attacks; the concept of physical protection of nuclear facilities has been put forward. In many years, a series of codes and regulations as well as technical standard systems on physical protection had been developed at international level. The United Nations passed No. 1540 resolution as well as 'Convention on the Suppression of Acts of Nuclear terrorism', and revised 'Convention on Physical Protection of Nuclear Materials', which has enhanced a higher level capacity of preparedness by international community to deal with security issues of nuclear facilities. In China, in order to improve the capability of nuclear power plants on preventing and suppressing the external attacks, the Chinese government consecutively developed the related codes and standards as well as technical documents based on the existing laws and regulations, including 'Guide for the Nuclear Security of Nuclear Power Plants' and 'Guide for the Physical Protection of Nuclear Materials', so as to upgrade the legislative requirements for nuclear security in power plants. The government also made greater efforts to support the scientific research and staff training on physical protection, and satisfying the physical protection standards for newly-built nuclear facilities such as large scale nuclear power plants to meet requirement at international level. At the same time old facilities were renovated and the Chinese government established a nuclear emergency preparedness coordination mechanism, developed corresponding emergency preparedness plans, intensified the

Nuclear power plants in the world

International Nuclear Information System (INIS)

2008-01-01

The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2007/2008 was made up on bases of answers on questionnaires from electric power companies and other nuclear organizations around the world by JAIF. This report is comprised of 18 items, and contains generating capacity of the plants; effect of the Niigata-ken chuetsu-oki earthquake; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities, and so forth. (J.P.N.)

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2004-01-01

The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2003 was made up on bases of answers on questionnaires from 81 electric power companies and other nuclear organizations in 33 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

Regularization methods for inferential sensing in nuclear power plants

International Nuclear Information System (INIS)

Hines, J.W.; Gribok, A.V.; Attieh, I.; Uhrig, R.E.

2000-01-01

Inferential sensing is the use of information related to a plant parameter to infer its actual value. The most common method of inferential sensing uses a mathematical model to infer a parameter value from correlated sensor values. Collinearity in the predictor variables leads to an ill-posed problem that causes inconsistent results when data based models such as linear regression and neural networks are used. This chapter presents several linear and non-linear inferential sensing methods including linear regression and neural networks. Both of these methods can be modified from their original form to solve ill-posed problems and produce more consistent results. We will compare these techniques using data from Florida Power Corporation's Crystal River Nuclear Power Plant to predict the drift in a feedwater flow sensor. According to a report entitled 'Feedwater Flow Measurement in U.S. Nuclear Power Generation Stations' that was commissioned by the Electric Power Research Institute, venturi meter fouling is 'the single most frequent cause' for derating in Pressurized Water Reactors. This chapter presents several viable solutions to this problem. (orig.)

Nuclear Power Plants (Rev.)

Energy Technology Data Exchange (ETDEWEB)

Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

1973-01-01

Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

2005-04-01

Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

Nuclear power plants in post-war thought

International Nuclear Information System (INIS)

Toya, Hiroshi

2015-01-01

This paper overviews how nuclear power plants have been talked about in the post-war thought. Science and technology sometimes significantly change the thinking way of humans, and nuclear power generation is an extreme technology. This paper overviews how nuclear power plants and humans are correlated. The following three points are discussed as the major issues of contemporary thought over nuclear power plants. First, on the danger of nuclear power plants, the risk of destructive power that nuclear energy has, and the danger of unreasoning development in science and technology civilization are discussed. Second, on the ethics issues surrounding nuclear power plants, the ethics that are based on unbalanced power relations, and democratic responsibility ethics based on discussion ethics are discussed. Third, on the issues of nuclear power plants and imagination, the limitations of democratic discussion surrounding nuclear power plants, the formation of imagination commensurate with the destructive power of nuclear power plants, and the formation of imagination that can represent the distant future are discussed. (A.O.)

Public regulation of nuclear plants

International Nuclear Information System (INIS)

Burtheret, M.; Cormis, de

1980-01-01

The construction and operation of nuclear plants are subject to a complex system of governmental administration. The authors list the various governmental authorisations and rules applicable to these plants. In the first part, they describe the national regulations which relate specifically to nuclear plants, and emphasize the provisions which are intended to ensure the safety of the installations and the protection of the public against ionizing radiation. However, while the safety of nuclear plants is a major concern of the authorities, other interests are also protected. This is accomplished by various laws or regulations which apply to nuclear plants as well as other industrial installations. The duties which these texts, and the administrative practice based thereon, impose on Electricite de France are covered in the second part [fr

Savannah River Site nuclear materials management plan FY 2017-2031

Energy Technology Data Exchange (ETDEWEB)

Magoulas, V. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-06-22

The purpose of the Nuclear Materials Management Plan (herein referred to as “this Plan”) is to integrate and document the activities required to disposition the legacy and/or surplus Enriched Uranium (EU) and Plutonium (Pu) and other nuclear materials already stored or anticipated to be received by facilities at the Department of Energy (DOE) Savannah River Site (SRS) as well as the activities to support the DOE Tritium mission. It establishes a planning basis for EU and Pu processing operations in Environmental Management Operations (EMO) facilities through the end of their program missions and for the tritium through the National Nuclear Security Administration (NNSA) Defense Programs (DP) facilities. Its development is a joint effort among the Department of Energy - Savannah River (DOE-SR), DOE – Environmental Management (EM), NNSA Office of Material Management and Minimization (M3), NNSA Savannah River Field Office (SRFO), and the Management and Operations (M&O) contractor, Savannah River Nuclear Solutions, LLC (SRNS). Life-cycle program planning for Nuclear Materials Stabilization and Disposition and the Tritium Enterprise may use this Plan as a basis for the development of the nuclear materials disposition scope and schedule. This Plan assumes full funding to accomplish the required project and operations activities. It is recognized that some aspects of this Plan are pre decisional with regard to National Environmental Policy Act (NEPA); in such cases new NEPA actions will be required.

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2000-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Developmental trends on nuclear power plants in the world'. In this report, some data at the end of 1999 was made up on bases of answers on questionnaires from 72 electric companies in 31 nations and regions in the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; location of the plants; the plants in the world; and so forth. And, it also has some survey results on the 'Liberalization of electric power markets and nuclear power generation' such as some 70% of respondents in nuclear power for future option, gas-thermal power seen as power source with most to gain from liberalization, merits on nuclear power generation (environmental considerations and supply stability), most commonly voiced concern about new plant orders in poor economy, and so forth. (G.K.)

Plant basket hydraulic structures (PBHS) as a new river restoration measure.

Science.gov (United States)

Kałuża, Tomasz; Radecki-Pawlik, Artur; Szoszkiewicz, Krzysztof; Plesiński, Karol; Radecki-Pawlik, Bartosz; Laks, Ireneusz

2018-06-15

River restoration has become increasingly attractive worldwide as it provides considerable benefits to the environment as well as to the economy. This study focuses on changes of hydromorphological conditions in a small lowland river recorded during an experiment carried out in the Flinta River, central Poland. The proposed solution was a pilot project of the construction of vegetative sediment traps (plant basket hydraulic structures - PBHS). A set of three PBSH was installed in the riverbed in one row and a range of hydraulic parameters were recorded over a period of three years (six measurement sessions). Changes of sediment grain size were analysed, and the amount and size of plant debris in the plant barriers were recorded. Plant debris accumulation influencing flow hydrodynamics was detected as a result of the installation of vegetative sediment traps. Moreover, various hydromorphological processes in the river were initiated. Additional simulations based on the detected processes showed that the proposed plant basket hydraulic structures can improve the hydromorphological status of the river. Copyright © 2018 Elsevier B.V. All rights reserved.

Nuclear power plant safety

International Nuclear Information System (INIS)

Otway, H.J.

1974-01-01

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

Environmental monitoring in the vicinity of the Savannah River Plant. Annual report for 1975

International Nuclear Information System (INIS)

1975-01-01

The concentration of radioactivity added by the Savannah River Plant to its environs during 1975 was, for the most part, too small to be distinguished from natural background radiation and fallout from worldwide nuclear weapons tests. Beta activity in particulate air filters was about one-half of the 1974 level and was due entirely to global fallout. An accidental release of tritium to the atmosphere occurred in a production facility on December 31, 1975. Monitoring teams were deployed along the estimated puff trajectory immediately following the release. Monitoring extended from the production facility to the Atlantic Ocean north of Charleston, SC. Environmental sample concentrations of tritium oxide were all within normal ranges. The low concentrations of tritium measured in environmental samples around the plantsite were of no health significance. Tritium, cesium-137, and strontium-90 were the only radionuclides of plant origin detectable in river water by routine analyses. None of these had an average concentration exceeding 0.2 percent of the Concentration Guide in river water samples 8 miles downstream from the plant. Monitoring in an offsite swamp immediately below the SRP boundary has shown radioactivity (primarily cesium-137) above the natural background level in soil and vegetation. Only one-third of a five-square-mile swamp, which is largely uninhabited and inaccessible, bordering the Savannah River and downstream from SRP is affected. No restrictions on use of the swamp are considered warranted nor are remedial actions needed. Concentrations of radioactivity in vegetation and soil were, in most instances, lower than those reported in 1974. During 1975 the average dose from atmospheric releases of radioactive materials from SRP was calculated to be 0.66 millirem (mrem) at the plant perimeter

Summary of nuclear power plant construction

International Nuclear Information System (INIS)

Tamura, Saburo

1973-01-01

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

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

1998-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Nuclear power plant diagnostic system

International Nuclear Information System (INIS)

Prokop, K.; Volavy, J.

1982-01-01

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

KWU Nuclear Plant Analyzer

International Nuclear Information System (INIS)

Bennewitz, F.; Hummel, R.; Oelmann, K.

1986-01-01

The KWU Nuclear Plant Analyzer is a real time engineering simulator based on the KWU computer programs used in plant transient analysis and licensing. The primary goal is to promote the understanding of the technical and physical processes of a nuclear power plant at an on-site training facility. Thus the KWU Nuclear Plant Analyzer is available with comparable low costs right at the time when technical questions or training needs arise. This has been achieved by (1) application of the transient code NLOOP; (2) unrestricted operator interaction including all simulator functions; (3) using the mainframe computer Control Data Cyber 176 in the KWU computing center; (4) four color graphic displays controlled by a dedicated graphic computer, no control room equipment; and (5) coupling of computers by telecommunication via telephone

Study on the distribution coefficient during environmental impact evaluation in Chinese inland nuclear power plants

International Nuclear Information System (INIS)

Xu Haifeng; Shang Zhaorong; Chen Fangqiang

2012-01-01

Description the radionuclide distribution coefficient of the important factors in the river sediment systems, at home and abroad the main method of measuring the K d value and progress in China's inland nuclear power plant environmental impact assessment of workers to carry out the distribution coefficient K d value measurement ideas put forward recommendations. (authors)

Nuclear accidents and safety measures of domestic nuclear power plants

International Nuclear Information System (INIS)

Song Zurong; Che Shuwei; Pan Xiang

2012-01-01

Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

Perspectives of nuclear power plants

International Nuclear Information System (INIS)

Vajda, Gy.

2001-01-01

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

Off-shore nuclear power plant

International Nuclear Information System (INIS)

Nakanishi, T.

1980-01-01

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

Plant life management optimized utilization of existing nuclear power plants

International Nuclear Information System (INIS)

Watzinger, H.; Erve, M.

1999-01-01

For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

Application of a model-based fault detection system to nuclear plant signals

International Nuclear Information System (INIS)

Gross, K.C.; Singer, R.M.; Wegerich, S.W.; Herzog, J.P.; VanAlstine, R.; Bockhorst, F.

1997-01-01

To assure the continued safe and reliable operation of a nuclear power station, it is essential that accurate online information on the current state of the entire system be available to the operators. Such information is needed to determine the operability of safety and control systems, the condition of active components, the necessity of preventative maintenance, and the status of sensory systems. To this end, ANL has developed a new Multivariate State Estimation Technique (MSET) which utilizes advanced pattern recognition methods to enhance sensor and component operational validation for commercial nuclear reactors. Operational data from the Crystal River-3 (CR-3) nuclear power plant are used to illustrate the high sensitivity, accuracy, and the rapid response time of MSET for annunciation of a variety of signal disturbances

1980 nuclear plant survey: no reactors sold; more cancellations

International Nuclear Information System (INIS)

Friedlander, G.D.

1980-01-01

No sales were reported in 1979 by any of the big four reactor suppliers. Three cancellations were reported and construction was suspended on the Jersey Central Power and Light Co.'s Forked River unit. Since last year's survey, the commercial operation dates of about 80 units have been postponed from one year to indefinitely, and nuclear commitments are down from last year's 195 units to 193 units. Presently, there are 72 plants on line, with a capacity of more than 53,000 MW. A resumption of new reactor orders is expected in either late 1980 or early 1981

Building of nuclear power plant

International Nuclear Information System (INIS)

Saito, Takashi.

1997-01-01

A first nuclear plant and a second nuclear power plant are disposed in adjacent with each other in a building for a nuclear reactor. A reactor container is disposed in each of the plants, and each reactor container is surrounded by a second containing facility. A repairing chamber capable of communicating with the secondary containing facilities for both of the secondary containing facilities is disposed being in contact with the second containing facility of each plant for repairing control rod driving mechanisms or reactor incorporated-type recycling pumps. Namely, the repairing chamber is in adjacent with the reactor containers of both plants, and situated between both of the plants as a repairing chamber to be used in common for both plants. Air tight inlet/exit doors are formed to the inlets/exits of both plants of the repairing chamber. Space for the repairing chamber can be reduced to about one half compared with a case where the repairing chamber is formed independently on each plant. (I.N.)

Nuclear Power Plants. Revised.

Science.gov (United States)

Lyerly, Ray L.; Mitchell, Walter, III

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

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

Science.gov (United States)

2010-10-29

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

Electromagnetic compatibility of nuclear power plants

International Nuclear Information System (INIS)

Cabayan, H.S.

1983-01-01

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

Nuclear power plants in populated areas

International Nuclear Information System (INIS)

Wachsmann, F.

1973-01-01

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

Determination of water fluoride levels in the vicinities of the nuclear fuel plant in Resende, Rio de Janeiro

International Nuclear Information System (INIS)

Carneiro, L.A.; Castro Faria, M.V. de

1983-01-01

The water fluoride levels in rivers and lakes, in a total of 26 different collection points placed within a circle of 10 km in diameter having the Nuclear Fuel Plant of Resende, Rio de Janeiro, as the center, were determined. (E.G.) [pt

Dissipation of the reactor heat at the Savannah River Plant

International Nuclear Information System (INIS)

Neill, J.S.; Babcock, D.F.

1971-10-01

The effluent cooling water from the heat exchangers of the Savannah River nuclear reactors is cooled by natural processes as it flows through the stream beds, canals, ponds, and swamps on the plant site. The Langhaar equation, which gives the rate of heat removal from the water surface as a function of the surface temperature, air temperature, relative humidity, and wind speed, is applied satisfactorily to calculate the cooling that occurs at all temperature levels and for all modes of water flow. The application of this equation requires an accounting of effects such as solar heating, shading, mixing, staging, stratification, underflow, rainfall, the imposed heat load, and the rate of change in heat content of the body of water

Saltstone processing startup at the Savannah River Plant

International Nuclear Information System (INIS)

Wilhite, E.L.; Langton, C.A.; Sturm, H.F.; Hooker, R.L.; Occhipinti, E.S.

1988-01-01

High-level nuclear wastes are stored in large underground tanks at the Savannah River Plant. Processing of this waste in preparation for ultimate disposal will begin in 1988. The waste will be processed to separate the high-level radioactive fraction from the low-level radioactive fraction. The separation will be made in existing waste tanks by a process combining precipitation, adsorption, and filtration. The high-level fraction will be vitrified into borosilicate glass in the Defense Waste Processing Facility (DWPF) for permanent disposal in a federal repository. The low-level fraction (decontaminated salt solution) will be mixed with a cementitious slag-flyash blend. The resulting wasteform, saltstone, will be disposed of onsite by emplacement in an engineered facility. Waste properties, disposal facility details, and wasteform characteristics are discussed. In particular, details of saltstone processing, focusing on experience obtained from facility startup, are presented

Overview of Savannah River Plant waste management operations

International Nuclear Information System (INIS)

Haywood, J.E.; Killian, T.H.

1987-01-01

The Du Pont Savannah River Plant (SRP) Waste Management Program is committed to the safe handling, storage, and disposal of wastes that result from the production of special nuclear materials for the US Department of Energy (US DOE). High-level radioactive liquid waste is stored in underground carbon steel tanks with double containment, and the volume is reduced by evaporation. An effluent treatment facility is being constructed to treat low-level liquid hazardous and radioactive waste. Solid low-level waste operations have been improved through the use of engineered low-level trenches, and transuranic waste handling procedures were modified in 1974 to meet new DOE criteria requiring 20-year retrievable storage. An improved disposal technique, Greater Confinement Disposal, is being demonstrated for intermediate-level waste. Nonradioactive hazardous waste is stored on site in RCRA interim status storage buildings. 5 figs

Nuclear Security for Floating Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-13

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

Nuclear power plants in the world - 2010 edition

International Nuclear Information System (INIS)

2010-01-01

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

Three run-of-river power plants

International Nuclear Information System (INIS)

1992-01-01

Three 'run-of-river' hydroelectric power plants in the Montreal area in the province of Quebec were described visually and in sound. A run-of-river generating station is one that has no reservoir behind the generating facilities. Instead of a reservoir, the generating station draws its power from the strong flow of the whole river as it passes through the turbines. The first generating station described was the Beauharnois power plant completed in 1963 which became the most powerful generating station in Canada at that time. Today, it ranks fourth after the La Grande complex. In winter, it supplies electricity primarily to the Quebec power system, but between April and November, 90 per cent of its power is destined for export. The Carillon power station on the Ottawa River, the second to be discussed in this videotape presentation, was completed in 1964 with a total generating capacity of 654 MW. Today, it is the tenth largest of its kind in Quebec. The Rivieres des Prairies generating station, the third and last one described was completed in 1930; today it has a generating capacity of 45 MW. Some of the efforts made by Hydro-Quebec to protect and enhance the natural environment were shown in action, including regular removal and recycling of debris at the gateways to the generating stations, construction of fish spawning ladders, and the control of zebra mussels

Nuclear plant life - A business decision

International Nuclear Information System (INIS)

Joosten, J.K.

1995-01-01

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

Owners of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hudson, C.R.; White, V.S.

1996-11-01

Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2000-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Advanced plant design recommendations from Cook Nuclear Plant experience

International Nuclear Information System (INIS)

Zimmerman, W.L.

1993-01-01

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

Elecnuc. Nuclear power plants worldwide

International Nuclear Information System (INIS)

1998-01-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-02-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-08-01

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

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

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

Operation and maintenance of nuclear power plants

International Nuclear Information System (INIS)

Ackermann, G.

1987-01-01

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

Impact of power plant KRSKO on the environment

International Nuclear Information System (INIS)

Hak, Nena; Lulic, Stipe

1993-01-01

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

Nuclear plant scram reduction

International Nuclear Information System (INIS)

Wiegle, H.R.

1986-01-01

The Nuclear Utility Management and Human Resources Committee (NUMARC) is a confederation of all 55 utilities with nuclear plants either in operation or under construction. NUMARC was formed in April 1984 by senior nuclear executives with hundreds of man-years of plant experience to improve (plant) performance and resolve NRC concerns. NUMARC has adopted 10 commitments in the areas of management, training, staffing and performance. One of these commitments is to strive to reduce automatic trips to 3 per year per unit for calendar year 1985 for plants in commercial operation greater than 3 years (with greater than 25% capacity factor). This goal applies to any unplanned automatic protection system trips at any time when the reactor is critical. Each utility has committed to develop methods to thoroughly evaluate all unplanned automatic trips to identify the root causes and formulate plans to correct the root causes thus reducing future unplanned scrams. As part of this program, the Institute of Nuclear Power Operations (INPO) collects and evaluates information on automatic reactor trips. It publishes the results of these evaluations to aid the industry to identify root causes and corrective actions

Effects of nuclear electromagnetic pulse (EMP) on nuclear power plants

International Nuclear Information System (INIS)

Barnes, P.R.; Manweiler, R.W.; Davis, R.R.

1977-09-01

The electromagnetic pulse (EMP) from a high-altitude nuclear detonation consists of a transient pulse of high intensity electromagnetic fields. These intense fields induce current and voltage transients in electrical conductors. Although most nuclear power plant cables are not directly exposed to these fields, the attenuated EMP fields that propagate into the plant will couple some EMP energy to these cables. The report predicts the probable effects of the EMP transients that could be induced in critical circuits of safety-related systems. It was found that the most likely consequence of EMP for nuclear plants is an unscheduled shutdown. EMP could prolong the shutdown period by the unnecessary actuation of certain safety systems. In general, EMP could be a nuisance to nuclear power plants, but it is not considered a serious threat to plant safety

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-09-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-12-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO 1 and II were in operation for almost the whole second quarter of 1991. The load factor average was 87.4 %. In consequence of a fire, which broke out in the switchgear building, connections to both external grids were lost and TVO II relied on power supplied by four back-up diesels for 7.5 hrs. The event is classified as Level 2 on the International Nuclear Event Scale. The process of examining the non-leaking fuel bundles removed from the Loviisa nuclear reactors has continued. The examinations have revealed, so far, that the uppermost spacing lattices of the bundles exhibit deformations similar to those detected in the leaking fuel bundles removed from the reactors. This event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale) on the Scale. The Finnish Centre for Radiation and Nuclear Safety has assessed the safety of the Loviisa and Olkiluoto nuclear power plants based on the new regulations issued on 14.2.1991 by the Council of State. The safety regulations are much more stringent than those in force when the Loviisa and Olkiluoto nuclear power plants were built. The assessment indicated that the TVO nuclear power plant meets these safety regulations. The Loviisa nuclear power plant meets the requirements with the exception of certain requirements related to the ensuring of safety functions and provision for accidents. At the Loviisa nuclear power plant there are several projects under consideration to enhance safety

Nuclear power plants maintenance

International Nuclear Information System (INIS)

Anon.

1988-01-01

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

Cooling towers of nuclear power plants

International Nuclear Information System (INIS)

Mikyska, L.

1986-01-01

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

The operation of nuclear power plants

International Nuclear Information System (INIS)

Brosche, D.

1992-01-01

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

4. Nuclear power plant component failures

International Nuclear Information System (INIS)

1990-01-01

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

Preparation and practice for nuclear power plant operation

International Nuclear Information System (INIS)

Wu Xuesong; Lu Tiezhong

2015-01-01

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

Streamflow variability and optimal capacity of run-of-river hydropower plants

Science.gov (United States)

Basso, S.; Botter, G.

2012-10-01

The identification of the capacity of a run-of-river plant which allows for the optimal utilization of the available water resources is a challenging task, mainly because of the inherent temporal variability of river flows. This paper proposes an analytical framework to describe the energy production and the economic profitability of small run-of-river power plants on the basis of the underlying streamflow regime. We provide analytical expressions for the capacity which maximize the produced energy as a function of the underlying flow duration curve and minimum environmental flow requirements downstream of the plant intake. Similar analytical expressions are derived for the capacity which maximize the economic return deriving from construction and operation of a new plant. The analytical approach is applied to a minihydro plant recently proposed in a small Alpine catchment in northeastern Italy, evidencing the potential of the method as a flexible and simple design tool for practical application. The analytical model provides useful insight on the major hydrologic and economic controls (e.g., streamflow variability, energy price, costs) on the optimal plant capacity and helps in identifying policy strategies to reduce the current gap between the economic and energy optimizations of run-of-river plants.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-06-01

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

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Nuclear plant life extension

International Nuclear Information System (INIS)

Negin, C.A.

1989-01-01

The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

NUCLEAR POWER PLANT

Science.gov (United States)

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

1963-05-14

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

Thermal insulation system design and fabrication specification (nuclear) for the Clinch River Breeder Reactor plant

International Nuclear Information System (INIS)

1978-01-01

This specification defines the design, analysis, fabrication, testing, shipping, and quality requirements of the Insulation System for the Clinch River Breeder Reactor Plant (CRBRP), near Oak Ridge, Tennessee. The Insulation System includes all supports, convection barriers, jacketing, insulation, penetrations, fasteners, or other insulation support material or devices required to insulate the piping and equipment cryogenic and other special applications excluded. Site storage, handling and installation of the Insulation System are under the cognizance of the Purchaser

QA programs in nuclear power plants

International Nuclear Information System (INIS)

Ellingson, A.C.

1976-01-01

As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

The distribution of tritium in the terrestrial and aquatic environments of the Creys-Malville nuclear power plant (2002-2005)

International Nuclear Information System (INIS)

Jean-Baptiste, P.; Baumier, D.; Fourre, E.; Dapoigny, A.; Clavel, B.

2007-01-01

The Creys-Malville nuclear plant, located on the left bank of the Rhone, was shut down in 1998. The facilities are currently in their initial stage of dismantling. In order to establish a baseline for tritium in the vicinity of the site prior to the main dismantling phase, we carried out a monitoring program between 2002 and 2005 in the main terrestrial and aquatic compartments of the local environment. Tritium levels in the groundwaters and in the Rhone waters correspond to the regional tritium concentration in precipitation. The data obtained for the terrestrial environment are also in good agreement with the regional background and do not show any specific signature linked to the nuclear plant. The various aquatic compartments of the Rhone (fish, plant, sediment) are significantly enriched in tritium both upstream and downstream of the power plant: although Tissue-Free Water Tritium concentrations are in equilibrium with the river water, the non-exchangeable fraction of organic bound tritium in plants and fishes shows values which outpace the river water background by one to two orders of magnitude, and up to four to five orders of magnitude in the sediments. This tritium anomaly is not related to the nuclear plant, as it is already present at the Swiss border 100 km upstream of the site. Although fine particles of tritiated polystyrene entering the composition of the luminous paints used by the clock industry have been suspected on several occasions, the exact nature and the origin of this tritium source remain unknown and require further investigations

Atucha I nuclear power plant transients analysis

International Nuclear Information System (INIS)

Castano, J.; Schivo, M.

1987-01-01

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

Guidelines for nuclear plant response to an earthquake

International Nuclear Information System (INIS)

1989-12-01

Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. The objectives of the earthquake response procedures are to determine (1) the immediate effects of an earthquake on the physical condition of the nuclear power plant, (2) if shutdown of the plant is appropriate based on the observed damage to the plant or because the OBE has been exceeded, and (3) the readiness of the plant to resume operation following shutdown due to an earthquake. Readiness of a nuclear power plant to restart is determined on the basis of visual inspections of nuclear plant equipment and structures, and the successful completion of surveillance tests which demonstrate that the limiting conditions for operation as defined in the plant Technical Specifications are met. The guidelines are based on information obtained from a review of earthquake response procedures from numerous US and foreign nuclear power plants, interviews with nuclear plant operations personnel, and a review of reports of damage to industrial equipment and structures in actual earthquakes. 7 refs., 4 figs., 4 tabs

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

International Nuclear Information System (INIS)

Demick, L.E.

2011-01-01

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

Energy Technology Data Exchange (ETDEWEB)

L.E. Demick

2011-10-01

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

Medium-size nuclear plants

International Nuclear Information System (INIS)

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

1977-01-01

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

Analysis of color environment in nuclear power plants

International Nuclear Information System (INIS)

Natori, Kazuyuki; Akagi, Ichiro; Souma, Ichiro; Hiraki, Tadao; Sakurai, Yukihiro.

1996-01-01

This article reports the results of color and psychological analysis of the outlook of nuclear power plants and the visual environments inside of the plants. Study one was the color measurements of the outlook of nuclear plants and the visual environment inside of the plants. Study two was a survey of the impressions on the visual environments of nuclear plants obtained from observers and interviews of the workers. Through these analysis, we have identified the present state of, and the problems of the color environments of the nuclear plants. In the next step, we have designed the color environments of inside and outside of the nuclear plants which we would recommend (inside designs were about fuel handling room, operation floor of turbine building, observers' pathways, central control room, rest room for the operators). Study three was the survey about impressions on our design inside and outside of the nuclear plants. Nuclear plant observers, residents in Osaka city, residents near the nuclear plants, the operators, employees of subsidiary company and the PR center guides rated their impressions on the designs. Study four was the survey about the design of the rest room for the operators controlling the plants. From the results of four studies, we have proposed some guidelines and problems about the future planning about the visual environments of nuclear power plants. (author)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-03-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-12-01

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

Modelling of nuclear power plant decommissioning financing.

Science.gov (United States)

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

2015-06-01

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

Run-of-river power plants in Alpine regions: whither optimal capacity?

Science.gov (United States)

Lazzaro, Gianluca; Botter, Gianluca

2015-04-01

Hydropower is the major renewable electricity generation technology worldwide. The future expansion of this technology mostly relies on the development of small run-of-river projects, in which a fraction of the running flows is diverted from the river to a turbine for energy production. Even though small hydro inflicts a smaller impact on aquatic ecosystems and local communities compared to large dams, it cannot prevent stresses on plant, animal, and human well-being. This is especially true in mountain regions where the plant outflow is located several kilometers downstream of the intake, thereby inducing the depletion of river reaches of considerable length. Moreover, the negative cumulative effects of run-of-river systems operating along the same river threaten the ability of stream networks to supply ecological corridors for plants, invertebrates or fishes, and support biodiversity. Research in this area is severely lacking. Therefore, the prediction of the long-term impacts associated to the expansion of run-of-river projects induced by global-scale incentive policies remains highly uncertain. This contribution aims at providing objective tools to address the preliminary choice of the capacity of a run-of-river hydropower plant when the economic value of the plant and the alteration of the flow regime are simultaneously accounted for. This is done using the concepts of Pareto-optimality and Pareto-dominance, which are powerful tools suited to face multi-objective optimization in presence of conflicting goals, such as the maximization of the profitability and the minimization of the hydrologic disturbance induced by the plant in the river reach between the intake and the outflow. The application to a set of case studies belonging to the Piave River basin (Italy) suggests that optimal solutions are strongly dependent the natural flow regime at the plant intake. While in some cases (namely, reduced streamflow variability) the optimal trade-off between economic

World nuclear power plant capacity

International Nuclear Information System (INIS)

1991-01-01

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

Development of nuclear power plant Risk Monitor

International Nuclear Information System (INIS)

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

2014-01-01

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

Nuclear engineering R ampersand D at the Savannah River Site

International Nuclear Information System (INIS)

Strosnider, D.R.; Ferrara, W.R.

1991-01-01

The Westinghouse Savannah River Company (WSRC) is the prime operating contractor for the US Department of Energy at the Savannah River Site (SRS), located near Aiken, South Carolina. One division of WSRC, the Savannah River Laboratory (SRL), has the primary responsibility for research and development, which includes supporting the safe and efficient operation of the SRS production reactors. Several Sections of SRL, as well as other organization in WSRC, pursue R ampersand D and oversight activities related to nuclear engineering. The Sections listed below are described in more detail in this document: (SRL) nuclear reactor technology and scientific computations department; (SRL) safety analysis and risk management department; (WSRC) new production reactor program; and (WSRC) environment, safety, health, and quality assurance division

Aquatic emergency response model at the Savannah River Plant

International Nuclear Information System (INIS)

Hayes, D.W.

1987-01-01

The Savannah River Plant emergency response plans include a stream/river emergency response model to predict travel times, maximum concentrations, and concentration distributions as a function of time at selected downstream/river locations from each of the major SRP installations. The menu driven model can be operated from any of the terminals that are linked to the real-time computer monitoring system for emergency response

HVDC transmission from nuclear power plant

International Nuclear Information System (INIS)

Yoshida, Yukio; Takenaka, Kiyoshi; Taniguchi, Haruto; Ueda, Kiyotaka

1980-01-01

HVDC transmission directly from a nuclear power plant is expected as one of the bulk power transmission systems from distant power generating area. Successively from the analysis of HVDC transmission from BWR-type nuclear power plant, this report discusses dynamic response characteristics of HVDC transmission (double poles, two circuits) from PWR type nuclear power plant due to dc-line faults (DC-1LG, 2LG) and ac-line faults (3LG) near inverter station. (author)

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

International Nuclear Information System (INIS)

Liu Wangtian

2005-01-01

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

Safety criteria for nuclear chemical plants

International Nuclear Information System (INIS)

Ball, P.W.; Curtis, L.M.

1983-01-01

Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

Development on database for foreign nuclear power plants

International Nuclear Information System (INIS)

Okuda, Yasunori; Yanagi, Chihiro

1999-01-01

The Nuclear Information Project in Institute of Nuclear Technology, Institute of Nuclear Safety Systems, Inc. (INSS) has been carrying out two activities related to technical information about nuclear power plants. The first is collection and analysis of accidents and incidents (troubles) of nuclear power plants in U.S.A. and West Europe and making draft of action proposals. The second is collection of main laws, government ordinances, regulatory guides, standard and domestic and international technical news connected with nuclear power plants. This report describes these two data bases about nuclear power plants details. (author)

Chemistry management system for nuclear power plants

International Nuclear Information System (INIS)

Nagasawa, Katsumi; Maeda, Katsuji

1998-01-01

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

Life management plants at nuclear power plants PWR; Planes de gestion de vida en centrales nucleares PWR

Energy Technology Data Exchange (ETDEWEB)

Esteban, G.

2014-10-01

Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

Technical descriptions of Hudson River electricity generating stations

International Nuclear Information System (INIS)

Hutchison, J.B.

1988-01-01

Six fossil-fueled and one nuclear electricity generating plants are sited along the Hudson River estuary between kilometers 8 and 228, measured from the river mouth. Their aggregate rated capacity is 5,798 MW of electricity; operating at that capacity they would withdraw cooling water from the river at the rate of 1.5 x 10 to the 9th power cu m/d and reject heat at the rate of 155 x 10 to the 9th power kcal/d. Three of these plants, the fossil-fueled Roseton and Bowline and the nuclear Indian Point facilities; account for 75% of total rated capacity, 62% of maximum water withdrawal, and 79% of potential heat rejection. These three plants and a proposed pumped-storage facility at Cornwall, all sited between km 60 and 106, were the focus of environmental litigation. The Indian Point plant normally operates at 100% generation capacity; the other plants may experience daily operating load changes that vary from approximately 50% to 100% of total generation capacity, depending on system electrical demand or economic considerations. All plants experience periodic unscheduled outages for repairs. 6 refs., 7 figs

Nuclear power plant V-1

International Nuclear Information System (INIS)

1998-01-01

The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

Man and nuclear power plants

International Nuclear Information System (INIS)

Anon.

1978-01-01

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

75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

Science.gov (United States)

2010-04-01

... Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC... the Perry Nuclear Power Plant, Unit 1 (PNPP). The license provides, among other things, that the... date for all operating nuclear power plants, but noted that the Commission's regulations provide...

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-09-01

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

Challenges for new nuclear plants

International Nuclear Information System (INIS)

Bruschi, H.J.

2000-01-01

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

Safety culture in nuclear power plants

International Nuclear Information System (INIS)

Weihe, G. von; Pamme, H.

2003-01-01

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

Elecnuc - Nuclear power plants in the world - 2009 edition

International Nuclear Information System (INIS)

2009-01-01

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

ELECNUC Nuclear power plants in the world - 2013 edition

International Nuclear Information System (INIS)

2013-01-01

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

Risk assessment for nuclear processes at the Savannah River Site

International Nuclear Information System (INIS)

Durant, W.S.

1992-01-01

The Savannah River Site, one of the US Department of Energy's nuclear materials processing facilities, has for many years conducted risk-based safety analyses for the nuclear processes conducted at the facilities. This approach has allowed comparisons of risks to established criteria for acceptability. When the risk-based program was begun, it was evident that its success would depend upon having a compilation of data that was site specific. The decision was made to create a data bank of undesirable events that had occurred at the site's nuclear fuel reprocessing facilities. From this modest beginning, five data banks have been created for nuclear fuel reprocessing, waste management, nuclear fuel fabrication, tritium operations, and the Savannah River Technology Center. In addition to the primary purpose of providing a sound basis for risk-based safety analyses, these highly versatile data banks are routinely used for equipment breakdown histories, incident investigations, design studies, project justifications, reliability studies, process problem solving, training, and audits

Solidification of Savannah River Plant high level waste

International Nuclear Information System (INIS)

Maher, R.; Shafranek, L.F.; Kelley, J.A.; Zeyfang, R.W.

1981-11-01

Authorization for construction of the Defense Waste Processing Facility (DWPF) is expected in FY 83. The optimum time for stage 2 authorization is about three years later. Detailed design and construction will require approximately five years for stage 1, with stage 2 construction completed about two to three years later. Production of canisters of waste glass would begin in 1988, and the existing backlog of high level waste sludge stored at SRP would be worked off by about the year 2000. Stage 2 operation could begin in 1990. The technology and engineering are ready for construction and eventual operation of the DWPF for immobilizing high level radioactive waste at Savannah River Plant (SRP). Proceeding with this project will provide the public, and the leadership of this country, with a crucial demonstration that a major quantity of existing high level nuclear wastes can be safely and permanently immobilized. Early demonstration will both expedite and facilitate rational decision making on this aspect of the nuclear program. Delay in providing these facilities will result in significant DOE expenditures at SRP for new tanks just for continued temporary storage of wastes, and would probably result in dissipation of the intellectual and planning momentum that has built up in developing the project

Implication of dual-purpose nuclear desalination plants

International Nuclear Information System (INIS)

Kutbi, I.I.

1983-01-01

Available dual purpose nuclear desalination schemes are reviewed. Three specific issues namely, impact of availability and reliability of the desalination stage of the plant, integration of the desalination and power production stages and new safety concerns of dual system, relating to desalination schemes are discussed. Results of operational and reliability studies of nuclear power stations, reverse osmosis and multistage flash distillation desalination plants are considered. Operational aspects of nuclear-multistage flash distillation, nuclear-reverse osmosis and nuclear-multistage flash distillation-reverse osmosis are compared. Concludes that the combined nuclear-multistage flash distillation-reverse osmosis plant arrangement permits very large production capacity, high availability, improvement of plant reliability and proovision of savings on the cost of water and power produced. 23 Ref

Indian Point Nuclear Generating Plant Unit No. 3 (Docket No. 50-286): Final environmental statement: Volume 2

International Nuclear Information System (INIS)

1975-02-01

This document contains nine appendices to Volume I, The Final Environmental Impact Statement for the Indian Point Nuclear Generating Plant Unit Number Three. Topics covered include thermal discharges to the Hudson River; supplemental information relating to biological models; radiation effects on aquatic biota; conditions, assumptions, and parameters used in calculating radioactive releases; meteorology for radiological dispersion calculations; life history information of important fish species in the Hudson River near Indian Point; additional information on cooling towers considered as alternatives; data and calculations for assessment of predicted electrical demand; and comments on draft environmental statement

The distribution of plutonium, americium and curium isotopes in pond and stream sediments of the Savannah River Plant, South Carolina, USA

International Nuclear Information System (INIS)

Alberts, J.J.; Halverson, J.E.; Orlandini, K.A.

1986-01-01

The concentrations of 238 Pu, 239 , 240 Pu, 241 Am and 244 Cm were determined in sediment samples from five streams and two ponds on the Savannah River Plant (SRP) and in four sediment samples from the Savannah River above and below the plant site. The following concentration ranges were determined: 238 Pu, 0.07-386 fCi g -1 ; 239 , 240 Pu, 0.37-1410 fCi g -1 ; 241 Am, 0.1-4360 fCi g -1 ; 244 Cm, -1 . Comparisons of the elemental and isotopic ratios of the sediments show that the majority of the sediments studied have been impacted upon by plant operations and that sediments outside the plant boundary in the Savannah River have only been influenced by aerial releases. Atom ratios of 240 Pu/ 239 Pu indicate that up to 86% of the Pu in these sediments is derived from plant operations. However, comparisons of the concentration data with values for other impacted sediments near nuclear facilities indicate that the levels are relatively small. Finally, <13% of the Pu, Am or Cm in pond sediments is associated with humic or fulvic acids, indicating that little of the material should be remobilized in oxic environments through organic complexation. (author)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-12-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations related to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing plant modifications and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and their load factors are also given. At the Loviisa 1 plant unit one of two specially-backed AC busbars was lost during the second quarter of 1993. A ca. 30 minute voltage break caused malfunctions in the plant unit's electrical equipment and rendered inoperable certain components important to safety. The event is rated on the International Nuclear Event Scale (INES) at level 1. In inspections carried out at TVO II during the annual maintenance outage, the number of cracks detected in control rod structural material was higher than usual. When cracks occur, part of boron carbide, the power regulating medium in control rods, may wash into the reactor water and control rod shutdown capability may be impaired. The event is rated on the INES at level 1. Other events in the second quarter of 1993 had no bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

The effect of radioactive contamination of the Yenisei river on cytogenetic characteristics of aquatic plants

Energy Technology Data Exchange (ETDEWEB)

Bolsunovsky, A.; Medvedeva, M. [Institute of Biophysics SB Russian Academy of Sciences (Russian Federation); Muratova, E. [Institute of Forest SB Russian Academy of Sciences (Russian Federation)

2014-07-01

areas (4-6%). The cytogenetic investigations of aquatic plants collected in the area affected by the MCC in 2011-12 also showed a significantly higher frequency of chromosomal aberrations in ana-telophase cells compared to the control samples. The frequency of chromosomal aberrations in the cells of aquatic plants in the control areas has remained nearly the same for almost a decade. The frequency of aberrant ana-telophases in Elodea canadensis cells has been found to be positively correlated to the total activity of artificial γ-radionuclides in Yenisei sediments of the study area and to {sup 137}Cs concentration in the sediments. The range of chromosomal aberrations in cells of Elodea collected in the area affected by the MCC was wider than in cells of the plant samples collected in the control areas (there were ring chromosomes and residual nucleoli in dividing cells). These data suggest that the radiation factor still affects the Yenisei River ecosystem, even several years after the MCC nuclear reactor was shut down. The possible reasons for this may be both discharges of the MCC Radiochemical Plant, which is still operating, and the effect of artificial radionuclides accumulated in sediments on submerged plants. Document available in abstract form only. (authors)

Nuclear power plants: 2009 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2010-01-01

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

Nuclear power plants: 2008 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2009-01-01

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

Fire scenarios in nuclear power plant

International Nuclear Information System (INIS)

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

1978-01-01

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

Ventilation-air conditioner system in nuclear power plant

International Nuclear Information System (INIS)

Kubota, Ryuji; Sugisaki, Toshihiko.

1989-01-01

This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

Vital areas at nuclear power plants

International Nuclear Information System (INIS)

Cameron, D.F.

1985-01-01

Vital area analysis of nuclear power plants has been performed for the Nuclear Regulatory Commission by the Los Alamos National Laboratory from the late 1970's through the present. The Los Alamos Vital Area Study uses a fault-tree modeling technique to identify vital areas and equipment at nuclear power plants to determine their vulnerability. This technique has been applied to all operating plants and approximately one-half of those under construction in the US. All saboteur-induced loss-of-coolant accidents and transients and the systems needed to mitigate them are considered. As a result of this effort, security programs at nuclear power plants now include vulnerability studies that identify targets in a systematic manner, and thus unnecessary protection has been minimized. 1 ref., 8 figs., 1 tab

78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

Science.gov (United States)

2013-06-27

... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

Savannah River Plant incinerator demonstration

International Nuclear Information System (INIS)

Lewandowski, K.E.

1983-01-01

A full-scale incineration process was demonstrated at the Savannah River Laboratory (SRL) using nonradioactive waste. From October 1981 through September 1982, 15,700 kilograms of solid waste and 5.7 m 3 of solvent were incinerated. Emissions of off-gas components (NO/sub x/, SO 2 , CO, and particulates) were well below South Carolina state standards. Volume reductions of 20:1 for solid waste and 7:1 for Purex solvent/lime slurry were achieved. The process has been relocated and upgraded by the Savannah River Plant to accept low-level beta-gamma combustibles. During a two-year demonstration, the facility will incinerate slightly radioactive ( 3 ) solvent and suspect level (< 1 mR/h at 0.0254 meter) solid wastes. This demonstration will begin in early 1984

China’s Nuclear Power Plants in Operation

Institute of Scientific and Technical Information of China (English)

无

2011-01-01

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

Commissioning of the nuclear power plant

International Nuclear Information System (INIS)

Furtado, P.M.; Rolf, F.

1984-01-01

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

Partner of nuclear power plants

International Nuclear Information System (INIS)

Gribi, M.; Lauer, F.; Pauli, W.; Ruzek, W.

1992-01-01

Sulzer, the Swiss technology group, is a supplier of components and systems for nuclear power plants. Important parts of Swiss nuclear power stations, such as containments, reactor pressure vessels, primary pipings, are made in Winterthur. Sulzer Thermtec AG and some divisions of Sulzer Innotec focus their activities on servicing and backfitting nuclear power plants. The European market enjoys priority. New types of valves or systems are developed as economic solutions meeting more stringent criteria imposed by public authorities or arising from operating conditions. (orig.) [de

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-08-01

During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

Environmental monitoring in the vicinity of the Savannah River Plant. Annual report, 1980

International Nuclear Information System (INIS)

1980-01-01

An extensive surveillance program has been continuously maintained since 1951 to determine the concentrations of radonuclides in a 1200-square-mile area in the environs of the plant and the radiation exposure of the population resulting from SRP operations. The results of this monitoring program are reported annually to the public. This document summarizes the 1980 results. The radiation dose at the plant perimeter and the population dose in the region from SRP operations is very small relative to the dose received from naturally occurring radiation. The annual average dose in 1980 from atmospheric releases of radioactive materials from SRP was 0.7 millirem at the plant perimeter. The maximum dose at the plant perimeter was 1.01 mrem, which is 0.2% of the Department of Energy limit for offsite exposures. The population dose to people living within 80 km of the center of SRP was 99.7 man-rems. During 1980, this same population received a radiation dose of 54,400 man-rems from natural radiation and an additional dose of 47,000 man-rems from medical x-rays. An individual consuming river water downstream from SRP would receive a maximum calculated dose in 1980 of 0.22 mrem which includes dose contributions from consumer products produced using Savannah River water. Air and water are the major dispersal media for radioactive emissions. Samples representing most segments of the environment that may conceivably be affected by these emissions were monitored to ensure a safe environment. Releases of radioactivity from SRP had an inconsequential effect on living plants and animals. With a few exceptions, concentrations outside the plant boundary were too low to distinguish from the natural radioactive background and continuing worldwide fallout from nuclear weapons tests

The safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

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

Countermeasures to earthquakes in nuclear plants

International Nuclear Information System (INIS)

Sato, Kazuhide

1979-01-01

The contribution of atomic energy to mankind is unmeasured, but the danger of radioactivity is a special thing. Therefore in the design of nuclear power plants, the safety has been regarded as important, and in Japan where earthquakes occur frequently, the countermeasures to earthquakes have been incorporated in the examination of safety naturally. The radioactive substances handled in nuclear power stations and spent fuel reprocessing plants are briefly explained. The occurrence of earthquakes cannot be predicted effectively, and the disaster due to earthquakes is apt to be remarkably large. In nuclear plants, the prevention of damage in the facilities and the maintenance of the functions are required at the time of earthquakes. Regarding the location of nuclear plants, the history of earthquakes, the possible magnitude of earthquakes, the properties of ground and the position of nuclear plants should be examined. After the place of installation has been decided, the earthquake used for design is selected, evaluating live faults and determining the standard earthquakes. As the fundamentals of aseismatic design, the classification according to importance, the earthquakes for design corresponding to the classes of importance, the combination of loads and allowable stress are explained. (Kako, I.)

Nuclear reactor kinetics and plant control

CERN Document Server

Oka, Yoshiaki

2013-01-01

Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. The first part focuses on understanding fundamental nuclear kinetics. It introduces delayed neutrons, fission chain reactions, point kinetics theory, reactivit

Flambeau River Biofuels Demonstration Plant

Energy Technology Data Exchange (ETDEWEB)

Byrne, Robert J. [Flambeau River Biofuels, Inc., Park Falls, WI (United States)

2012-07-30

Flambeau River BioFuels, Inc. (FRB) proposed to construct a demonstration biomass-to-liquids (BTL) biorefinery in Park Falls, Wisconsin. The biorefinery was to be co-located at the existing pulp and paper mill, Flambeau River Papers, and when in full operation would both generate renewable energy – making Flambeau River Papers the first pulp and paper mill in North America to be nearly fossil fuel free – and produce liquid fuels from abundant and renewable lignocellulosic biomass. The biorefinery would serve to validate the thermochemical pathway and economic models for BTL production using forest residuals and wood waste, providing a basis for proliferating BTL conversion technologies throughout the United States. It was a project goal to create a compelling new business model for the pulp and paper industry, and support the nation’s goal for increasing renewable fuels production and reducing its dependence on foreign oil. FRB planned to replicate this facility at other paper mills after this first demonstration scale plant was operational and had proven technical and economic feasibility.

Elecnuc. Nuclear power plants in the world. 1997

International Nuclear Information System (INIS)

Maubacq, F.; Tailland, C.

1997-04-01

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

Nuclear plant aging research program

International Nuclear Information System (INIS)

Eissenberg, D.M.

1987-01-01

The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

Decommissioning and back working of Greifswald nuclear power plant

International Nuclear Information System (INIS)

Rittscher, D.; Leushacke, D.F.; Meyer, R.

1998-01-01

At Nuclear Power Plant Greifswald, the Energiewerke Nord are carrying out the presently world's largest decommissioning project. This requires the gathering up of experience from the operation of the nuclear power plants at Greifswald, the decommissioning of other nuclear power plants, waste management, project management and licensing procedures for the decommissioning of nuclear power plants. That confirmed that the back working of nuclear plants is not a technical problem but a challenge for project management and logistics. It shows that the dismantling and disposal of nuclear plants is an ordinary process in our economic life. (orig.) [de

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

1988-04-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Heimburger, H.

1988-08-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Ottosson, C.

1989-05-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Haenninen, R.; Koponen, H.; Nevander, O.; Paltemaa, R.; Poellaenen, I.; Rannila, P.; Valtonen, K.; Vilkamo, O.

1988-02-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Haenninen, R.

1988-09-01

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

Increasing reliability of nuclear energy equipment and at nuclear power plants

International Nuclear Information System (INIS)

Ochrana, L.

1997-01-01

The Institute of Nuclear Energy at the Technical University in Brno cooperates with nuclear power plants in increasing their reliability. The teaching programme is briefly described. The scientific research programme of the Department of Heat and Nuclear Power Energy Equipment in the field of reliability is based on a complex systematic concept securing a high level of reliability. In 1996 the Department prepared a study dealing with the evaluation of the maintenance system in a nuclear power plant. The proposed techniques make it possible to evaluate the reliability and maintenance characteristics of any individual component in a nuclear power plant, and to monitor, record and evaluate data at any given time intervals. (M.D.)

TVA's nuclear power plant experience

International Nuclear Information System (INIS)

Willis, W.F.

1979-01-01

This paper reviews TVA's nuclear power plant design and construction experience in terms of schedule and capital costs. The completed plant in commercial operation at Browns Ferry and six additional plants currently under construction represent the nation's largest single commitment to nuclear power and an ultimate investment of $12 billion by 1986. The presentation is made in three separate phases. Phase one will recapitulate the status of the nuclear power industry in 1966 and set forth the assumptions used for estimating capital costs and projecting project schedules for the first TVA units. Phase two describes what happened to the program in the hectic early 1979's in terms of expansion of scope (particularly for safety features), the dramatic increase in regulatory requirements, vendor problems, stretchout of project schedules, and unprecedented inflation. Phase three addresses the assumptions used today in estimating schedules and plant costs for the next ten-year period

Academic training for nuclear power plant operators

International Nuclear Information System (INIS)

Jones, D.W.

1982-01-01

In view of the increasing emphasis being placed upon academic training of nuclear power plant operators, it is important that institutions of higher education develop and implement programs which will meet the educational needs of operational personnel in the nuclear industry. Two primary objectives must be satisfied by these programs if they are to be effective in meeting the needs of the industry. One objective is for academic quality. The other primary objective is for programs to address the specialized needs of the nuclear plant operator and to be relevant to the operator's job. The Center for Nuclear Studies at Memphis State University, therefore, has developed a total program for these objectives, which delivers the programs, and/or appropriate parts thereto, at ten nuclear plant sites and with other plants in the planning stage. The Center for Nuclear Studies program leads to a Bachelor of Professional Studies degree in nuclear industrial operations, which is offered through the university college of Memphis State University

78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

Science.gov (United States)

2013-08-19

... Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station... that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee.... Fitzpatrick Nuclear Power Plant (Fitzpatrick), Vermont Yankee Nuclear Power Station (Vermont Yankee), and...

Cyber security issues imposed on nuclear power plants

International Nuclear Information System (INIS)

Kim, Do-Yeon

2014-01-01

Highlights: • Provide history of cyber attacks targeting at nuclear facilities. • Provide cyber security issues imposed on nuclear power plants. • Provide possible countermeasures for protecting nuclear power plants. - Abstract: With the introduction of new technology based on the increasing digitalization of control systems, the potential of cyber attacks has escalated into a serious threat for nuclear facilities, resulting in the advent of the Stuxnet. In this regard, the nuclear industry needs to consider several cyber security issues imposed on nuclear power plants, including regulatory guidelines and standards for cyber security, the possibility of Stuxnet-inherited malware attacks in the future, and countermeasures for protecting nuclear power plants against possible cyber attacks

Nuclear power plant insurance - experience and loss statistics

International Nuclear Information System (INIS)

Feldmann, J.; Dangelmaier, P.

1982-01-01

Nuclear power plants are treated separately when concluding insurance contracts. National insurance pools have been established in industrial countries, co-operating on an international basis, for insuring a nuclear power plant. In combined property insurance, the nuclear risk is combined with the fire risk. In addition, there are the engineering insurances. Of these, the one of significance for nuclear power plants is the machinery insurance, which can be covered on the free insurance market. Nuclear power plants have had fewer instances of damage than other, conventional installations. (orig.) [de

Human factors in nuclear power plants

International Nuclear Information System (INIS)

Hennig, J.; Bohr, E.

1976-04-01

This annotated bibliography is a first attempt to give a survey of the kind of literature which is relevant for the ergonomic working conditions in nuclear power plants. Such a survey seems to be useful in view of the fact that the 'factor human being' comes recently more and more to the fore in nuclear power plants. In this context, the necessity is often pointed out to systematically include our knowledge of the performance capacity and limits of human beings when designing the working conditions for the personnel of nuclear power plants. For this reason, the bibliography is so much intended for the ergonomics experts as for the experts of nuclear engineering. (orig./LN) [de

76 FR 40403 - R.E. Ginna Nuclear Power Plant, LLC, R.E. Ginna Nuclear Power Plant, R.E. Ginna Independent Spent...

Science.gov (United States)

2011-07-08

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-244; Docket No. 72-67] R.E. Ginna Nuclear Power Plant, LLC, R.E. Ginna Nuclear Power Plant, R.E. Ginna Independent Spent Fuel Storage Installation; Notice of... Facility Operating License No. DPR-18, for the R.E. Ginna Nuclear Power Plant (Ginna), currently held by R...

Advancements in nuclear plant maintenance programs

International Nuclear Information System (INIS)

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

1993-01-01

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

Emergency control centers for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1979-01-01

Guidance is provided for the development and implementation of emergency control centers for nuclear power plants, including nuclear plant control room, nuclear plant company headquarters, emergency control center, and nuclear plant alternate emergency control center. Requirements and recommendations are presented for the mission, communications, instrumentation and equipment associated with each type of control center. Decisional aids, manning requirements and resources are also given; the decision aids cover both the accident assessment and protective action areas. Both normal and alternate means of communications are considered. Off-site emergency control centers, although not covered in the strict sense by this standard, are considered in an appendix

SWOT of nuclear power plant sustainable development

International Nuclear Information System (INIS)

Abbaspour, M.; Ghazi, S.

2008-01-01

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

Lessons learned from the licensing process for the Clinch River Breeder Reactor Plant

International Nuclear Information System (INIS)

Dickson, P.W.; Clare, G.H.

1991-01-01

This paper presents the experience of licensing a specific liquid-metal fast breeder reactor (LMFBR), the Clinch River Breader Reactor Plant (CRBRP). It was a success story in that the licensing process was accomplished in a very short time span. The actions of the applicant and the actions of the US Nuclear Regulatory Commission (NRC) in response are presented and discussed to provide guidance to future efforts to license unconventional reactors. The history is told from the perspective of the authors. As such, some of the reasons given for success or lack of success are subjective interpretations. Nevertheless, the authors' positions provided them an excellent viewpoint to make these judgements. During the second phase of the licensing process, they were the CRBRP Technical Director and the Licensing Manager, respectively, for the Westinghouse Electric Corporation, the prime contractor for the reactor plant

Slovak Electric, plc, Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

1999-01-01

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

Millstone nuclear power plant emergency system assessment

International Nuclear Information System (INIS)

Akhmad Khusyairi

2011-01-01

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

Safety Assessment - Swedish Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kjellstroem, B. [Luleaa Univ. of Technology (Sweden)

1996-12-31

After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs.

Safety Assessment - Swedish Nuclear Power Plants

International Nuclear Information System (INIS)

Kjellstroem, B.

1996-01-01

After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs

Publication of the planned erection and operation of a nuclear power plant near the town of Lingen, Emsland

International Nuclear Information System (INIS)

Anon.

1979-01-01

The nuclear power plant site is planned in the south Lingen industrial park in field 5 of the Darme district and in fields 34 and 35 of the Bramsche district, about 0.6 km nortn-east of the section between kilometers 139 and 140 of the Dortmund-Ems canal which shares the river bed of the Ems in this section. The nuclear power plant will have a PWR with a thermal power of 3765 MW, i.e. an electrical gross power of 1291 MWe during normal operation under design conditions. Heat removal from the turbine condenser will take place in closed recirculation cooling operation via a natural-draught cooling tower. (orig.) [de

Preliminary regulatory assessment of nuclear power plants vulnerabilities

International Nuclear Information System (INIS)

Kostadinov, V.; Petelin, S.

2004-01-01

Preliminary attempts to develop models for nuclear regulatory vulnerability assessment of nuclear power plants are presented. Development of the philosophy and computer tools could be new and important insight for management of nuclear operators and nuclear regulatory bodies who face difficult questions about how to assess the vulnerability of nuclear power plants and other nuclear facilities to external and internal threats. In the situation where different and hidden threat sources are dispersed throughout the world, the assessment of security and safe operation of nuclear power plants is very important. Capability to evaluate plant vulnerability to different kinds of threats, like human and natural occurrences and terrorist attacks and preparation of emergency response plans and estimation of costs are of vital importance for assurance of national security. On the basis of such vital insights, nuclear operators and nuclear regulatory bodies could plan and optimise changes in oversight procedures, organisations, equipment, hardware and software to reduce risks taking into account security and safety of nuclear power plants operation, budget, manpower, and other limitations. Initial qualitative estimations of adapted assessments for nuclear applications are shortly presented. (author)

Problems in Siting Nuclear Power Plants in Japan and Efforts to Solve Them

Energy Technology Data Exchange (ETDEWEB)

Inouye, T. [Ministry of International Trade and Industry, Tokyo (Japan)

1967-09-15

The rapidly growing demand for energy in Japan will require a total capacity of 30 to 40 thousand MW(e) in nuclear power by 1985. Materialization of this development programme must naturally be supported by securing the requisite sites for the nuclear power plants. The following factors make siting of nuclear power plants more difficult in Japan than in any other country: a small, densely populated territory with little level land, that is already completely utilized for agricultural and/or industrial purposes; small rivers and an active marine-product industry developed along most of the seacoasts, both of which create difficult cooling-water problems; frequent earthquakes; and the fear of possible radioactivity, which prevails in the only nation in the world to have suffered from the atomic bomb. There are at present four nuclear power plants in operation or under construction in Japan with a total capacity of about 1.3 thousand MW(e). However, the plants in these construction programmes have been sited on the basis of taking the easiest course available although there were several possible solutions to choose from. It is pointed out here that the long-range nuclear power development programme will call for a fundamental solution to enable siting a large number of power plants under the adverse conditions in Japan. Accordingly, a study was made, which included quantitative analyses of reactor siting factors and suggested measures for solving the siting problems. The analyses were based on nuclear power plant sites assumed to be located on the seacoast and characterized by low-population density, desirable geology and favourable topography. It was assumed that seacoast siting was more economical than inland siting. Although the study was made by a general survey using maps, it was shown that approximately 10% of the total coastline areas would be eligible for reactor siting, but most of these areas in this case are located in the northern part of Japan, far from

Loviisa nuclear power plant analyzer

International Nuclear Information System (INIS)

Porkholm, K.; Nurmilaukas, P.; Tiihonen, O.; Haenninen, M.; Puska, E.

1992-12-01

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

I and C upgrading at nuclear power plants

International Nuclear Information System (INIS)

Tamiri, A.

2003-01-01

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

Seismic reevaluation of existing nuclear power plants

International Nuclear Information System (INIS)

Hennart, J.C.

1978-01-01

The codes and regulations governing Nuclear Power Plant seismic analysis are continuously becoming more stringent. In addition, design ground accelerations of existing plants must sometimes be increased as a result of discovery of faulting zones or recording of recent earthquakes near the plant location after plant design. These new factors can result in augmented seismic design criteria. Seismic reanalysius of the existing Nuclear Power Plant structures and equipments is necessary to prevent the consequences of newly postulated accidents that could cause undue risk to the health or safety of the public. This paper reviews the developments of seismic analysis as applied to Nuclear Power Plants and the methods used by Westinghouse to requalify existing plants to the most recent safety requirements. (author)

Robotics for nuclear power plants

International Nuclear Information System (INIS)

Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

1984-01-01

Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics. (author)

Robotics for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

1984-10-01

Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics.

Nuclear Power Plant Technician

Science.gov (United States)

Randall, George A.

1975-01-01

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

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

International Nuclear Information System (INIS)

Matthes, Felix C.

2009-10-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-05-01

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

Maintenance planning for nuclear power plants

International Nuclear Information System (INIS)

Mattu, R.K.; Cooper, S.E.; Lauderdale, J.R.

2004-01-01

Maintenance planning for nuclear power plants is similar to that in other industrial plants but it is heavily influenced by regulatory rules, with consequent costs of compliance. Steps by the nuclear industry and the Nuclear Regulatory Commission to address that problem include development of guidelines for maintenance of risk-critical equipment, using PRA-based techniques to select a set of equipment that requires maintenance and reliability-centered maintenance (RCM) approaches for determining what maintenance is required. The result of the process is a program designed to ensure effective maintenance of the equipment most critical to plant safety. (author)

Safety assessment principles for nuclear plants

International Nuclear Information System (INIS)

1992-01-01

The present Safety Assessment Principles result from the revision of those which were drawn up following a recommendation arising from the Sizewell-B enquiry. The principles presented here relate only to nuclear safety; there is a section on risks from normal operation and accident conditions and the standards against which those risks are assessed. A major part of the document deals with the principles that cover the design of nuclear plants. The revised Safety assessment principles are aimed primarily at the safety assessment of new nuclear plants but they will also be used in assessing existing plants. (UK)

Qualification of nuclear power plant operations personnel

International Nuclear Information System (INIS)

1984-01-01

With the ultimate aim of reducing the possibility of human error in nuclear power plant operations, the Guidebook discusses the organizational aspects, the staffing requirements, the educational systems and qualifications, the competence requirements, the ways to establish, preserve and verify competence, the specific aspects of personnel management and training for nuclear power plant operations, and finally the particular situations and difficulties to be overcome by utilities starting their first nuclear power plant. An important aspect presented in the Guidebook is the experience in training and qualification of nuclear power plant personnel in various countries: Argentina, Belgium, Canada, Czechoslovakia, France, Federal Republic of Germany, Spain, Sweden, United Kingdom and United States of America

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

Occupational dose control in Nuclear Power Plants

International Nuclear Information System (INIS)

Viktorsson, C.; Lochard, J.; Benedittini, M.; Baum, J.; Khan, T.A.

1990-01-01

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

Economics and policies of nuclear plant life management

International Nuclear Information System (INIS)

Yamagata, H.

1998-01-01

NEA provides an opportunity for international exchange of information on the economics and policies of nuclear plant life management for governments and plant owners. The NEA Secretariat is finalising the 'state-of-the-art report' on the economics and policies of nuclear plant life management, including the model approach and national summaries. In order to meet power supply obligations in the early 2000, taking into account energy security, environmental impact, and the economics of nuclear power plants whose lives have been extended, initiatives at national level must be taken to monitor, co-ordinate, and support the various industry programmes of nuclear plant life management by integrated and consistent policies, public acceptance, R and D, and international co-operation. Nuclear power owners should establish an organisation and objectives to carry nuclear plant life management in the most economic and smoothest way taking into consideration internal and external influences. The organisation must identify the critical item and the ageing processes, and optimise equipment reliability and maintenance workload. (author)

German risk study 'nuclear power plants, phase B'

International Nuclear Information System (INIS)

Heuser, F.W.

1989-01-01

The results of the German risk study 'Nuclear power plants, phase B' indicate that an accident in a nuclear power plant which cannot be managed by the safety systems according to design, is extremely improbable: Its probability is at about 3 to 100,000 per year and plant. Even if the safety systems fail, emergency measures can be effected in a nuclear power plant to prevent an accident. These in-plant emergency measures diminish the probability of a core meltdown to about 4 to 1,000,000 per year and plant. Hence, the accident risk is greatly reduced. The information given by the author are to smooth the emotional edge in the discussion about the safety of nuclear power plants. (orig.) [de

Nuclear power plant decommissioning

International Nuclear Information System (INIS)

Yaziz Yunus

1986-01-01

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

Hydrologic alteration affects aquatic plant assemblages in an arid-land river

Science.gov (United States)

Vinson, Mark; Hestmark, Bennett; Barkworth, Mary E.

2014-01-01

We evaluated the effects of long-term flow alteration on primary-producer assemblages. In 1962, Flaming Gorge Dam was constructed on the Green River. The Yampa River has remained an unregulated hydrologically variable river that joins the Green River 100 km downstream from Flaming Gorge Dam. In the 1960s before dam construction only sparse occurrences of two macroalgae, Cladophora and Chara, and no submerged vascular plants were recorded in the Green and Yampa rivers. In 2009–2010, aquatic plants were abundant and widespread in the Green River from the dam downstream to the confluence with the Yampa River. The assemblage consisted of six vascular species, Elodea canadensis, Myriophyllum sibiricum, Nasturtium officinale,Potamogeton crispus, Potamogeton pectinatus, and Ranunculus aquatilis, the macroalgae Chara and Cladophora, and the bryophyte, Amblystegium riparium. In the Green River downstream from the Yampa River, and in the Yampa River, only sparse patches of Chara and Cladophora growing in the splash zone on boulders were collected. We attribute the observed changes in the Green River to an increase in water transparency and a reduction in suspended and bed-load sediment and high flow disturbances. The lack of hydrophyte colonization downstream from the confluence with the Yampa River has implications for understanding tributary amelioration of dam effects and for designing more natural flow-regime schedules downstream from large dams.

Nuclear power plant outage optimisation strategy

International Nuclear Information System (INIS)

2002-10-01

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

Nuclear regulation. License renewal questions for nuclear plants need to be resolved

International Nuclear Information System (INIS)

Fultz, Keith O.; Kruslicky, Mary Ann; McDowell, William D. Jr.; Coleman, Robert L.

1989-04-01

A December 1986 pipe rupture at Virginia Power's Surry unit 2 nuclear power plant injured eight workers; four later died. As a result of this accident, Representative Edward J. Markey requested GAO to examine the Surry accident and assess the problems confronting aging nuclear plants. In March 1988 we reported our findings concerning the accident and a July 1987 incident at the Trojan nuclear plant in Oregon. This report addresses problems confronting aging nuclear plants by examining the Nuclear Regulatory Commission's (NRC) program to develop a license renewal policy and accompanying regulations, and the initiatives underway by the Department of Energy (DOE) and the electric utility industry to extend the operating lives of these plants. Nuclear power has become second only to coal as the largest producer of electricity in the United States. The 110 nuclear plants currently in service are operated by 54 utilities, provide about 20 percent of the nation's electricity, and represent a capital investment of over $200 billion. The Atomic Energy Act authorizes NRC to issue nuclear plant operating licenses for up to 40 years and provides for license extensions beyond the initial operating period. The act does not, however, stipulate the criteria for evaluating a utility request to operate a nuclear plant longer than 40 years. The oldest operating license currently in effect will expire in the year 2000. According to NRC, about one-half of the existing operating licenses will terminate by the year 2015, and most licenses will expire by about 2030. Many utilities will have to decide in the early 1990s whether to continue operating older nuclear plants or to construct new generating capacity. A clear understanding of the terms and conditions governing the license renewal process will be a key element in deciding how to meet future electricity demand. Although NRC has developed 3 possible license renewal policy options and identified 15 areas of regulatory uncertainty that

Plant designer's view of the operator's role in nuclear plant safety

International Nuclear Information System (INIS)

Corcoran, W.R.; Church, J.F.; Cross, M.T.; Porter, N.J.

1981-01-01

The nuclear plant operator's role supports the design assumptions and equipment with four functional tasks. He must set up th plant for predictable response to disturbances, operate the plant so as to minimize the likelihood and severity of event initiators, assist in accomplishing the safety functions, and feed back operating experiences to reinforce or redefine the safety analyses' assumptions. The latter role enhances the operator effectiveness in the former three roles. The Safety Level Concept offers a different perspective that enables the operator to view his roles in nuclear plant safety. This paper outlines the operator's role in nuclear safety and classifies his tasks using the Safety Level Concept

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

International Nuclear Information System (INIS)

Matthes, Felix C.; Hermann, Hauke

2009-06-01

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

Robotics for nuclear power plants

International Nuclear Information System (INIS)

Nakayama, Ryoichi; Kimura, Motohiko; Abe, Akira

1993-01-01

A continuing need exists for automatic or remote-controlled machines or robots which can perform inspection and maintenance tasks in nuclear power plants. Toshiba has developed several types of monofunctional and multi- functional robots for such purposes over the past 20 years, some of which have already been used in actual plants. This paper describes new multifunctional robots for inspection and maintenance. An inspection robot has been applied in an actual plant for two years for performance testing. Maintenance robots for grinding tasks have also been developed, which can be easily teleoperated by the operator using automatic control. These new robots are expected to be applied to actual inspection and maintenance work in nuclear power plants. (author)

Affective imagery and acceptance of replacing nuclear power plants.

Science.gov (United States)

Keller, Carmen; Visschers, Vivianne; Siegrist, Michael

2012-03-01

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

Human factors in nuclear power plants

International Nuclear Information System (INIS)

Swain, A.D.

1981-01-01

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

ALARA at nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.

1991-01-01

Implementation of the ALARA principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed through a variety of dose reduction techniques. Initiatives by the ICRP, NCRP, NRC, INPO, EPRI, and BNL ALARA Center have all contributed to a heightened interest and emphasis on dose reduction. The NCRP has formed Scientific Committee 46-9 which is developing a report on ALARA at Nuclear Power Plants. It is planned that this report will include material on historical aspects, management, valuation of dose reduction ($/person-Sv), quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report

Worker Alienation and Compensation at the Savannah River Site.

Science.gov (United States)

Ashwood, Loka; Wing, Steve

2016-05-01

Corporations operating U.S. nuclear weapons plants for the federal government began tracking occupational exposures to ionizing radiation in 1943. However, workers, scholars, and policy makers have questioned the accuracy and completeness of radiation monitoring and its capacity to provide a basis for workers' compensation. We use interviews to explore the limitations of broad-scale, corporate epidemiological surveillance through worker accounts from the Savannah River Site nuclear weapons plant. Interviewees report inadequate monitoring, overbearing surveillance, limited venues to access medical support and exposure records, and administrative failure to report radiation and other exposures at the plant. The alienation of workers from their records and toil is relevant to worker compensation programs and the accuracy of radiation dose measurements used in epidemiologic studies of occupational radiation exposures at the Savannah River Site and other weapons plants. © The Author(s) 2016.

Defense Waste Processing Facility, Savannah River Plant

International Nuclear Information System (INIS)

After 10 years of research, development, and testing, the US Department of Energy is building a new facility which will prepare high-level radioactive waste for permanent disposal. The Defense Waste Processing Facility, known as the DWPF, will be the first production-scale facility of its kind in the United States. In the DWPF, high-level waste produced by defense activities at the Savannah River Plant will be processed into a solid form, borosilicate glass, suitable for permanent off-site geologic disposal. With construction beginning in the fall of 1983, the DWPT is scheduled to be operational in 1989. By 2005, the DWPF will have immobilized the backlog of high-level waste which has been accumulating in storage tanks at the Savannah River Plant since 1954. Canisters of the immobilized waste will then be ready for permanent disposal deep under the ground, safely isolated from the environment

Development and comparision of techniques for estimating design basis flood flows for nuclear power plants

International Nuclear Information System (INIS)

1980-05-01

Estimation of the design basis flood for Nuclear Power Plants can be carried out using either deterministic or stochastic techniques. Stochastic techniques, while widely used for the solution of a variety of hydrological and other problems, have not been used to date (1980) in connection with the estimation of design basis flood for NPP siting. This study compares the two techniques against one specific river site (Galt on the Grand River, Ontario). The study concludes that both techniques lead to comparable results , but that stochastic techniques have the advantage of extracting maximum information from available data and presenting the results (flood flow) as a continuous function of probability together with estimation of confidence limits. (author)

A common high standard for nuclear power plant exports: overview and analysis of the Nuclear Power Plant Exporters' Principles of Conduct

International Nuclear Information System (INIS)

Perkovich, George; Radzinsky, Brian

2012-01-01

At this time, there is no overarching global framework to regulate the development of the nuclear power industry. Laws concerning the export of nuclear technology vary across jurisdictions, and politically-binding arrangements such as the Nuclear Suppliers Group (NSG) help ensure that weapons-usable or dual-use technologies are not exported, but no single international regime or agreement manages the gamut of potential risks that may arise from the export of civilian nuclear power plants. Accordingly in 2008, the Carnegie Endowment for International Peace convened internationally-recognised experts in nuclear energy to begin a dialogue with nuclear power plant vendors about defining common criteria for the socially responsible export of nuclear power plants. The goal was to articulate a comprehensive set of principles and best practices that would raise the overall standard of practice for exports of nuclear power plants while enjoying widespread support and adherence. The outcome of this process is the Nuclear Power Plant Exporters' Principles of Conduct - an export-oriented code of conduct for nuclear power plant vendors. The Principles of Conduct help ensure that the participating companies will proceed with the sale of a new nuclear power plant only after a careful assessment of the legal, political, and technical contexts surrounding potential customers. It comprises six 'principles' that each address a major area of concern involved in the export of a nuclear power plant: safety, physical security, environmental protection and spent fuel management, systems of compensation for nuclear damage, non-proliferation and safeguards, and business ethics. The Principles of Conduct entail vendor responsibilities to apply specific standards or engage in certain practices before signing contracts and during the marketing and construction phases of a nuclear power plant export project. Conformity with the Principles of Conduct is voluntary and not-legally binding, but the

Do invasive alien plants really threaten river bank vegetation? A case study based on plant communities typical for Chenopodium ficifolium—An indicator of large river valleys

Science.gov (United States)

Nowak, Arkadiusz; Rola, Kaja

2018-01-01

Riparian zones are very rich in species but subjected to strong anthropogenic changes and extremely prone to alien plant invasions, which are considered to be a serious threat to biodiversity. Our aim was to determine the spatial distribution of Chenopodium ficifolium, a species demonstrating strong confinement to large river valleys in Central Europe and an indicator of annual pioneer nitrophilous vegetation developing on river banks, which are considered to be of importance to the European Community. Additionally, the habitat preferences of the species were analysed. Differences in the richness and abundance of species diagnostic for riverside habitats, as well as the contribution of resident and invasive alien species in vegetation plots along three rivers differing in terms of size and anthropogenic impact were also examined. Finally, the effect of invaders on the phytocoenoses typical for C. ficifolium was assessed. The frequency of C. ficifolium clearly decreased with an increasing distance from the river. Among natural habitats, the species mostly preferred the banks of large rivers. The vegetation plots developing on the banks of the three studied rivers differed in total species richness, the number and cover of resident, diagnostic and invasive alien species, as well as in species composition. Our research indicates that abiotic and anthropogenic factors are the most significant drivers of species richness and plant cover of riverbank vegetation, and invasive alien plants affect this type of vegetation to a small extent. PMID:29543919

Do invasive alien plants really threaten river bank vegetation? A case study based on plant communities typical for Chenopodium ficifolium-An indicator of large river valleys.

Science.gov (United States)

Nobis, Agnieszka; Nowak, Arkadiusz; Rola, Kaja

2018-01-01

Riparian zones are very rich in species but subjected to strong anthropogenic changes and extremely prone to alien plant invasions, which are considered to be a serious threat to biodiversity. Our aim was to determine the spatial distribution of Chenopodium ficifolium, a species demonstrating strong confinement to large river valleys in Central Europe and an indicator of annual pioneer nitrophilous vegetation developing on river banks, which are considered to be of importance to the European Community. Additionally, the habitat preferences of the species were analysed. Differences in the richness and abundance of species diagnostic for riverside habitats, as well as the contribution of resident and invasive alien species in vegetation plots along three rivers differing in terms of size and anthropogenic impact were also examined. Finally, the effect of invaders on the phytocoenoses typical for C. ficifolium was assessed. The frequency of C. ficifolium clearly decreased with an increasing distance from the river. Among natural habitats, the species mostly preferred the banks of large rivers. The vegetation plots developing on the banks of the three studied rivers differed in total species richness, the number and cover of resident, diagnostic and invasive alien species, as well as in species composition. Our research indicates that abiotic and anthropogenic factors are the most significant drivers of species richness and plant cover of riverbank vegetation, and invasive alien plants affect this type of vegetation to a small extent.

Nuclear plant license renewal

International Nuclear Information System (INIS)

Gazda, P.A.; Bhatt, P.C.

1991-01-01

During the next 10 years, nuclear plant license renewal is expected to become a significant issue. Recent Electric Power Research Institute (EPRI) studies have shown license renewal to be technically and economically feasible. Filing an application for license renewal with the Nuclear Regulatory Commission (NRC) entails verifying that the systems, structures, and components essential for safety will continue to perform their safety functions throughout the license renewal period. This paper discusses the current proposed requirements for this verification and the current industry knowledge regarding age-related degradation of structures. Elements of a license renewal program incorporating NRC requirements and industry knowledge including a schedule are presented. Degradation mechanisms for structural components, their significance to nuclear plant structures, and industry-suggested age-related degradation management options are also reviewed

Nuclear power plants 1995 - a world survey

International Nuclear Information System (INIS)

Anon.

1996-01-01

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

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

International Nuclear Information System (INIS)

1987-08-01

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

Quality assurance in nuclear power plant

International Nuclear Information System (INIS)

Magalhaes, M.T. de

1981-01-01

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

78 FR 55118 - Seismic Instrumentation for Nuclear Power Plants

Science.gov (United States)

2013-09-09

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0202] Seismic Instrumentation for Nuclear Power Plants... Reports for Nuclear Power Plants: LWR Edition,'' Section 3.7.4, ``Seismic Instrumentation.'' DATES: Submit... Nuclear Power Plants: LWR Edition'' (SRP, from the current Revision 2 to a new Revision 3). The proposed...

Nuclear power plant operation 2016. Pt. 1

Energy Technology Data Exchange (ETDEWEB)

Anon.

2017-05-15

A report is given on the operating results achieved in 2016, events important to plant safety, special and relevant repair, and retrofit measures from nuclear power plants in Germany. Reports about nuclear power plants in Belgium, Finland, the Netherlands, Switzerland, and Spain will be published in a further issue.

Clinch River Breeder Reactor Plant Project: construction schedule

International Nuclear Information System (INIS)

Purcell, W.J.; Martin, E.M.; Shivley, J.M.

1982-01-01

The construction schedule for the Clinch River Breeder Reactor Plant and its evolution are described. The initial schedule basis, changes necessitated by the evaluation of the overall plant design, and constructability improvements that have been effected to assure adherence to the schedule are presented. The schedule structure and hierarchy are discussed, as are tools used to define, develop, and evaluate the schedule

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

International Nuclear Information System (INIS)

Metke, E.

1984-01-01

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

Modifications at operating nuclear power plants

International Nuclear Information System (INIS)

Duffy, T.J.; Gazda, P.A.

1985-01-01

Modifications at operating nuclear power plants offer the structural engineer many challenges in the areas of scheduling of work, field adjustments, and engineering staff planning. The scheduling of structural modification work for operating nuclear power plants is normally closely tied to planned or unplanned outages of the plant. Coordination between the structural engineering effort, the operating plant staff, and the contractor who will be performing the modifications is essential to ensure that all work can be completed within the allotted time. Due to the inaccessibility of some areas in operating nuclear power plants or the short time available to perform the structural engineering in the case of an unscheduled outrage, field verification of a design is not always possible prior to initiating the construction of the modification. This requires the structural engineer to work closely with the contractor to promptly resolve problems due to unanticipated interferences or material procurement problems that may arise during the course of construction. The engineering staff planning for structural modifications at an operating nuclear power plant must be flexible enough to permit rapid response to the common ''fire drills,'' but controlled enough to ensure technically correct designs and to minimize the expenditure of man-hours and the resulting engineering cost

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-03-01

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

Nuclear power plant's safety and risk

International Nuclear Information System (INIS)

Franzen, L.F.

1975-01-01

Starting with a comprehensive safety strategy as evolved over the past years and the present legal provisions for the construction and operation of nuclear power plants, the risk of the intended operation, of accidents and unforeseen events is discussed. Owing to the excellent safety record of nuclear power plants, main emphasis in discussing accidents is given to the precautionary analysis within the framework of the licensing procedure. In this context, hypothetical accidents are mentioned only as having been utilized for general risk comparisons. The development of a comprehensive risk concept for a completely objective safety assessment of nuclear power plants remains as a final goal. (orig.) [de

Heat supply from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

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

1978-05-01

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

Information Technology for Nuclear Power Plant Configuration Management

International Nuclear Information System (INIS)

2010-07-01

Configuration management (CM) is an essential component of nuclear power plant design, construction and operation. The application of information technology (IT) offers a method to automate and ensure the timely and effective capture, processing and distribution of key nuclear power plant information to support CM principles and practical processes and procedures for implementation of CM at nuclear power plants. This publication reviews some of the principles established in IAEA-TECDOC-1335, 'Configuration Management in Nuclear Power Plants.' It also recaps tenets laid out in IAEA- TECDOC-1284, 'Information Technology Impact on Nuclear Power Plant Documentation' that supports CM programmes. This publication has been developed in conjunction with and designed to support these other two publications. These three publications combined provide a comprehensive discussion on configuration management, information technology and the relationship between them. An extensive discussion is also provided in this publication on the role of the design basis of the facility and its control through the CM process throughout the facility's lifetime. While this report was developed specifically for nuclear power plants, the principles discussed can be usefully applied to any high hazard nuclear facility

Nuclear power plant emergency preparedness

International Nuclear Information System (INIS)

2005-01-01

The guide sets forth detailed requirements on how the licensee of a nuclear power plant shall plan, implement and maintain emergency response arrangements. The guide is also applied to nuclear material and nuclear waste transport in situations referred to in guide YVL 6.5. Requirements on physical protection are presented in a separate guide of Finnish Radiation and Nuclear Safety Authority (STUK)

Seismic safety of nuclear power plants

International Nuclear Information System (INIS)

Guerpinar, A.; Godoy, A.

2001-01-01

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

Nuclear power plant

International Nuclear Information System (INIS)

Aisaka, Tatsuyoshi; Kamahara, Hisato; Yanagisawa, Ko.

1982-01-01

Purpose: To prevent corrosion stress cracks in structural materials in a BWR type nuclear power plant by decreasing the oxygen concentration in the reactor coolants. Constitution: A hydrogen injector is connected between the condensator and a condensate clean up system of a nuclear power plant. The injector is incorporated with hydrogenated compounds formed from metal hydrides, for example, of alloys such as lanthanum-nickel alloy, iron titanium alloy, vanadium, palladium, magnesium-copper alloy, magnesium-nickel alloy and the like. Even if the pressure of hydrogen obtained from a hydrogen bomb or by way of water electrolysis is changed, the hydrogen can always be injected into a reactor coolant at a pressure equal to the equilibrium dissociation pressure for metal hydride by introducing the hydrogen into the hydrogen injector. (Seki, T.)

Basic safety principles for nuclear power plant

International Nuclear Information System (INIS)

Zhang Shiguan

1989-01-01

To ensure the safety operation of nuclear power plant, one should strictly adhere to the implelmentation of safety codes and the establishment of nuclear safety code system, as well as the applicable basic safety principles of nuclear power plants. This article briefly introduce the importance of nuclear codes and its economic benefits and the implementation of basic safety principles to be accumulated in practice for many years by various countries

Fire prevention in nuclear power plants

International Nuclear Information System (INIS)

1993-01-01

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

Fire protection at nuclear power plants

International Nuclear Information System (INIS)

1999-11-01

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

Radioactive waste management for German nuclear power plants

International Nuclear Information System (INIS)

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

1996-01-01

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

Model and simulation of the hydraulic turbine speed regulator of the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Copparoni, G.; Etchepareborda, A.; Urrutia, G.

1992-01-01

The hydraulics turbines of Atucha I Nuclear Power Plant takes advantage of condenser cooling water level difference between the plant and the river to recover about 2,5 MW e. It also supplies emergency power until diesel generators start up. Speed regulation is needed due to the transients that during this process occur. The purpose is to minimize the diesels start up time, and to avoid overshoots on the internal grid frequency. The hydraulic turbine, its speed regulator and the electric system associated with this transient have been modeled. The models and some simulation results are presented in this work. (author)

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

International Nuclear Information System (INIS)

Feretic, Danilo; Cavlina, Nikola

2010-01-01

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

Docommissioning of nuclear power plants

International Nuclear Information System (INIS)

Essmann, J.

1981-01-01

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

Fire prevention in nuclear plants

International Nuclear Information System (INIS)

Cayla, J.P.; Jacquet-Francillon, J.; Matarozzo, F.

2014-01-01

About 80 fire starts are reported in EDF nuclear power plants every year but only 3 or 4 turn into a real fire and none has, so far, has led to a major safety failure of a nuclear plant. A new regulation has been implemented in july 2014 that strengthens the concept of defense in depth, proposes an approach that is proportionate to the stakes and risks, this proportionality means that the requirements for a power reactor are not the same as for a nuclear laboratory, and imposes an obligation or result rather than of means. The second article deals with the fire that broke out in the waste silo number 130 at La Hague plant in january 1981. The investigation showed that the flammability of the silo content had been underestimated. The third article presents the consequences of the fire that broke out in a power transformer at the Cattenom plant in june 2013. The fire was rapidly brought under control thanks to the immediate triggering of the emergency plan. The article details also the feedback experience of this event. (A.C.)

Investigation of cable deterioration in the containment building of the Savannah River Nuclear Reactor

International Nuclear Information System (INIS)

Gillen, K.T.; Clough, R.L.; Jones, L.H.

1982-08-01

This report describes an investigation of the deterioration of polyethylene and polyvinylchloride cable materials which occurred in the containment building of the Savannah River nuclear reactor located at Aiken, South Carolina. Radiation dosimetry and temperature mapping data of the containment area indicated that the maximum dose experienced by the cable materials was only 2.5 Mrad at an average operating temperature of 43 0 C. Considering this relatively moderate environment, the amount of material degradation seemed surprising. To understand these findings, an experimental program was performed on the commercial polyethylene and polyvinylchloride materials used at the plant to investigate their degradation behavior under combined γ-radiation and elevated temperature conditions. It is established that the material deterioration at the plant resulted from radiation-induced oxidation and that the degradation rate can be correlated with local levels of radiation intensity in the containment area

Seismic review of existing nuclear power plants

International Nuclear Information System (INIS)

Yanev, P.I.; Mayes, R.L.; Jones, L.R.

1975-01-01

Because of developments in the fields of earthquake and structural engineering over the last two decades, the codes, standards and design criteria for Nuclear Power Plants and other critical structures have changed substantially. As a result, plants designed only a few years ago do not satisfy the requirements for new plants. Accordingly, the Regulatory Agencies are requiring owners of older Nuclear Power Plants to re-qualify the plants seismically, using codes, standards, analytical techniques and knowledge developed in recent years. Seismic review consists of three major phases: establishing the design and performance criteria, re-qualifying the structures, and re-qualifying the equipment. The authors of the paper have been recently involved in the seismic review of existing nuclear power plants in the United States. This paper is a brief summary of their experiences

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

International Nuclear Information System (INIS)

Kaiser, Peter; Madsen, Michael

2013-01-01

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

Nuclear and thermal power plants and the environment

International Nuclear Information System (INIS)

Mejstrik, V.

1978-01-01

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

Nuclear and thermal power plants and the environment

Energy Technology Data Exchange (ETDEWEB)

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

1978-01-01

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

Strengthening of nuclear power plant construction safety management

International Nuclear Information System (INIS)

Yu Jun

2012-01-01

The article describes the warning of the Fukushima nuclear accident, and analyzes the major nuclear safety issues in nuclear power development in China, problems in nuclear power plants under construction, and how to strengthen supervision and management in nuclear power construction. It also points out that the development of nuclear power must attach great importance to the safety, and nuclear power plant construction should strictly implement the principle of 'safety first and quality first'. (author)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1994-06-01

Quarterly reports on the operation of the Finnish NPPs describe nuclear and radiation safety related events and observations which the Finnish Centre for Radiation and Nuclear Safety considers significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and load factors are also given. One event during the last quarter of 1993 was rated on the International Nuclear Event Scale (INES) as level 1. During this event at Loviisa 2, the secondary circuit emergency feedwater system was erroneously isolated from automatic start-up readiness. The error went unnoticed for 4.5 hours. During 1993 one level 2 incident and three level 1 incidents occurred at the Finnish NPPs. (8 figs., 4 tabs.)

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

International Nuclear Information System (INIS)

1998-01-01

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

Aircraft, ships, spacecraft, nuclear plants and quality

International Nuclear Information System (INIS)

Patrick, M.G.

1984-05-01

A few quality assurance programs outside the purview of the Nuclear Regulatory Commission were studied to identify features or practices which the NRC could use to enhance its program for assuring quality in the design and construction of nuclear power plants. The programs selected were: the manufacture of large commercial transport aircraft, regulated by the Federal Aviation Administration; US Navy shipbuilding; commercial shipbuilding regulated by the Maritime Administration and the US Coast Guard; Government-owned nuclear plants under the Department of Energy; spacecraft under the National Aeronautics and Space Administration; and the construction of nuclear power plants in Canada, West Germany, France, Japan, Sweden, and the United Kingdom

Thermal coupling system analysis of a nuclear desalination plant

International Nuclear Information System (INIS)

Adak, A.K.; Srivastava, V.K.; Tewari, P.K.

2010-01-01

When a nuclear reactor is used to supply steam for desalination plant, the method of coupling has a significant technical and economic impact. The exact method of coupling depends upon the type of reactor and type of desalination plant. As a part of Nuclear Desalination Demonstration Project (NDDP), BARC has successfully commissioned a 4500 m 3 /day MSF desalination plant coupled to Madras Atomic Power Station (MAPS) at Kalpakkam. Desalination plant coupled to nuclear power plant of Pressurized Heavy Water Reactor (PHWR) type is a good example of dual-purpose nuclear desalination plant. This paper presents the thermal coupling system analysis of this plant along with technical and safety aspects. (author)

Insurance risk of nuclear power plant concentrations

International Nuclear Information System (INIS)

Feldmann, J.

1976-01-01

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

Deep waters : the Ottawa River and Canada's nuclear adventure

International Nuclear Information System (INIS)

Krenz, F.H.K.

2004-01-01

Deep Waters is an intimate account of the principal events and personalities involved in the successful development of the Canadian nuclear power system (CANDU), an achievement that is arguably one of Canada's greatest scientific and technical successes of the twentieth century. The author tells the stories of the people involved and the problems they faced and overcame and also relates the history of the development of the town of Deep River, built exclusively for the scientists and employees of the Chalk River Project and describes the impact of the Project on the traditional communities of the Ottawa Valley. Public understanding of nuclear power has remained confused, yet decisions about whether and how to use it are of vital importance to Canadians today - and will increase in importance as we seek to maintain our standard of living without doing irreparable damage to the environment around us. Deep Waters examines the issues involved in the use of nuclear power without over-emphasizing its positive aspects or avoiding its negative aspects.

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

International Nuclear Information System (INIS)

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

1975-01-01

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

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

International Nuclear Information System (INIS)

Hashemian, H.M.

2011-01-01

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

Closures for underground nuclear power plants

International Nuclear Information System (INIS)

1981-10-01

This study demonstrates that, with the appropriate selection of an access concept on the underground nuclear power plant, it is possible to design a gate complying with the increased requirements of the construction of an underground nuclear power plant. The investigations revealed that a comparison leakage of 42 mm in diameter for the failure of seals is too conservative. When selecting suitable seals a leakage being more extensive than the above mentioned one can be prevented even in case of disturbance lasting several months. The closure structures of the personnel and material accesses do not represent any weak point within the concept of the construction method for underground nuclear power plants. (orig./HP)

Methods of assessing nuclear power plant risks

International Nuclear Information System (INIS)

Skvarka, P.; Kovacz, Z.

1985-01-01

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

Evaluation of sediment and 137Cs redistribution in the Oginosawa River catchment near the Fukushima Dai-ichi Nuclear Power Plant using integrated watershed modeling.

Science.gov (United States)

Sakuma, Kazuyuki; Malins, Alex; Funaki, Hironori; Kurikami, Hiroshi; Niizato, Tadafumi; Nakanishi, Takahiro; Mori, Koji; Tada, Kazuhiro; Kobayashi, Takamaru; Kitamura, Akihiro; Hosomi, Masaaki

2018-02-01

The Oginosawa River catchment lies 15 km south-west of the Fukushima Dai-ichi nuclear plant and covers 7.7 km 2 . Parts of the catchment were decontaminated between fall 2012 and March 2014 in preparation for the return of the evacuated population. The General-purpose Terrestrial Fluid-flow Simulator (GETFLOWS) code was used to study sediment and 137 Cs redistribution within the catchment, including the effect of decontamination on redistribution. Fine resolution grid cells were used to model local features of the catchment, such as paddy fields adjacent to the Oginosawa River. The simulation was verified using monitoring data for river water discharge rates (r = 0.92), suspended sediment concentrations, and particulate 137 Cs concentrations (r = 0.40). Cesium-137 input to watercourses came predominantly from land adjacent to river channels and forest gullies, e.g. the paddy fields in the Ogi and Kainosaka districts, as the ground in these areas saturates during heavy rain and is easily eroded. A discrepancy between the simulation and monitoring results on the sediment discharge rate following decontamination may be explained by fast erosion occurring after decontamination. Forested areas far from the channels only made a minor contribution to 137 Cs input to watercourses, total erosion of between 0.001 and 0.1 mm from May 2011 to December 2015, as ground saturation is infrequent in these areas. The 2.3-6.9% y -1 decrease in the amount of 137 Cs in forest topsoil over the study period can be explained by radioactive decay (approximately 2.3% y -1 ), along with a migration downwards into subsoil and a small amount of export. The amount of 137 Cs available for release from land adjacent to rivers is expected to be lower in future than compared to this study period, as the simulations indicate a high depletion of inventory from these areas by the end of 2015. However continued monitoring of 137 Cs concentrations in river water over future years is advised, as

Striving for excellence in nuclear plant safety and reliability

International Nuclear Information System (INIS)

Beard, P.M.

1985-01-01

The Institute of Nuclear Power Operations, or INPO, promotes excellence in the construction and operation of nuclear power plants. All US nuclear utilities are INPO members. Additionally, INPO has an active international programme that includes utility participants from 13 countries and a supplier programme composed of 13 firms that provide construction, design or manufacturing services for nuclear utilities. INPO's activities revolve around four programme categories: (1) evaluating US nuclear plant construction projects and operating nuclear power plants; (2) assisting utilities in developing and maintaining performance-based training programmes and accrediting US nuclear plant training programmes; (3) analysing and sharing information on operating experience from plants around the world; (4) providing technical assistance to members and participants. INPO periodically evaluates all US operating nuclear power plants. Additionally, INPO uses the evaluations to observe good practices that can be shared with nuclear utilities world wide. The Significant Event Evaluation and Information Network (SEE-IN) programme provides a system for collecting, analysing and sharing information on plant operating experience throughout the world. SEE-IN provides the industry with information on events that could lead to serious consequences and provides recommendations on how these events can be prevented or their effects mitigated. INPO's international programme promotes information exchange among members and participants. The international programme centres on three activities: (1) collecting, analysing and sharing information on international nuclear plant operating experience; (2) establishing a forum for nuclear utilities world-wide to exchange technical data with each other; (3) providing technical assistance to participants on a variety of concerns

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

Science.gov (United States)

Whitelaw, Robert L.

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

Nuclear power plants and the environment

Energy Technology Data Exchange (ETDEWEB)

Barabas, K [Ceskoslovenska Komise pro Atomovou Energii, Prague

1978-05-01

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

Nuclear power plants and the environment

International Nuclear Information System (INIS)

Barabas, K.

1978-01-01

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

Regulatory requirements for desalination plant coupled with nuclear reactor plant

International Nuclear Information System (INIS)

Yune, Young Gill; Kim, Woong Sik; Jo, Jong Chull; Kim, Hho Jung; Song, Jae Myung

2005-01-01

A small-to-medium sized reactor has been developed for multi-purposes such as seawater desalination, ship propulsion, and district heating since early 1990s in Korea. Now, the construction of its scaled-down research reactor, equipped with a seawater desalination plant, is planned to demonstrate the safety and performance of the design of the multi-purpose reactor. And the licensing application of the research reactor is expected in the near future. Therefore, a development of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant is necessary for the preparation of the forthcoming licensing review of the research reactor. In this paper, the following contents are presented: the design of the desalination plant, domestic and foreign regulatory requirements relevant to desalination plants, and a draft of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant

Quality assurance during operation of nuclear power plants

International Nuclear Information System (INIS)

1994-01-01

The general requirements applicable to the quality assurance of the Finnish nuclear power plants are presented in the Council of State Decision (395/91) and in the guide YVL 1.4. This guide specifies the quality assurance requirements to be applied during the operation of the nuclear power plants as well as of the other nuclear facilities. Quality assurance applies to all the activities and organizations with a bearing on the safe operation of the nuclear power plants. (5 refs.)

Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

Energy Technology Data Exchange (ETDEWEB)

Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

1983-02-01

This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants.

Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

International Nuclear Information System (INIS)

Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

1983-02-01

This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants

Cooling water recipients for nuclear power plants

International Nuclear Information System (INIS)

Dahl, F.-E.; Saetre, H.J.

1971-10-01

The hydrographical and hydrological conditions at 17 prospective nuclear power plant sites in the Oslofjord district are evaluated with respect to their suitability as recipients for thermal discharges from nuclear power plants. No comparative evaluations are made. (JIW)

Portland General Electric Company report on the operating and startup experience with control and instrumentation and electrical systems at the Trojan Nuclear Plant

International Nuclear Information System (INIS)

Zimmerman, G.A.

1977-01-01

The Trojan Nuclear Plant is an 1178 MWe nuclear plant located on the Columbia River 40 miles northwest of Portland, Oregon. The Nuclear Stream Supply System vendor is Westinghouse with a General Electric turbine generator. The reactor is rated and licensed for 3423 MWt (1178 MWe) and the turbine generator is designed for 3570 MWt(1219 MWe). The startup phase testing of Trojan commenced on November 21, 1975, upon receipt of our NRC Operating License. The startup testing program was completed on May 22, 1976, following 100 hours of full-power operation, at which time a scheduled summer maintenance outage began. Some of the highlights and milestones of the startup testing program are described

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Lehtinen, Pekka

1987-05-01

These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the perssonnel or the environment. For remedying certain defects found in the administrative procedures concerning plant operation and maintenance, the Loviisa power plant was shut down for several days

Fuzzy logic control of nuclear power plant

International Nuclear Information System (INIS)

Yao Liangzhong; Guo Renjun; Ma Changwen

1996-01-01

The main advantage of the fuzzy logic control is that the method does not require a detailed mathematical model of the object to be controlled. In this paper, the shortcomings and limitations of the model-based method in nuclear power plant control were presented, the theory of the fuzzy logic control was briefly introduced, and the applications of the fuzzy logic control technology in nuclear power plant controls were surveyed. Finally, the problems to be solved by using the fuzzy logic control in nuclear power plants were discussed

Decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Vollradt, J.

1977-01-01

A survey of the main questions of decommissioning of nuclear power plants will be given in the sight of German utilities (VDEW-Working group 'Stillegung'). The main topics are: 1) Definitions of decommissioning, entombment, removal and combinations of such alternatives; 2) Radioactive inventory (build up and decay); 3) Experience up to now; 4) Possibilities to dismantle are given by possibility to repair nuclear power plants; 5) Estimated costs, waste, occupational radiation dose; 6) German concept of decommissioning. (orig./HK) [de

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Safety principles for nuclear power plants

International Nuclear Information System (INIS)

Vuorinen, A.

1993-01-01

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

Effect of thermal and radioactive waste waters from nuclear power plant on recipient biocenosis

Energy Technology Data Exchange (ETDEWEB)

Veresikova, M; Csupka, S; Tomanova, E [Krajska Hygienicka Stanica, Bratislava (Czechoslovakia)

1979-01-01

During the years 1974 to 1976 the effect was studied of thermal and radioactive effluents from the A-1 nuclear power plant on aquatic microorganisms. The values obtained from the waste water canal and the river Dudvah after the canal discharged into the river were compared with the values found in the Dudvah before the discharge. The correlation between aquatic microorganisms and water temperature was found to be closest in the waste water canal and between microorganisms and /sup 137/Cs content in the Dudvah after sewer emptying. With increasing water temperature the populations of aquatic microorganisms decrease, with the exception of producers whose numbers will increase with rising water temperature. The content of /sup 137/Cs in water had an effect similar to that of water temperature.

Chernobyl nuclear accident hydrologic analysis and emergency evaluation of radionuclide distributions in the Dnieper River, Ukraine, during the 1993 summer flood

International Nuclear Information System (INIS)

Voitsekhovitch, O.V.; Zheleznyak, M.J.

1994-06-01

This report describes joint activities of Program 7.1.F, ''Radionuclide Transport in Water and Soil Systems,'' of the USA/Commonwealth of Independent States (CIS) Joint Coordinating Committee of Civilian Nuclear Reactor Safety to study the hydrogeochemical behavior of radionuclides released to the Pripyat and Dnieper rivers from the Chernobyl Nuclear Power Plant in Ukraine. These joint activities included rapid evaluation of radionuclide distributions in the Pripyat and Dnieper river system and field data evaluation and modeling for the 1993 summer flood to assist the Ukrainian government in their emergency response during the flood. In July-August 1993, heavy rainfall over the Pripyat River Catchment in Belarus and Ukraine caused severe flooding, significantly raising 90 Sr concentrations in the river. Near the Chernobyl area, the maximum 90 Sr concentration in the Pripyat River reached 20--25 PCi/L in early August; near the Pripyat River mouth, the concentration rose to 35 pCi/L. The peak 90 Sr concentration in the Kiev Reservoir (a major source of drinking water for Kiev) was 12 pCi/L. Based on these measured radionuclide levels, additional modeling results and the assumption of water purification in a water treatment station, 90 Sr concentrations in Kiev's drinking water were estimated to be less than 8 pCi/L. Unlike 90 Sr, 137 Cs concentrations in the Pripyat River during the flood did not rise significantly to the pre-flood levels. Estimated 137 Cs concentrations for the Kiev drinking water were two orders of magnitude lower than the drinking water standard of 500 pCi/L for 137 Cs

Study of a conceptual nuclear energy center at Green River, Utah: licensing considerations

International Nuclear Information System (INIS)

Dowdle, M.; Russell, R.; Zillman, D.

1982-04-01

This report examines the laws governing the location of a 9-unit nuclear energy center (NEC) near Green River, Utah. The time frame being considered for development of the conceptual NEC is from 1995 to 2013. Accordingly, the report is forced to speculate about some aspects of the plant, its site and its construction. Most of the report examines existing legal requirements for constructing an NEC. Where pertinent, changes in the law are discussed that would affect an NEC that is to be licensed in one or two decades. In general, no insurmountable legal problems exist that would prevent an NEC from being licensed at the Green River location. Several legal requirements pose significant concerns and would have to be faced before an NEC could be built. Among the major legal constraints are radiation protection, regulatory approval of financing, access to water, and local zoning restrictions. Two other constraints that involve legal matters are the wisdom of standardization of the units and the responsibility of the NEC builder to correct socio-economic impacts on the local area

Relative costs to nuclear plants: international experience

International Nuclear Information System (INIS)

Souza, Jair Albo Marques de

1992-03-01

This work approaches the relative costs to nuclear plants in the Brazil. It also presents the calculation methods and its hypothesis to determinate the costs, and the nacional experience in costs of investment, operating and maintenance of the nuclear plants

EPRI nuclear power plant decommissioning technology program

International Nuclear Information System (INIS)

Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

2011-01-01

The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

Environmental survey around EDF nuclear power plants

International Nuclear Information System (INIS)

Foulquier, L.

1992-01-01

Description of various types of environmental test carried out under the responsibility of the Operator of nuclear power plants in France, with taking Fessenheim nuclear power plant as an example: permanent monitoring of radioactivity, periodic radioecological assessments, main results of measurements taken, showing that there are no detectable effects of the plant on the environment, policy of openness by publication of these results

Migration of radionuclides through a river system

Energy Technology Data Exchange (ETDEWEB)

Matsunaga, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1999-03-01

Migration behavior of several atmospherically-derived radionuclides in a river watershed was studied. A main interest was in their relocation from the ground soil of the watershed to a downstream region through a river. Studied radionuclides are: {sup 137}Cs generated by weapon tests in the atmosphere; {sup 210}Pb and {sup 7}Be of naturally occurring radionuclides; {sup 137}Cs, {sup 90}Sr, {sup 239,240}Pu and {sup 241}Am released by the Chernobyl nuclear power plant accident. Dominance of the form in suspended solid in river water (particulate form) was qualified for the radionuclides in the Kuji river watershed. An importance of discharge in flooding was also confirmed. A historical budget analysis for weapon test derived {sup 137}Cs was presented for the Hi-i river watershed and its accompanied lake sediment (Lake Shinji). The work afforded a scheme of a fate of {sup 137}Cs after falling on the ground soil and on the lake surface. Several controlling factors, which can influence on the chemical form of radionuclides discharged to a river, were also investigated in the vicinity of the Chernobyl nuclear power plant. A special attention was paid on the association of the radionuclides with dissolved species in water. Preferential association of Pu and Am isotopes to a large molecular size of dissolved matrices, probably of humic substances, was suggested. (author)

In-plant reliability data base for nuclear power plant components: data collection and methodology report

International Nuclear Information System (INIS)

Drago, J.P.; Borkowski, R.J.; Pike, D.H.; Goldberg, F.F.

1982-07-01

The development of a component reliability data for use in nuclear power plant probabilistic risk assessments and reliabiilty studies is presented in this report. The sources of the data are the in-plant maintenance work request records from a sample of nuclear power plants. This data base is called the In-Plant Reliability Data (IPRD) system. Features of the IPRD system are compared with other data sources such as the Licensee Event Report system, the Nuclear Plant Reliability Data system, and IEEE Standard 500. Generic descriptions of nuclear power plant systems formulated for IPRD are given

Maintenance of nuclear power plants

International Nuclear Information System (INIS)

Lashgari, Farbod.

1995-01-01

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

Financial analysis of large versus small nuclear power plants

International Nuclear Information System (INIS)

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

1986-01-01

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

Cost savings from extended life nuclear plants

International Nuclear Information System (INIS)

Forest, L.R. Jr.; Deutsch, T.R.; Schenler, W.W.

1988-09-01

This study assesses the costs and benefits of nuclear power plant life extension (NUPLEX) for the overall US under widely varying economic assumptions and compares these with alternative new coal- fired plants (NEWCOAL). It is found that NUPLEX saves future electricity consumers more than 3 cents/-kwh compared with NEWCOAL. The NUPLEX costs and benefits for existing individual US nuclear power plants under base-line, or most likely, assumptions are assessed to determine the effects of the basic plant design and plant age. While benefits vary widely, virtually all units would have a positive benefit from NUPLEX. The study also presents a cost-benefit analysis of the nuclear industry's planned advanced light water reactor (ALWR). It is concluded that ALWR offers electrical power at a substantially lower cost than NEWCOAL. 9 refs., 6 figs

Environmental monitoring in the vicinity of the Savannah River Plant. Annual report, 1974

International Nuclear Information System (INIS)

1974-01-01

The results obtained from the environmental monitoring program at the Savannah River Plant during 1974 are presented. An inventory of radioactive materials released to the environment, and data on radioactivity in samples of surface air, surface waters, soil, plants, and food are included. Data are also included on pesticides in Savannah River sediment. (U.S.)

Cost benefit justification of nuclear plant reliability improvement

International Nuclear Information System (INIS)

El-Sayed, M.A.H.; Abdelmonem, N.M.

1985-01-01

The design of the secondary steam loop of the nuclear power plant has a significant effect on the reliability of the plant. Moreover, the necessity to cool a reactor safely has increased the reliability demanded from the system. The rapidly rising construction costs and fuel prices in recent years have stimulated a great deal in optimizing the productivity of a nuclear power plant through reliability improvement of the secondary steamloop and the reactor cooling system. A method for evaluating the reliability of steam loop and cooling system of a nuclear power plant is presented. The method utilizes the cut-set technique. The developed method can be easily used to show to what extent the overall reliability of the nuclear plant is affected by the possible failures in the steam and cooling subsystem. A model for calculating the increase in the nuclear plant productivity resulting from a proposed improvement in the two subsystems reliability is discussed. The model takes into account the capital cost of spare parts for several components, replacement energy, operating and maintenance costs

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1994-03-01

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

Beloyarsk Nuclear Power Plant

International Nuclear Information System (INIS)

1997-01-01

The Beloyarsk Nuclear Power Plant (BNPP) is located in Zarechny, approximately 60 km east of Ekaterinberg along the Trans-Siberian Highway. Zarechny, a small city of approximately 30,000 residents, was built to support BNPP operations. It is a closed city to unescorted visitors. Residents must show identification for entry. BNPP is one of the first and oldest commercial nuclear power plants in Russia and began operations in 1964. As for most nuclear power plants in the Russian Federation, BNPP is operated by Rosenergoatom, which is subordinated to the Ministry of Atomic Energy of the Russian Federation (Minatom). BNPP is the site of three nuclear reactors, Units 1, 2, and 3. Units 1 and 2, which have been shut-down and defueled, were graphite moderated reactors. The units were shut-down in 1981 and 1989. Unit 3, a BN-600 reactor, is a 600 MW(electric) sodium-cooled fast breeder reactor. Unit 3 went on-line in April 1980 and produces electric power which is fed into a distribution grid and thermal power which provides heat to Zarechny. The paper also discusses the SF NIKIET, the Sverdiovsk Branch of NIKIET, Moscow, which is the research and development branch of the parent NIKEIT and is primarily a design institute responsible for reactor design. Central to its operations is a 15 megawatt IVV research reactor. The paper discusses general security and fissile material control and accountability at these two facilities

About a hypothetical terrorist attack on a nuclear power plant

International Nuclear Information System (INIS)

2001-10-01

After the terrorism attack on the World Trade Center, a record number ( two thirds) of US citizens favour the use of nuclear energy and consider nuclear plants to be safe. At the same time 59% definitely support building more nuclear plants, less than in March during the Californian crisis, but more than earlier., Most american citizens ( 84%) continue to support licence renewal for nuclear plants and 72 % agree with keeping the option open to build new nuclear plants in the future. The strongest supporters are those who have visited a nuclear plant or information centre. (N.C.)

SECURE nuclear district heating plant

International Nuclear Information System (INIS)

Nilsson; Hannus, M.

1978-01-01

The role foreseen for the SECURE (Safe Environmentally Clean Urban REactor) nuclear district heating plant is to provide the baseload heating needs of primarily the larger and medium size urban centers that are outside the range of waste heat supply from conventional nuclear power stations. The rationale of the SECURE concept is that the simplicity in design and the inherent safety advantages due to the use of low temperatures and pressures should make such reactors economically feasible in much smaller unit sizes than nuclear power reactors and should make their urban location possible. It is felt that the present design should be safe enough to make urban underground location possible without restriction according to any criteria based on actual risk evaluation. From the environmental point of view, this is a municipal heat supply plant with negligible pollution. Waste heat is negligible, gaseous radioactivity release is negligible, and there is no liquid radwaste release. Economic comparisons show that the SECURE plant is competitive with current fossil-fueled alternatives. Expected future increase in energy raw material prices will lead to additional energy cost advantages to the SECURE plant

Medical consequences of a nuclear plant accident

International Nuclear Information System (INIS)

Olsson, S.E.; Reizenstein, P.; Stenke, L.

1987-01-01

The report gives background information concerning radiation and the biological medical effects and damages caused by radiation. The report also discusses nuclear power plant accidents and efforts from the medical service in the case of a nuclear power plant accident. (L.F.)

Computer-assisted nuclear fuel manufacture

International Nuclear Information System (INIS)

Maloney, J.P.; Schaumann, S.M.; Stone, E.

1976-01-01

At the ERDA Savannah River Plant, a process monitor, which incorporates an online digital computer, assists in manufacturing fuel elements used to produce nuclides such as plutonium, tritium, and californium in the plant's nuclear reactors. Also, inventory functions assist in safeguarding fissile material and protecting against accidental nuclear criticality. Terminals at strategic locations throughout the process area enable production operators to send and receive instructions and information on each manufacturing step

Investigation of human system interface design in nuclear power plant

International Nuclear Information System (INIS)

Feng Yan; Zhang Yunbo; Wang Zhongqiu

2012-01-01

The paper introduces the importance of HFE in designing nuclear power plant, and introduces briefly the content and scope of HFE, discusses human system interface design of new built nuclear power plants. This paper also describes human system interface design of foreign nuclear power plant, and describes in detail human system interface design of domestic nuclear power plant. (authors)

Risk perception among nuclear power plant personnel: A survey

International Nuclear Information System (INIS)

Kivimaeki, M.; Kalimo, R.

1993-01-01

This study investigated risk perception, well-being, and organizational commitment among nuclear power plant personnel. The study group, 428 employees from a nuclear power plant, completed a questionnaire which included the same questions as those in previous surveys on risk perception of lay persons and industrial workers. Hazards at work were not seen as a sizable problem by nuclear power plant personnel. The study group estimated the safety of nuclear power plants better and the possibility of a serious nuclear accident as more unlikely than the general public. Compared to employees in other industrial companies, the overall perceived risks at work among plant personnel did not exceed the respective perceptions of the reference groups. Risk-related attitudes did not explain well-being among plant personnel, but the relationship between the perceived probability of a serious nuclear accident at work and organizational commitment yielded to a significant correlation: Those plant workers who estimated the likelihood of an accident higher were less committed to the organization. 21 refs., 2 tabs

A trend to small nuclear power plants?

International Nuclear Information System (INIS)

Lameira, Fernando Soares

2000-01-01

The release of fossil fuel greenhouse gases and the depletion of cheap oil reserves outside the Persic Gulf suggest a promising scenario for the future of nuclear power. But the end of the Cold War, the crisis of the state, axiological questions and globalization may lead to a marked for small power plants. The purpose of this paper is to analyze these factors, since they are not always considered all together in the future scenarios for nuclear power. It is concluded that the current evolutionary trend of nuclear power projects toward big plants may become one of the main barriers for the introduction of new plants in the future. It is suggested that a combination of fission reactors with technologies unavailable in the 1950's, when the design characteristics of the current nuclear power plants were established, could be considered to overcome this barrier. (author)

Space nuclear reactor power plants

International Nuclear Information System (INIS)

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

1980-01-01

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

Nuclear power plants and their insurances

International Nuclear Information System (INIS)

Schludi, H.N.

1984-01-01

From the commencement of building to the time of decommissioning of nuclear power plants, the insurances provide continuous coverage, i.e. for construction, nuclear liability, nuclear energy hazards insurance, fire insurance, machinery insurance. The respective financial security is quantified. (DG) [de

Croatian-Hungarian cooperation on the Danube river radioactivity measurements

International Nuclear Information System (INIS)

Lulic, S.; Vancsura, P.

2003-01-01

Danube river radioactivity measurements on the border profile Mohac-Batina have been performed since the beginning of 1978 with varying frequency of sampling. Thus, in the period before nuclear power plant Paks started to work joint croatian-hungarian sampling at the border profile was taking place four times a year; the obtained results of measured radioactivity levels were used to assess radioactivity background data. From the start of nuclear power plant Paks running until Chernobyl reactor accident (April 1986) sampling was performed six times a year. After the Chernobyl accident, samples have been taken every month. Since decreased Chernobyl reactor accident influence was estimated until present samples have been taken six times a year. On the Danube river border profile the concentration activity of gamma radionuclides has been determined in water samples (filtered water and suspended matter), and in fish, sediment and Danube river algae samples. (authors)

Transfer mechanisms in cultivated soils of waste radionuclides from electronuclear power plants in the system river--irrigated soil--underground water level

Energy Technology Data Exchange (ETDEWEB)

Saas, A; Grauby, A

1974-12-31

From symposinm on environmentl behavior of radionuclides released in the nuclear industry; Aix-en-Provence, France (14 May 1973). The location of nuclear power plants by rivers whose waters are used for irrigation and industrial and domestic consumption necessities a profound study of the river-irrigated soil- ground water system. Mechanisms of radionuclide transport in cultivated soil are considered under three principal aspects: the effect of the quality of the river water, of the irrigation channels, and of the ground water level on the mobility of the radionuclides in the soil; the influence of the type of soil (the four types of soils considered are acid brown soil, calcic brown soil, chalky brown soil, and chalky alluvial soil); and the distribution of radionuclides in the soil (hydrosoluble forms can contminate the ground water level and these are the forms in which they are taken up by plants. A study was made on the following nuclides: /sup 22/Na, /sup 137/Cs, /sup 85/Sr, /Sup 54/Mn, /Sup 59/Fe, /Sup 60/ Co, /sup 65/Zn, /sup 124/Sb, /sup 141 in the cultivated soils permit the evaluation of the risks of contmination of the food chain and of the underground water. This study also showed new perspectives of the behavior of radionuclides as a function of their contmination of the organo-mineral wastes of industrial and domestic origin. This pollution interfers largely with the formation of stble complexes carried by the river to irrigated soils. The quality of the water determines the distribution of the radionuclides in the profile. The hydrosoluble complex persists in the soil and migrates toward the underground water level if they are not biodegradable. The stability of these forms as a function of the soil pH and of its physicochemical characteristics, as well as that of the radionuclides considered, permit the formulation of a new balance of the radionuclides in soils. The formulation of new proposals for the contml of nuclear sites is discussed. (tr-auth)

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

1992-01-01

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

Passive Nuclear Plants Program (UPDATE)

International Nuclear Information System (INIS)

Chimeno, M. A.

1998-01-01

The light water passive plants program (PCNP), today Advanced Nuclear Power Plants Program (PCNA), was constituted in order to reach the goals of the Spanish Electrical Sector in the field of advanced nuclear power plants, optimize the efforts of all Spanish initiatives, and increase joint presence in international projects. The last update of this program, featured in revision 5th of the Program Report, reflects the consolidation of the Spanish sector's presence in International programs of the advanced power plants on the basis of the practically concluded American ALWR program. Since the beginning of the program , the PCNP relies on financing from the Electrical sector, Ocide, SEPI-Endesa, Westinghouse, General Electric, as well as from the industrial cooperators, Initec, UTE (Initec- Empresarios Agrupados), Ciemat, Enusa, Ensa and Tecnatom. The program is made up of the following projects, already concluded: - EPRI's Advanced Light Water Plants Certification Project - Westinghouse's AP600 Project - General Electric's SBWR Project (presently paralyzed) and ABWR project Currently, the following project are under development, at different degrees of advance: - EPP project (European Passive Plant) - EBWR project (European Advanced Boiling Water Reactor)

Classification of nuclear plant cost to energy

International Nuclear Information System (INIS)

Long, G.A.

1983-01-01

In order to understand why the fixed-cost/variable-cost method of classifying nuclear plant costs can lead to rate discontinuities, the author must examine the factors which lead to the decision to build a nuclear power plant and the interrelationship between demand (KW) and energy (KWH). The problems and inequities associated with the nuclear plants can be avoided by recognizing that fixed costs are related to both demand and energy and by using a costing methodology which closely relates to the functional purpose of the plant. Generally, this leads to classifying fixed costs of nuclear plants primarily to the energy function in an embedded cost-of-service study and through either implicit or explicit recognition of fuel savings in a marginal cost study. The large rate discontinuities which occurred in the scenario can be resolved. Costs associated with demand or energy charges remain relatively stable compared to actual capacity costs and customers would not experience large changes in their bills due solely to a particular costing convention

76 FR 75771 - Emergency Planning Guidance for Nuclear Power Plants

Science.gov (United States)

2011-12-05

... Guidance for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of NUREG... Support of Nuclear Power Plants;'' NSIR/DPR-ISG-01, ``Interim Staff Guidance Emergency Planning for Nuclear Power Plants;'' and NUREG/CR-7002, ``Criteria for Development of Evacuation Time Estimate Studies...

Environmental and security challenges of nuclear plants

International Nuclear Information System (INIS)

Omar, A.S.

2014-01-01

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

Investigation of cable deterioration in the containment building of the Savannah River Nuclear Reactor

Energy Technology Data Exchange (ETDEWEB)

Gillen, K.T.; Clough, R.L.; Jones, L.H.

1982-08-01

This report describes an investigation of the deterioration of polyethylene and polyvinylchloride cable materials which occurred in the containment building of the Savannah River nuclear reactor located at Aiken, South Carolina. Radiation dosimetry and temperature mapping data of the containment area indicated that the maximum dose experienced by the cable materials was only 2.5 Mrad at an average operating temperature of 43/sup 0/C. Considering this relatively moderate environment, the amount of material degradation seemed surprising. To understand these findings, an experimental program was performed on the commercial polyethylene and polyvinylchloride materials used at the plant to investigate their degradation behavior under combined ..gamma..-radiation and elevated temperature conditions. It is established that the material deterioration at the plant resulted from radiation-induced oxidation and that the degradation rate can be correlated with local levels of radiation intensity in the containment area.

Human factors in nuclear power plant operations

International Nuclear Information System (INIS)

Swain, A.D.

1980-08-01

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

Abandoned floodplain plant communities along a regulated dryland river

Science.gov (United States)

Reynolds, L. V.; Shafroth, Patrick B.; House, P. K.

2014-01-01

Rivers and their floodplains worldwide have changed dramatically over the last century because of regulation by dams, flow diversions and channel stabilization. Floodplains no longer inundated by river flows following dam-induced flood reduction comprise large areas of bottomland habitat, but the effects of abandonment on plant communities are not well understood. Using a hydraulic flow model, geomorphic mapping and field surveys, we addressed the following questions along the Bill Williams River, Arizona: (i) What per cent of the bottomland do abandoned floodplains comprise? and (ii) Are abandoned floodplains quantitatively different from adjacent xeric and riparian surfaces in terms of vegetation composition and surface sediment? We found that nearly 70% of active channel and floodplain area was abandoned following dam installation. Abandoned floodplains along the Bill Williams River tend to be similar to each other yet distinct from neighbouring habitats: they have been altered physically from their historic state, leading to distinct combinations of surface sediments, hydrology and plant communities. Abandoned floodplains may transition to xeric communities over time but are likely to retain some riparian qualities as long as there is access to relatively shallow ground water. With expected increases in water demand and drying climatic conditions in many regions, these surfaces and associated vegetation will continue to be extensive in riparian landscapes worldwide