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Sample records for central nuclear embalse

  1. Valuation of Embalse Nuclear Power Plant and of heavy water

    International Nuclear Information System (INIS)

    The author describes the Nuclear Power Plant characteristics, the building work, the heavy water valuation criteria and the reasons why he considers that any capital good can be valuated by means of cash-flow. The value of replacement of Embalse Nuclear Power Plant is of U$S 1.593.538.000 (authors)

  2. Embalse nuclear power plant and heavy water valuation

    International Nuclear Information System (INIS)

    The author describes the nuclear power plant characteristics, the building work, the heavy water valuation criteria and the reasons why he considers that any capital good can be valued by the cash-flow method. The Embalse nuclear power plant replacement value is of U$S 1.593.538.000. (author)

  3. Implementation of the Embalse nuclear power plant's commissioning

    International Nuclear Information System (INIS)

    This work points out the main experiences gathered during the Embalse nuclear power plant start-up, which after the first years of operation arise as quite convenient to be taken into account for future nuclear power plants' start-up. (Author)

  4. Inspection program for Embalse Nuclear Generating Station

    International Nuclear Information System (INIS)

    Embalse Nuclear Generating Station (ENGS), a CANDU 6 type with 648 MWe output, started operating in 1983. In the last 10 years it has shown an excellent performance with an average 88.25 % capacity factor. In order to maintain the safety and operation levels at economically convenient levels, an efficient management of the effects of aging of Critical Systems, Structures and Components is required. In this regard, Nucleoelectrica Argentina S.A.-ENGS's operator- has initiated a Plant Life Management (PLiM) program focused on reaching its design life and establishing the requirements for its life extension. Within the framework of this program, a series of reviews of the existing Operation and Maintenance programs is scheduled with the aim of establishing the bases for potential life extension. A work team has been designated to this effect and the team has received training in the PLiM methodologies by AECL. In this paper an analysis of the Inspection Program for ENGS is presented. Also, the areas to be reinforced for the Systems, Structures and Components identified as critical are identified based on the SAM (Systematic Assessment of Maintenance) methodologies. The ENGS Engineering Procedures form the basis for the inspection program along with the records of the inspections performed. The inspection program will be the object of analysis, as the starting point of the PLiM of ENGS. There are also other programs, for example those for preventive / predictive maintenance, routine testing, which focus on maintaining a high reliability of the safety as well as the process systems. All plant systems are taken into account with a list of inspections based on recommendations by the plant designer (AECL). It is continuously modified according to the results thereof and the experience of other plants, and revised within the framework of the SAM of the most important systems. Within this program, the ENGS chemistry laboratory and CNEA's (Comision Nacional Energia Atomica

  5. Deuterium ingress at rolled joints in Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Deuterium ingress model at the Rolled Joint has been extensively used for CANDU Nuclear Power Plants Operators in the Life Management of the Pressure Tubes. The importance of understanding the model is vital to avoid delayed hydride cracking at the Rolled Joint. This work reports the first step on develop the model presented on literature to be used in Argentinean CANDU 6, Embalse Nuclear Power Plant. (author)

  6. Dosimetry of the Embalse nuclear power plant neutron/gamma mixed fields

    International Nuclear Information System (INIS)

    The aim of this work is to describe the method used at the Embalse nuclear power plant for carrying out personal dosimetry of the agents affected to the tasks on the Embalse nuclear power plant neutron-gamma mixed fields. (Author)

  7. An Embalse nuclear power plant basic principles simulator

    International Nuclear Information System (INIS)

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

  8. Real time neutronic evolution CNE (Embalse nuclear power plant)

    International Nuclear Information System (INIS)

    The simulator of the Embalse nuclear power plant uses a Point Reactor Model(PRM) for the neutronic evolution calculation. As this model is not conservative for transients produced by the sudden or localized reactivity insertion in big cores, it is convenient to use spatial models in these cases. In this report we show the results obtained using a nodal model (codes NODOS-TIEMPO). This model has been fitted against a more exact solution for the neutron flux and delayed neutron precursors. This has been done for the reactor at full power with nominal values for the reactivity control devices (liquid zones and adjusters rods). Transients corresponding to the global variation of the liquid zones and to the insertion of fresh fuel in some channels are shown. The results are compared with calculations made with the quasi-static model of the PUMA code. (author). 1 ref

  9. Population distribution, food production and other aspects in the vicinity of the Embalse Nuclear Power Station

    International Nuclear Information System (INIS)

    The paper presents some of the results of the pre-operational studies carried out in the vicinity of the site of the Embalse Nuclear Power Station, which is being built in the Province of Cordoba, Rio Tercero, next to the lake Embalse. The studies cover population distribution, food production, and other local aspects. The low population in the vicinity of the site increases in summer due to tourism. Main use of the land is grazing and cereal production. Milk production is small, but some is produced near the site. Other aspects of the study are presented in other papers of the Seminar. (author)

  10. A small reactor inter header break for Embalse nuclear power plant with loss of electrical supply

    International Nuclear Information System (INIS)

    A small reactor inlet header break was studied for Embalse Nuclear Power Station. The initial leakage rate was 55 kg/s. A low pressure trip was reached. As a consequence, electrical power supply was assumed to be lost. Results show that in 30 minutes operator actions must follow in order to avoid high fuel temperatures. (author)

  11. Environmental management in Atucha-I and Embalse nuclear power plants

    International Nuclear Information System (INIS)

    The operator, Nucleoelectrica Argentina, received the certification of the IRAM (Argentine Institute of Normalization) under the ISO standard 14001:1996 for the System of Environmental Management implemented in the nuclear power plants of Atucha I (Lima, province of Buenos Aires, Argentina) and Embalse (Cordoba, Argentina). The process of certification is outlined as well as its effects on the environmental management

  12. Evaluation code for the dose due to the discharges of liquid effluents of the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    A new methodology is presented to assess the evaluation of the radiological impact to the population, due to the discharges to the environment of liquids effluents of Central Nuclear Embalse (CNE), located in the Province of Cordoba (Argentina). In order to carry out the dose evaluation, a code denominated EDDELIQ was developed, in this code the calculation of the radionuclides concentration in the water lake is made by means of a simple physical model of the type of complete mixture. The physical model is solved numerically by means of Runge Kutta method of second order. (author)

  13. Software system for fuel management at Embalse nuclear power plant

    International Nuclear Information System (INIS)

    For accurate tracking of flux and power distribution in a CANDU reactor, the information needed is evaluated from a neutronic code calculation adjusted with experimental values, making use of in-core vanadium detectors at 102 locations together with auxiliary programs.The basic data that feed these programs come from the geometric and neutronic features and the actual instantaneous operating parameters. The system that provides all this information should be designed to meet with software quality assurance requirements. A software system was implemented at Embalse Nuclear Power Plant and it is in operation since 1998 after two year testing. This PC version replaced the former system introducing new concepts in its architecture. The neutronic code runs by procedures implemented in a language of macro instructions, so only new data are loaded for two consecutive instantaneous cases avoiding unnecessary data repetition. After each step, all results of neutronic calculation are stored in master files. Afterwards other auxiliary programs retrieve basic data for further evaluation and files are sorted in different thematic folders using a specific codification, for reevaluating further calculations over any specific case. The whole system can be installed in any PC. The package is provided with its general and particular support documentation and procedures for each program.The main purpose of the system is to track fuel and power distribution calculated after a certain period where fuelling operation were done in between. The main code, PUMA, evaluates in a 3-D, two-group scheme using finite difference diffusion theory. After neutronic calculation is performed, other programs allow to retrieve assorted information valid for fuel strategy and to build the fuelling operation list to be sent to the operation shifts. This program also permits to evaluate the accuracy of PUMA by doing comparisons with experimental values. Along with these features, some other system

  14. Object-oriented simulator of the dynamics of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    LUDWIG is an object-oriented simulator of the dynamics of the CANDU Nuclear power plant Embalse Rio Tercero. The tool consists in a numerical plant analyzer by means of a model of the plant dynamics during normal operation, and a graphic environment for configuration and visualization of results. The simulator was validated against plant transients occurred in the plant and recorded in the past. (author)

  15. Determination of temperature measurements uncertainties of the heat transport primary system of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    In this work, the systematic errors in temperature measurements in inlet and outlet headers of HTPS coolant channels of Embalse nuclear power plant are evaluated. These uncertainties are necessary for a later evaluation of the channel power maps transferred to the coolant. The power maps calculated in this way are used to compare power distributions using neutronic codes. Therefore, a methodology to correct systematic errors of temperature in outlet feeders and inlet headers is developed in this work. (author)

  16. Plant life extension (PLEX) and repowering. Study on Embalse Nuclear Power Plant

    International Nuclear Information System (INIS)

    This is a PowerPoint presentation. Nuclearelectrica Argentina S.A. (NA.S.A.), the Argentine Utility owner and operator of the Embalse CANDU Nuclear Power Plant, has the firm intention of refurbishing and - thereby - extending the design service life of Embalse Nuclear Power Plant up to 2035, providing a Plant Life Extension equal to 25 years. Embalse Plant Life Extension pre-project work has started and is being executed by AECL and Ansaldo Nucleare, for NPP and BOP systems respectively; NA.S.A. has assigned a contract to Ansaldo Nucleare for the BOP PLEX pre-project first phase, as a part of an overall Power Life Management program. The job is organized in order to get within the Plant outages of April 2007 and late November 2008 the residual life evaluation of the as built configuration of the Plant; within the outages 2010 (end of the Plant Design Life) it is planned to produce the intervention planning to be implemented in the years 2009 and 2010 to get the required life extension. Through this strategic approach it would be possible to get the life extension without being forced to stop the Plant for updating implementation. This PLEX for Embalse BOP first phase consists, as minimum, of the following: - Investigation of the as built configuration of the Embalse BOP, based on the available Embalse documentation in terms of Process and Instruments Diagrams / Systems Technical Descriptions for BOP as well as of BOP General Arrangement / Composite Drawings, and based on specialists walkdowns during Outage periods and during plant normal operation. This activity is performed by means of dedicated systems/component check lists to collect all data; - Investigation of potential repowering of the Embalse BOP, based on evaluation of the possibility to increase the power for the NPP by Repowering associated to thermal cycle design optimization, without considering any modification to the current configuration of the turbine blades, and by Repowering associated to

  17. Embalse life extension project

    International Nuclear Information System (INIS)

    The Embalse life extension (LEP) project involved reactor core replacement (re-tubing), control computer replacement, safety and licensing and safety upgrades and power uprating. Objective of this program was to extend the life of the Embalse Nuclear Generating Station for about 30 more years of safe, reliable operation. The scope of this work was in keeping with LEP upgrades that other sister CANDU 6 stations are or have been implementing as part of their refurbishment programs.

  18. Liquid relief valve failure simulation in the Embalse nuclear power station

    International Nuclear Information System (INIS)

    Simulations of the failure (open) of a liquid relief valve in the Embalse Nuclear Power Station primary heat transport system have been performed using the Firebird III computer code. Results show that, without any action by the operators, and if the degasser 'bottles up', then pressure will increase, causing the relief degasser condenser valve to open. Several actions that might be taken to prevent this and the resulting loss of heavy water have been analyzed. The results of the simulations indicate that the best action is to reduce power when the pressurizer level stops decreasing. 1 ref., 10 figs

  19. Determination of the filling gas composition of the Embalse nuclear power plant's fuel rods by gas chromatography

    International Nuclear Information System (INIS)

    The present method is appropriate to evaluate the argon content in its mixture with hellium in Embalse nuclear power plant tubes, without active material. The maximum relative error within the range from 20% to 80% of argon, is of 1%. The detection limit for the possible nitrogen presence is in the order of magnitude of 5ppm. (Author)

  20. Critical channel power calculation for nominal operation in the CNE (Embalse nuclear power plant): sensitivity study

    International Nuclear Information System (INIS)

    In the Embalse nuclear power plant (CNE), the Regional Overpower Protection System acting on the Shutdown Systems number 1 and number 2 protects the reactor against overpowers in the reactor field for a localized peaking or a power increase in the reactor as a whole. This report summarizes the results of the critical channel power calculation for the time average powers configuration for the 380 reactor field channels. The final purpose of this work is to analyze and eventually modify the detector set points. Other reactor configurations are being analyzed. The report also presents a sensitivity analysis in order to evaluate potential sources of error and uncertainties which could affect the ROP performance. (author)

  1. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    Science.gov (United States)

    Katchadjian, Pablo; Desimone, Carlos; Garcia, Alejandro; Antonaccio, Carlos; Schroeter, Fernando; Molina, Héctor

    2015-03-01

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces.

  2. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    International Nuclear Information System (INIS)

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces

  3. Results of fuel management at Embalse nuclear power plant. Analysis of performance at other plants

    International Nuclear Information System (INIS)

    The operating experience of fuel management at the Embalse nuclear power plant from new core to the present situation (approximately 937 days at full power) is described. The average core burnup is about 4000 MW d/t U and the monthly averaged discharge burnup about 7800 MW d/t U. The neutron flux distribution is calculated by means of program PUMA-C, which is periodically checked by comparison between calculated and measured values of 102 vanadium detectors. A comparison of the performance of other reactors type CANDU 600 (Point Lepreau, Gentilly 2, Wolsung) from the point of view of fuel strategy is also presented. The data to perform the comparison were obtained by means of the CANDU system of information exchange between users (COG). (Author)

  4. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Katchadjian, Pablo, E-mail: katcha@cnea.gov.ar; Desimone, Carlos, E-mail: katcha@cnea.gov.ar; Garcia, Alejandro, E-mail: katcha@cnea.gov.ar [Comisión Nacional de Energía Atómica, Depto. ENDE - INEND, Av. Gral. Paz 1499, Buenos Aires (Argentina); Antonaccio, Carlos; Schroeter, Fernando; Molina, Héctor [Nucleoeléctrica Argentina-SA, Arribeños 3619, Buenos Aires (Argentina)

    2015-03-31

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces.

  5. PUMA code simulation of recovery power transients after a short shutdown of the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    A simulation of recovery power transients after a short shutdown on Embalse nuclear power plant equilibrium core with slightly enriched uranium fuel was performed in order to know the response of the reactor under such conditions. Also, comparison against the same event in a natural uranium core were done. No significant restrictions were found in operating with enriched fuel in the conditions of the analyzed event and in fact, slightly differences arose with natural uranium fuels. (author)

  6. Code of dose assessment due to the discharges to the environment of liquid effluents of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Full text: A new methodology is presented to assess the evaluation of the radiological impact to the population, due to the discharges to the environment of liquid effluents of Embalse nuclear power plant (CNE), located in the Province of Cordoba of the Republica Argentina. In order to carry out the dose evaluation, a code denominated EDDELIQ was developed, in which the new criteria of radiological safety, recommended by the International Atomic Energy Agency are considered. In EDDELIQ code, the calculation of the radionuclide concentration in the water Embalse of Rio Tercero lake is made by means of a simple physical model of the type of complete mixture. The raised physical model is solved numerically by means of Runge Kutta method of second order. In this work, the dose assessment results obtained due to liquid effluents discharges of years 2000, 2001 and 2002 are presented. (author)

  7. Nuclear power plant life management: flow accelerated corrosion and chemical control. Application to Embalse Nuclear power plant

    International Nuclear Information System (INIS)

    The chemistry of a water-steam cycle is one of the main aspects of the Plant Life Management of a Nuclear Power Plant and it is important for the preservation, efficiency and availability of the whole system. In that sense this aspect has to be prioritized in any study whose aim is the life extension of the plant. In particular, the flow-assisted -corrosion or FAC is a problem that worldwide has been considered important due to the piping wall thinning that in some occasions has led to severe accidents. The FAC phenomena is not easy to be interpreted and addressed although nowadays there are some accepted models to understand and predict sensitive areas of the cycle. The objectives of the present paper have been: a) The construction of an integrated code that involves all the aspects that have influence on FAC, i.e., materials, composition, geometry, temperature and flow rate, quality, chemistry, etc.; b) Establish or adapting current models to the circuit of Embalse PHWR NPP; c) Identify new locations for inspection and wall thickness measurement in order to predict residual life; d) Compare different chemistries and e) handle large sets of inspection data. Among the results, new lines have been incorporated to the inspection schedule of the 2005' programmed outage. Also, the evaluation is part of the PLIM-PLEX programme at Embalse-N.A.S.A. in collaboration with C.N.E.A. is being carried out. (author)

  8. Corrosion behaviour of zirconium alloys in the autoclaves of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    The corrosion behaviour of zirconium alloys coupons attached to the holders of the autoclaves located out of core in the primary circuit of Embalse nuclear power plant is described. The Zr-2.5 Nb coupons of the autoclaves at the higher temperature (305 C degrees) and the Zry-4 coupons of the autoclaves at 265 and 305 C degrees installed in 1988 had a normal corrosion behaviour, after 3500 of full power days. While, the Zr-2.5 Nb coupons, at 265 C degrees, showed the presence of white oxide nuclei and a weight gain indicating an abnormal corrosion behaviour which might be attributed to the material microstructure. Complementary tests, made in the period September 1991-April 1993, showed that the abnormal corrosion behaviour observed for the Canadian coupons installed in 1983 was due to a surface contamination of the Zry-4 coupons and due to the microstructure of the Zr-2.5 Nb coupons. The normal corrosion behaviour for both alloys installed in 1986, showed that the resin ingress to the primary circuit that occurred in 1988, do not affect the performance of these materials. (author)

  9. National supply of reactivity control rods for Embalse nuclear power plant (CNE)

    International Nuclear Information System (INIS)

    The manufacture and supply on industrial scale of reactivity control rods for CNE (Embalse nuclear power plant) were developed by the National Atomic Energy Commission (CNEA) together with the private industry, as part of a program aimed to the substitution of imported supplies used in the operation of power plants by materials manufactured in Argentina. So far, the control rods were imported from Canada. In this work, the different development stages performed by CNEA and CONUAR S.A. are described, leading to the supply of a set of 21 cobalt rods to be included in a reactor of CNE in order to qualify this component. Among the main activities performed, the following stand out: specifications development, particularly those concerning to cobalt cores, evaluation of design documentation and elaboration of bidding conditions and a plan of manufacture and control. According to the results obtained during the service and the post-irradiation measurements, the design will be reviewed in order to undertake new manufacturing plans. (Author)

  10. Experimental ratio between the 'real' dose per organ and the calculated dose determined by means of the Embalse nuclear power plant's personal dosimeter

    International Nuclear Information System (INIS)

    The specific purpose of the study was to determine the experimental ratio between the reading of dosimeters used by the personnel of the Embalse nuclear power plant and the 'real' dose absorbed by the worker in different organs. An anthropomorphic phantom ALDERSON internal and externally loaded with approximately 150 TLD crystals was used. This phantom was placed in five enclosures that were usually occupied by workers of the Embalse nuclear power plant. In this way, the average dose per organ and the effective equivalent dosis in each enclosure could be calculated and compared with the personal dosimeters placed over the thorax and the conversion factor rem/rem for each enclosure was determined. The average factor resulting from the five considered enclosures was 0.73 rem/rem. This means that the personal dosimeters over value the real dosis absorbed by the personnel of the Embalse nuclear power plant in approximately 37%. (Author)

  11. Experience gained with the development of a performance test program for the monitoring and surveillance systems in the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    The monitoring and surveillance system for Embalse nuclear power plant are presented. The reactor, the nuclear fuel management, the equipments from monitoring and surveillance system, the activities developed by the AIEA experts in each mission of this test program and the management of the components for this test program in Argentine are described. (E.G.)

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

    International Nuclear Information System (INIS)

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

  13. Embalse NGS PLEX overview

    International Nuclear Information System (INIS)

    Embalse Nuclear Generating Station (ENGS), a CANDU 6 type with 648 MWe output, started operation in 1983. In the last 10 years it has shown an excellent performance with an average capacity factor of 88.25 %. An effective plant operation and management of the effects of aging on equipment, piping, accessories, components and structures that constitute plant principal systems by means of a continuos inspection program; is required. The end of the design life is foreseen for 2011. However, a political decision about the intention for an Embalse PLEX has been taken. In this paper an analysis of the Embalse-NGS Program for a possible Plant Life Extension (PLEx) is presented. A typical program for a CANDU PLEX has three main phases: Phase 1: Pre-project definition. Phase 2: Project Engineering and preparation. Phase 3: Project Implementation. However, there are also other programs, for example, In Service Inspection (ISI), Preventive / Predictive Maintenance (call-up cards), Routine Testing, Operating Routine, which focus on maintaining a high reliability of safety and process systems, as well. These are not included herein but their contributions to the Aging Assessment (AA) as well as to the performance of the plant are very important. (author)

  14. Gestión óptima de embalses en avenidas incorporando al concepto de incertidumbre : aplicación a embalses con central hidroeléctrica

    OpenAIRE

    Bianucci, Sandra Paola

    2013-01-01

    Esta tesis realiza una contribución metodológica al problema de la gestión óptima de embalses hidroeléctricos durante eventos de avenidas, considerando un enfoque estocástico y multiobjetivo. Para ello se propone una metodología de evaluación de estrategias de laminación en un contexto probabilístico y multiobjetivo. Además se desarrolla un entorno dinámico de laminación en tiempo real con pronósticos que combina un modelo de optimización y algoritmos de simulación. Estas herramientas asisten...

  15. Design of the containment structure in prestressed concrete for the Embalse-Cordoba Nuclear Power Plant

    International Nuclear Information System (INIS)

    The design of a typical prestressed concrete containment structure for a 600 MW Candu - PHW Reactor, presently under construction at Embalse - Cordoba, Argentina is briefly described. The structural behaviour , adcpted prestressing system and tendon pattern are described. Afterwards the evaluation of the prestressing forces as well as the losses assessment and the prestressing sequence are discussed. Finally, some conclusions are drawn in the light of the experience gained at different stages of the construction. (Author)

  16. Real time simulator modelling for the nuclear power plant at Embalse

    International Nuclear Information System (INIS)

    A real time simulator for the Nuclear Power Plant at Embalse (CANDU 600 type) was developed. It runs in an ordinary personal computer with a Pentium processor. This simulator includes: spatial kinetic model with 14 power or flux zones for the reactor, with representation of Xenon, decay heat, temperature and void reactivity effects; spatial modeling of reactivity devices: liquid zones, absorber, adjuster and shut off rods; detailed representation of the primary side: two hydraulic loops with four equivalent coolant channels, four steam generators and primary pumps, collectors and pressurizer; auxiliary systems of the primary side (feed and bleed) with its pumps, tanks and valves; full secondary side: four valve systems for feeding steam generators, pumps, condenser, condenser steam discharge valve, turbine inlet valve and auxiliary systems; turbine and related systems: high and low-pressure turbine with all its steam or water extractions, reheater and four preheater devices; all reactivity control operations: power increase, power step backs, and power setbacks; reactor and turbine trip; turbine speed and frequency control. Turbine synchronization and start up; simulation of the normal (turbine controls reactor) of alternative power control mode (reactor controls turbine) using the steam generator pressure at the secondary side. Steam generator pressure and level control; alarm signals for warning the operator about abnormal events: overpassing of limit values for pressure or temperatures, primary or secondary pump trips or some special operations; malfunctions for valves, pumps and liquid zones. The simulator consists of two Windows applications: one of them is the 'engine' that performs the simulation. The other one shows to the user what is happening by means of screens where he can operate the system. The communication between both applications is done using the Dynamic Data Exchange (DDE) method. Screens for viewing the different parameter values of primary

  17. Adjustment of the thermohydraulic NUCIRC 2.0 code to the present aging conditions of the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    This work gives a description of the adjustment process of NUCIRC code to the actual aging conditions of Embalse nuclear power plant. For this adjustment the flow of the fuel channels of the primary heat transport system (PHTS) is calculated using the channel heat balance flow (CHBF) methodology. Then roughness and the localized loss of charge are modified in NUCIRC code for different groups of channels. These adjustments are done in way to fit by regions the channels flows calculated with NUCIRC to the CHBF flows. The fitting results in a discrepancy by regions of less than 0,1% and an average quadratic error of 5% approximately. These values indicate that the code NUCIRC is right adjusted for critical channel power calculations and aging tracking of PHTS. (author)

  18. Maintenance and life assessment of steam generators at Embalse Nuclear Station

    International Nuclear Information System (INIS)

    Full text: The Embalse Nuclear Generating Station (ENGS) has four vertical I-800 U-tubes Steam Generators (SGs) manufactured by Babcock and Wilcox (B and W). They are one of the most important components from the point of view of safety and cost-related elements for potential life extensions in case of a replacement thereof. A Plant Life Management program has commenced covering the entire plant and one of the first pilot study was the SG Life Assessment (LA), which consisted in a systematic way to evaluate the aging mechanisms focused on the plant refurbishment and life extension. Because of this, maintenance-based ageing assessment from beginning of operation has been analyzed and LA-frame maintenance and inspections programs were carried out. The most important taken actions have been the Eddy Current (EC) In Service Inspection Program (ISI) which performs 100% of the tubes of two SG every 1.5 years started in 1992, the mechanical cleaning by blasting of the internal tube surface, the sludge removal from the secondary side tubesheet, the divider plate replacement, the installation of antivibration bars (AVB's), installation of TSP inspection ports and an exhaustive inspection of the secondary internals as a preliminary result of the LA. The most relevant aging mechanism up to 2004 was the Flow Accelerated Corrosion (FAC) of U-bend supports and consequent fretting of tubes. The eddy current inspections allowed the fretting degradation to be detected and mitigated by installing AVB's. Currently, efficiency of this mitigating action is followed by vibration measurements and visual inspections. However, other degradation mechanism that could have origin due to the Ubend FAC like loose part damage (LPD) it is being analyzed since could be an issue in the near future. At present, FAC degradation on the cold leg side and sludge deposition on the hot leg side of the carbon steel Tube Support Plates (TSP) are the main ageing issues at the point that SGs life extension is

  19. Maintenance and life assessment of steam generators at Embalse Nuclear Station

    International Nuclear Information System (INIS)

    The Embalse Nuclear Generating Station (ENGS) has four vertical I-800 U-tubes Steam Generators (SGs) manufactured by Babcock and Wilcox (B and W). They are one of the most important components from the point of view of safety and cost-related elements for potential life extensions in case of a replacement thereof. A Life Management program has been started covering the entire plant and starting with the Life Assessment (LA) of this component which consists in a systematic way to evaluate aging mechanisms focused on the plant refurbishment and life extension. Because of this, maintenance-based ageing assessment from beginning of operation is analyzed and current LA-frame maintenance and inspections programs are carried out in order to maintain a high availability of the SGs then to enable the planning for the plant life extension. The most important taken actions have been the Eddy Current (EC) In Service Inspection program which performs 100% of the tubes of two SG every 1.5 years started in 1992, the mechanical cleaning by blasting of the internal tube surface, the sludge removal from the secondary side tubesheet, the divider plate replacement, the installation of antivibration bars (AVB's), installation of TSP inspection ports and an exhaustive inspection of the secondary internals as a preliminary result of the Life Assessment started during early 2000. The most relevant aging mechanism up to 2004 was the Flow Accelerated Corrosion (FAC) of U-bend supports and consequent fretting of tubes. The eddy current inspections allowed the fretting degradation to be detected and mitigated by installing AVB's. Currently, efficiency of this mitigating action is being performed by vibration measurements and visual inspections. However, other degradation mechanism that could have origin due to the U-bend FAC like loose part damage (LPD) is being to be analyzed since could be an issue in the future. At present, FAC degradation on the cold leg side and sludge deposition on the

  20. Optimización del Embalse de una Central Hidroeléctrica situada en el río Yarjip (India)

    OpenAIRE

    Bourguignon, Jonathan

    2011-01-01

    Premi al millor Projecte de Fi de Carrera presentat durant l'any 2011 en l'àmbit d'Optimització de Recursos que atorga DOW CHEMICAL IBÉRICA El presente proyecto fin de carrera forma parte de los estudios realizados para un conjunto de tres centrales hidroeléctricas, situadas en India, proyectadas por la empresa Velcan Energy. Este conjunto de centrales está regulado por un único embalse de agua, y alcanzará una potencia de 500MW. El proyecto fin de carrera presentado tiene como ob...

  1. Safety and availability of the fuel handling system at Embalse nuclear power plant

    International Nuclear Information System (INIS)

    The paper attempts the Fuel Handling (F/H) System maintenance and operating methodology at the Embalse Power Station. It doesn't refer to the F/H process, because it's common and well known by all the CANDU Stations. Instead of that, the presentation will be focused on people qualification, training and selection. Also the key subjects for a smooth and successful operation. Additionally will be remarked the human aspect and the role of the person in the organization. The safe and reliable operation of the CNE Fuel Handling System has been always target, supported by the operational experience. The accountability and fitness for the job were the main qualification for the crew members. They have very clear their role and the importance of equipment which they are operating or manipulating. The person who has greater experience and responsibility must struggle continuously to keep the safe and confident operation. Also we have to increase permanently our knowledge with a greater training and experience exchange with another CANDU 6 Station, like this Conference which let us to grow as persons and technicians. It also allows our utility to have access to other realities and work methods. (authors)

  2. Distribution of amines and organic acids in the secondary side of Embalse Nuclear Power Station

    International Nuclear Information System (INIS)

    In this work we summarized the distribution of amines and organic acids generated by the thermal decomposition of morpholine in the secondary side of Embalse NPP. Sampling and analytical procedures to determine the concentration of formic, acetic and glycolic acids, morpholine, ammonia, methylamine, ethanolamine and 2(2-aminoethoxy)ethanol are described. Two sets of samples were collected in March 1995 and October 1996 in the following points: main steam line, composite steam generator blowdown, moisture separator, condensate extraction pump discharge and outlet feed pump. The general trend of the product distribution along the secondary side is similar to that reported for other CANDU NPP. In CNE methylamine and ethanolamine are more abundant than 2(2-aminoethoxy)ethanol due to faster decomposition of morpholine and less oxidizing conditions. Ammonia, and methylamine concentrate in the steam because of the lack of a de-aerator. The volatility of ethanolamine is low and its concentration in the steam generator is high. It could help to neutralize acid conditions in crevices and sludges. The concentration of organic acids in CNE is low as compared with other CANDU NPP, with formic acid being the predominant species. Differences in the relative concentrations of morpholine degradation products as compared to other CANDU NPP are discussed. (author)

  3. CNE (Embalse nuclear power plant): probabilistic safety study. Loss of service water. Probabilistic evaluation and analysis through events sequence

    International Nuclear Information System (INIS)

    This work is part of a study on the service water systems of the Embalse nuclear power plant from a safety point of view. The faults of service water systems of high and low pressure that can lead to situations threatening the plant safety were analyzed in a previous report. The event 'total loss of low pressure service water' causes the largest number of such conditions. Such event is an operational incident that can lead to an accident situation due to faults in the required process systems or by omission of a procedure. The annual frequency of the event 'total loss of low pressure service water' is calculated. The main contribution comes from pump failure. The evaluation of the accident sequences shows that the most direct way to the liberation of fission products is the loss of steam generators as heat sink. The contributions to small and large LOCA and electric supply loss are analyzed. The sequence that leads to tritium release through boiling of moderator is also evaluated. (Author)

  4. Analysis of liquid relief valves opening demand during pressure increase abnormal scenarios at Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Two hypothetical scenarios have been analyzed where, after an initiating event, Embalse nuclear power plant primary heat transport system could undergo a pressure increase. These abnormal events are a loss of feedwater to the steam generators and a loss of Class IV power supply with Class III restoration. This analysis focuses on primary system liquid relief valves action, specially on their opening demand. Calculation results show that even when these valves are expected to open during the transient, primary system maximum allowable pressure would not be exceeded if they failed to open. System response was also studied in case that one of these relief valves did not close once primary system pressure decreases. For the scenario of loss of feedwater to steam generators, if the degasser-condenser could not be bottled-up, Emergency Cooling Injection conditions would be reached due to a continuos loss of coolant. In case of loss of Class IV -and assuming degasser-condenser bottling-up as service water would not be available- it was observed that primary system should remain pressurized, and with core cooled by thermo siphoning mechanism. (author)

  5. Treatment of main heat transport system of Embalse Nuclear Power Plant with hydrazine at 150 deg C

    International Nuclear Information System (INIS)

    Ion exchange resins entrance to the main heat transport system of Embalse Nuclear Power Plant in April 1988 produced an increase of crud transport in the media, an increase of D2 evolution and mild steel corrosion rates. The removal of aggressive species from steady zones and a soft passivation of surfaces using hydrazine at moderate temperature, was recommended. The aim of this treatment was a partial dissolution of superficial defective oxides followed by the build up of a protective, homogeneous and adherent layer, to reduce generalized corrosion rate to historical values. The technique consisted of successive additions of the reagent solution to complete the prefixed amount, keeping a constant temperature of 150-152 deg C during 26 hours with continuous filtration through 1um mechanical filter, followed by a period at 180 deg C. Reagent addition was limited by ammonia concentration increase due to decomposition of hydrazine. Crud evolution was according to start up operation. Latter chemical control of the media consumes a 1000 litres resin bed. The results of this very soft treatment compatible with the start up operation of the plant, are very promising from the point of view that transported crud, deuterium concentration and corrosion rates decreased to the normal values before the mentioned event. (Author)

  6. Simulation of a hypothetical liquid relief valve failure (open) at Embalse nuclear power plant when a reactor shutdown is considered

    International Nuclear Information System (INIS)

    The study of the spurious opening of the liquid relief valves is of great interest in CANDU nuclear power plants because this could lead to a loss of coolant through the degasser-condenser relief valves, and implies an undesirable intermittent opening/closure of them. In fact, there is a specific procedure to follow at Embalse nuclear power plant whenever this abnormal situation occurs. This procedure contains a section where a reactor trip is considered. Really, automatic reactor trip is not accepted to occur. No trip parameters set points are through to be reached (neutronic or process). However, the procedure considers the situation where the reactor does trip. We analyzed the plant behavior when a reactor shutdown is triggered. Our objective was to assess if after this trip, the procedure can lead the plant to a safe situation, preventing high pressures in the degasser-condenser and with the inventory recovered in the storage tank. The case was analyzed with Firebird III, Mod. 1.0 code. Two situations were considered: trip at 40 sec. and trip at 180 sec. after the liquid relief valve failed opened (the latter when the degasser-condenser fills up). Procedure analysis and code simulations showed that following the steps recommended, provided the liquid relief valve can be closed manually, the inventory that enters the degasser-condenser from the heat transport primary system through the failed valve could be recovered in the storage tank, leading the plant to shutdown in safe conditions, and preventing the degasser-condenser relief valves setpoint from being reached. (author). 3 refs., 10 figs

  7. Welding with the TIG automatic process of the end fittings for the execution of the Embalse nuclear power plant fuel channel rechange

    International Nuclear Information System (INIS)

    The present work describes the methodology for the cutting of the existing welding and subsequent welding applied by the TIG process of the coupling composed by the shroud ring and the end fitting ring from one of Embalse nuclear power plant's fuel channels. The replacement will be previously determined by the SLAR-ETTE mechanism where a displacement operated among the Gartner Spring rings, the pressure tubes are separated from the Calandria tubes. The welding to be carried out has the function of stamping the CO2 annular gas (thermal insulator) circulating between the pressure tube and the Calandria one during the functioning of the plant. (Author)

  8. Temperature in the Primary Heat Transport Pump Bearing of the Nuclear Power Plant 'Embalse Rio Tercero' in view of the Cutting of the Service Water

    International Nuclear Information System (INIS)

    This study contains the analysis of the Primary Heat Transport Pump Bearing of the Nuclear Power Plant 'Embalse Rio Tercero', Cordoba, Argentine, in view of the cutting of the Service Water refrigeration which cools the Gland Seal System.This takes two ways: One is the study of the temperature rise of the water that cools the carbon bearing and the time involved.This is supported upon manuals and drawings.The other, on the temperature distribution in different operating conditions.This has been done by the simulation of the normal and transient conditions in the software COSMOS/M

  9. Flow accelerated corrosion and life management of the secondary circuit of the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Flow accelerated corrosion is a matter of concern in secondary circuits of nuclear power plants as well as in fossil fired plants. It contributes to the piping wall thinning and to the corrosion products transport to the steam generators. Because it is a generalized corrosion phenomena, could address to extensive failures. In that sense the plants conduct extensive programs of surveillance of piping degradation. Because the problem involves many variables like alloys, water chemistry and hydrodynamics several models have been proposed in the literature. In the present paper the variables have been organized in a spreadsheet which allows the calculation of normalized risk factors. (author)

  10. Una aproximación sedimentológica al aterramiento de embalses y la erosión en cuencas de montaña: el embalse de Barasona y la cuenca de Esera-Isábera (Pirineos centrales, Huesca)

    OpenAIRE

    Valero-Garcés, Blas L.; Navas Izquierdo, Ana; Machín Gayarre, Javier

    1997-01-01

    [ES] El estudio sedimentológico del embalse de Barasona (Pirineos Centrales, Huesca) y su cuenca de drenaje ilustra la variabilidad espacial y temporal de los procesos de erosión, transporte y sedímentación en- cuencas de montaña. El análisis de 20 sondeos y tres perfiles ha permitido caracterizar el sedimento, reconstruir tridimensionalmente el relleno del vaso y proponer un modelo deposicional dominado por las fluctuaciones en el régimen de aporte de los ríos. Las variaciones en la composic...

  11. Spectroscopic verification of fuel bundles at Embalse using CdZnTe

    International Nuclear Information System (INIS)

    The Central Nuclear Embalse is a Candu-6 nuclear power station in Argentina. In support of the International Atomic Energy Agency plan to implement remote monitoring at this site, we have developed and tested a prototype underwater spent-fuel verification system based on coplanar-grid cadmium-zinc-telluride (CdZnTe) technology. The system uses the 137 Cs gamma ray signature, and is designed for minimal interference to the operator and eventual unattended operation: Test results suggest that the method is very likely to succeed. (author)

  12. Desarrollo de proveedores para la industria nuclear argentina Visión desde las Centrales Nucleares

    Directory of Open Access Journals (Sweden)

    DOMINGO QUILICI

    2013-06-01

    Full Text Available Frente al inicio de una nueva etapa en la instalación de capacidad núcleo eléctrica en el país, se recorrerá la historia del desarrollo de la industria nuclear nacional (1964-1986 en búsqueda de antecedentes útiles para esta nueva realidad. Partiendo de la intención de dar repuesta a las preguntas: ¿Por qué se decidió tan tempranamente construir una central nuclear (en adelante CN; ¿por qué se decidió comprarla con una modalidad particular de los contratos “llave en mano”, en vez del desarrollo de una versión “criolla”? Y cuál fue el significado de la apertura del “paquete tecnológico” en aquel momento; se indagará sobre los antecedentes del desarrollo de proveedores para la industria nuclear en la Argentina. Se describirán las acciones que llevaron a la compra de las centrales de Atucha I, Embalse y Atucha II y como a partir de esas decisiones se implementaron políticas para maximizar la participación nacional en la construcción de las mismas y para la transferencia de tecnología del exterior hacia la industria local. Se analizará el Plan Nuclear puesto en vigencia a fines de los años setenta, desde el punto de vista de su influencia sobre el desarrollo tecnológico endógeno. Abstract The history of the development of national nuclear industry (1964-1986 will be reviewed in the search of useful patterns for the present new phase in the installation of nucleo-electric capacity in the country Precedents of development of suppliers for the argentinean nuclear industry will be considered, taking as starting point the following questions: Why the early decision of constructing a Nuclear Power Plant was taken? Why was it decided to buy it under a peculiar version of a turnkey contract instead of developing a “native” design? What were the implications of opening “technological packages” at that time? Actions leading to the construction of Atucha I, Embalse and Atucha II stations will be described, as well

  13. Application of concepts contained in the NUSS programme to the formulation of the emergency plan for the Embalse nuclear plant

    International Nuclear Information System (INIS)

    The paper describes the basic criteria adopted by the body responsible when drawing up the general emergency plan for the second Argentine nuclear plant, which is intended to mitigate the radiological consequences to the plant personnel, the public at large and the environment in the face of different assumptions with regard to the accident. When developing this general emergency plan particular consideration was given to the criteria established by the Argentine Regulatory Body, with the NUSS safety guides and codes of practice being used as guidelines after adaptation to the local infrastructure and specific features. There is discussion of the counter measures required in the affected off-site areas during the initial and intermediate stages of the emergency in order to avoid non-stochastic effects and to reduce the probability of stochastic effects. During the initial phase there is stress on the aim of minimizing the inhalation dose and external exposure from the radioactive cloud, with the taking of cover, simple respiratory protection, thyroid blocking and control of accesses and exits being considered the principal counteractions. In the intermediate phase of the emergency, during which the dose is delivered chiefly by radiation stemming from the deposit of radioactive material on the ground, evacuation as the main countermeasure envisaged is decided upon only on the basis of previous radiological measurement data. The paper describes the basic criteria adopted to identify the different intervention levels; the relevant action to be taken; the procedure for declaring an emergency; the machinery for communicating with the public and the various organizations involved; the responsibility of each of those organizations; the areas of application of the various countermeasures foreseen, and the administrative and legal framework. A logic diagram is the basic conceptual scheme used as the point of departure for the formulation of the general emergency plan and

  14. Embalse steam generators - status in 2009

    International Nuclear Information System (INIS)

    The Embalse Nuclear Generating Station (ENGS) is a CANDU 6, a pressurized heavy water plant, with a net capacity of 648 MW. The primary heat transport system at Embalse includes four Steam Generators (SGs) manufactured by Babcock and Wilcox Canada (B and W). These steam generators are vertical recirculating heat exchangers with Incoloy 800 inverted U-tubes and an integral preheater. Embalse SGs performed very well until the late 1990s, when an increase in tube fretting was noticed in the U-bend region. In-service inspection in 2002 and 2004 confirmed that the cause of the tube fretting was flow accelerated corrosion (FAC) damage of scallop bar supports in the U-bend region. The straight leg tube support plates (TSPs) have also been degrading. Degradation was worst at the top support plates, and it was in the form of material loss on the cold leg. The hot leg TSPs were heavily fouled with deposits and flow areas were blocked. Visual inspections and subsequent studies showed that the cause of the TSP degradation was also FAC. The Embalse SGs have carbon steel supports that make them susceptible to FAC. To mitigate the effects of degraded tube support structures, three additional sets of anti-vibration bars were installed in the U-bend regions of all four steam generators in 2004. In 2007, an improved secondary-side chemistry specification was implemented to reduce the FAC rate and the hot leg TSPs was waterlanced. A root cause analysis and condition assessment was performed for the tube supports in 2007. Fitness for Service (FFS) evaluation was completed using the Canadian Industry Guidelines for steam generator tubes. The steam generators were returned to service and the plant has operated without another forced outage to date. The FAC degradation of the carbon steel U-bend tube support systems has had the most significant impact on the plant operation causing a number of forced outages. The discovery of the extent of TSP degradation and difficulties to repair TSPs

  15. Replacement of steam generators for Embalse NGS - the steam generator cartridge design and manufacturing issues, localization and site assembly challenges

    International Nuclear Information System (INIS)

    Embalse Nuclear Generating Station (Central Nuclear Embalse) was placed in service in 1983 and the outage for refurbishment is foreseen for 2011/2012. Embalse is equipped with four vertical inverted 'U' tube-type Steam Generators (SG) with integral preheater, I-800 tubes and carbon steel internals. Between 2002-2006, the owner assessed the potential for SG life extension; Nucleoelectrica Argentina S.A. (NA-SA) and AECL and a number of actions were completed towards meeting this objective (i.e.: primary divider plate replacement, additional U Bend support and inspection port installation). However, degradation of the tube supports (carbon steel broached plate) and U-bend supports due to Flow-accelerated corrosion (FAC) compromised the possibility for life extension of these Steam Generators. This issue, coupled with the plan to increase the plant power output during the life extension of the station, resulted in the strategic decision by NA-SA, to replace the Steam Generators. Several options were considered for SG replacement: In-situ replacement of the SG tube bundle, the original steam drum to be re-used; Removal and replacement of the entire SG (including the steam drum); and, Replacement of the bottom portion of the SG, i.e. the shell, the tube bundle, the tube sheet, the primary head and its internals and the primary nozzles with a factory assembled cartridge (collectively called the 'SG cartridge'). In this option, the original steam drum would be retained for the extended life. The final decision, based on the recommendations from the Life Assessment Study performed during the Pre-project Condition Assessment Process, is to replace only the Steam Generator cartridges. NA-SA requested AECL's support for the preparation of the Technical Specification for the replacement cartridges, allowing for the higher plant output. This paper presents the design basis for the technical requirements covered in the Technical Specification. The specified requirements include

  16. Planktonic crustacean assemblages of three reservoirs from the Mexican Central Plateau: relationships with biotic and abiotic factors Crustáceos planctónicos de tres embalses de la Mesa Central Mexicana: relaciones con factores bióticos y abióticos

    Directory of Open Access Journals (Sweden)

    Gloria Ana María Arroyo Bustos

    2008-03-01

    Full Text Available The reservoirs Trinidad Fabela (TF, Ignacio Ramírez (IR and Tepuxtepec (T are located along an altitude gradient in the upper Lerma Basin of the Mexican Central Plateau. Between July 1993 and June 1994, the planktonic crustacean assemblages of these systems were dominated by seven cladoceran species and five copepod species. Specific richness ranged from 13 species in TF to 16 species in T, out of a total 20 species. Nine species were common to all three systems, while the rest were absent from at least one reservoir. Canonic correspondence analysis showed that the structure and seasonal variation of these assemblages are regulated by factors directly related (transparency and dissolved oxygen or inversely related (turbidity, temperature, mineralization and eutrophication to the altitude at which the reservoirs are located. TF had the lowest levels of mineralization and the lowest specific richness, as well as the highest plankton diversity and mean density, while T had the highest mineralization and highest specific richness, but showed the lowest density. Crustacean mean size was smaller in T than in TF, possibly due to predation by fish in the former system and the presence of fish predators (waterfowl in the latter, as well as the impact of the different hydrological regime and release schedules of the reservoirs.Se estudiaron los embalses Trinidad Fabela (TF, Ignacio Ramírez (IR y Tepuxtepec (T que se localizan en un gradiente de altitud en la subcuenca del Alto Lerma en la Mesa Central de México. La asociación de crustáceos planctónicos estuvo dominada por siete especies de cladóceros y cinco copépodos y la riqueza específica varió entre 13 y 16 especies con un total de 20 especies; nueve de éstas resultaron comunes a todos los embalses y las otras no se encontraron en al menos uno de ellos. El análisis de correspondencias canónicas mostró que la estructura y la variación estacional de las asociaciones de crustáceos planct

  17. Embalse PLiM/PLEx

    International Nuclear Information System (INIS)

    The objective of the presentation is to show the current state of the Embalse PLiM/PLEx (Plant life management/Plant life extension) program (and its results) which strongly focuses on PLEx decision/implementation; to present the methodologies used and the PLEx plan is described. The objectives of the PLiM/PLEx program is to achieve the long term operation, maintaining a high level of safety and plant performance; to identify the necessary modifications for PLEx and its alternatives. This will enable to make de economic assessment and justify the life extension against other sources of energy. (author)

  18. Rol del fallo mecánico en la optimización del mantenimiento en una central nuclear//Role of the mechanical failure during the maintenance optimization in the nuclear power plant

    OpenAIRE

    Antonio Torres - Valle

    2012-01-01

    Entre las más recientes aplicaciones del Análisis Probabilista de Seguridad (1997 – 2003) de la Central Nuclear Embalse en Argentina, está el Programa de Mantenimiento Orientado a la Seguridad (2006– 2009) el cual se ha desarrollado con el empleo de la metodología de Mantenimiento Centrado en la Confiabilidad (RCM en inglés). El objetivo general del artículo es demostrar la alta contribución de los fallos mecánicos en el diseño de las políticas de mantenimiento de varios sistemas de la instal...

  19. Modelos conceptuales de abundancia de fitoplancton asociados a la heterogeneidad espacial en el Embalse Rapel (Chile central Conceptual models of phytoplankton abundance associated to spatial heterogeneity at the Rapel reservoir (central Chile

    Directory of Open Access Journals (Sweden)

    GINGER MARTÍNEZ

    2003-06-01

    Full Text Available La heterogénea morfología de los sistemas acuáticos regulados genera patrones de abundancia y gatilla una respuesta diferencial de los ensambles planctónicos. Un ejemplo de ello ocurre en el Embalse Rapel (34º10' S, 71º29' O. Un gradiente morfoedáfico longitudinal y condiciones hidrodinámicas localizadas producen complejidad espacial en esta cuenca dendrítica, lo que ha sido propuesto como probable factor causal de las diferencias de abundancia fitoplanctónica entre distintos sectores del embalse. En el presente estudio se proponen mecanismos y modelos conceptuales de abundancia de fitoplancton y para ello se describieron patrones de distribución de algas en tres sectores del embalse: Las Balsas, Alhué y El Muro. Posteriormente se identificaron las principales variables predictoras de abundancia fitoplanctónica y se estableció un modelo de funcionamiento específico para cada sector del embalse. A partir de una base de datos bibliográficos se obtuvo información de abundancia total de fitoplancton y de variables físicas y químicas desde cuatro estaciones de muestreo representativas de cada sector además del sector de Confluencia entre los sectores Las Balsas y Alhué. Se realizaron análisis de clasificación jerárquica y de componentes principales para la descripción del patrón espacial y a través de un análisis de regresión múltiple se identificaron las variables predictoras en cada estación de muestreo. Los resultados mostraron dos agrupamientos significativos: 1 = Las Balsas-Muro y 2 = Alhué-Confluencia. Las variables físicas y químicas también se segregaron espacialmente en función de las estaciones de muestreo. Se detectaron diferentes conjuntos de variables predictoras en cada sector del embalse. En la estación Las Balsas, las variables asociadas a la abundancia de fitoplancton fueron la temperatura, concentración de fósforo soluble y conductividad específica. Por el contrario, en las estaciones Alhué y

  20. Nuclear Energy in Central Europe 98, Proceedings

    International Nuclear Information System (INIS)

    Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 63 articles from Slovenia, sorounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Nuclear Methods, Reactor Physics, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation and Nuclear Waste disposal

  1. Operating Experience and Condition Assessment of Spent Fuel Dry Storage Silos and Spent Fuel Pool at Embalse NPP

    International Nuclear Information System (INIS)

    At Embalse Nuclear Power Plant (NPP), spent fuel removed from the reactor core is placed in a carbon steel basket before it is removed from the Plant spent fuel storage pool. Then, baskets are carried in a shielding container to a storage silo, where they remain until their final disposal. The silo system consists in a concrete cylinder of 2.80 m external diameter and 0.85 m thick, internally lined with a carbon steel cylinder of 9.5 mm thick. This structure is supported by a 0.60 m thick concrete slab. This work reviews the Condition Assessment of Embalse Spent Fuel Dry Storage Silos and was performed following the procedures implemented in the Embalse Refurbishment Project. A review of nondestructive and destructive methods is presented so as to assess the condition of concrete and carbon steel of this structure. Future tasks to be performed in the Spent Fuel Pool is presented. (author)

  2. Separating rings detection in fuel channels of Embalse NPP

    International Nuclear Information System (INIS)

    The design specifications of Embalse Nuclear Power Plants (CANDU Type Reactor 600Mw) define the positions to be taken by 4 separating rings of the fuel channels. Experience has demonstrated the displacement possibility of the above mentioned rings. It means a risk of contact between pressure tube and calandria tube. In order to determine the position of separating rings, an inspection system based on Eddy Currents technique was developed by CNEA personnel. Detection is performed through two special probes operating according the ''emitter-receiver'' principle. Obtained signals and its relative position are recorded in a video tape and registered in paper. The probe is telecommanded by an automatic equipment. In this paper the construction and calibration of the detection equipment is described, as well as the propulsion. Final results are also outlined in the inspection carried out in November 1986 when an effective displacement of separating rings was verified from its design position in most of the inspected tubes

  3. Application of reliability centered maintenance to Embalse NPP

    International Nuclear Information System (INIS)

    One of the most recent applications of Probabilistic Safety Analysis to Embalse NPP is the Safety Oriented Maintenance Program developed through the Reliability Centered Maintenance (RCM) methodology. Such an application was carried out by a cooperated effort between the staff of nuclear safety department of NPP and experts from Instituto Superior de Tecnologias y Ciencias Aplicadas of Cuba. So far 6 technological systems have been analyzed with important results regarding the optimization of preventive and predictive maintenance program of those systems. Any tasks of RCM were automated via MOSEG code. The results of this study were focused on the elaboration and modification of the Preventive Program, prioritization of stocks, reorientation of predictive techniques and modification in the time parameters of maintenance. (author)

  4. Nuclear insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

    In the world outside the former Soviet Union, insurance industries in their respective domestic markets have pooled their resources so as to provide a secure and cost-effective conduit for the transaction of insurance business on behalf of the nuclear industry. These are the so-called nuclear pools. This paper explains the four main principles behind nuclear liability insurance and discusses their application to Central Europe and in particular to the problems facing the nuclear industry in Eastern Europe. (author)

  5. Composition and concentration of soluble and particulate matter in the coolant of the reactor primary cooling system of the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Nuclear power plants type PWR and PHWR (pressurized water reactor and pressurized heavy water reactor) have three coolant circuits which only exchange energy among them. The primary circuit, whose coolant extracts the reactor energy, the secondary circuit or water-steam cycle and the tertiary circuit which could be lake, river or sea water. The chemistry of the primary and secondary coolants is carefully controlled with the aim of minimizing the corrosion of structural materials. However, very low rates of corrosion are inevitable and one of the consequences of the corrosion processes is the presence of soluble and particulate matter in the coolant from where several problems associated with mass transfer arisen. In this way radioactive nuclides are transported out of the core to the steam generators, hydraulic resistance increases and heat transfer capability degrades. In the present paper some alternative techniques are proposed for the quantification of both, the particulate and soluble matter present in the coolant and their correspondent composition. Some results are also included and discussed. (author)

  6. Central Institute for Nuclear Research (1956 - 1979)

    International Nuclear Information System (INIS)

    The Central Institute for Nuclear Research (ZfK) of the Academy of Sciences of the GDR is presented. This first overall survey covers the development of the ZfK since 1956, the main research activities and results, a description of the departments responsible for the complex implementation of nuclear research, the social services for staff and the activities of different organizations in the largest central institute of the Academy of Sciences of the GDR. (author)

  7. Measurement of the power trasient and valve closing time, for the zone control system, during a programmed shutdown in August 1989 and its relation with the class IV partial loss event occurred on 27/12/88 in CNE (Embalse nuclear power plant)

    International Nuclear Information System (INIS)

    A description is made of a number of measurements performed during the programmed shutdown on Embalse nuclear power plant (CNE) (August 1989) to validate the existance of a reactivity insertion owing to the emptying of the liquid zone control system. In the event occurred on 27/12/88 when there was a partial loss Cl IV. Once the existance of this contribution was confirmed, the pertinent corrective measures were taken and the test was repeated to verify the effectiveness of the latter. The temporal evolution of a number of neutronic variables and process variables of the liquid zone system were stored in an IBM-PC XT equipped with analog-to-digital converters, for later analysis. (Author)

  8. Fitoplancton de embalses subtropicales del noroeste argentino.

    OpenAIRE

    María Mónica Salusso; Liliana Beatriz Moraña

    2014-01-01

    Los embalses Cabra Corral y El Tunal de la cuenca del Juramento (ACJ), constituyen los reservorios de mayor relevancia de la provincia de Salta (Argentina). Se analizó la composición y estructura del fitoplancton en ambas presas en febrero, mayo y octubre en el período 1998-2011, utilizando técnicas normalizadas. El inventario algal comprendió un total de 334 spp., siendo los grupos más diversos: Chlorophyta (116), Bacillariophyta (112) y Cianophyta (64). La abundancia y diversidad de especie...

  9. Central Bureau for Nuclear Measurements

    International Nuclear Information System (INIS)

    The main task of CBNM is defined as the specific programme Nuclear Measurements and Reference Materials. In the field of neutron data for standards, for fission and for fusion application, the nuclear charge distribution and odd-even effects for mass, charge and neutron number in the cold spontaneous fission of 252Cf were determined. X- and γ-ray emission probabilities were evaluated in the frame of an IAEA coordinated Research Project. The subthermal fission cross section measurements of 235U, 233U and 239Pu, were finalised. The dependence of the experimental weighting function of C6D6 detectors on thickness of several 56Fe samples was determined. Fusion data studies involved the development of a light-ion telescope with improved time - and energy resolution. Double differential cross-sections of 9Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO2), 523 (Al), 525 (Nb) and 526 (Nb). Progress was achieved in the preparation of dried solid spikes of uranium and plutonium for undiluted reprocessing input solution analysis. 10B and 6Li deposits were prepared for a redetermination of the neutron lifetime. Preliminary studies on speciation of trace metals in biological fluids were successful. Radioactive waste barrels were analysed by γ-scanning and blood samples were irradiated with 0.6 MeV neutrons. Exploratory research resulted in first measurements of transition radiation properties

  10. Nuclear energy options for Central Asia

    International Nuclear Information System (INIS)

    Full text: The five countries of Central Asia have a strong basis for the development of commercial nuclear energy. Several test reactors have operated within the region, including the Ak tau BN350 - a very advanced fast breeder reactor combined with a large water desalination plant. The Central Asian countries have a large cadre of well-trained nuclear scientists and engineers who could operate and maintain nuclear power plants and expanded nuclear fuel infrastructure as they evolve. The Central Asia region experiences significant demand for base-load energy in major population centers and industrial development areas. A well-developed electricity transmission grid could transmit nuclear-generated electricity from the power stations to the load centers. Finally, given the large land area and the relatively small population (in relation to the size of the region) there exist many remote and stable sites where nuclear generation centers can be sited and connected to the transmission grid. A good example is the Semipalatinsk Nuclear Test Site (STS) whose vast area could easily contain several nuclear power plants, which would be cooled by the water flow of the Irtish River. The Kazakhstan authorities have already identified several potential nuclear power plant sites within the national transmission system, the STS being one such prospective site. The large-scale availability of uranium in the region affords the uranium exporting countries - particularly Kazakhstan and Uzbekistan - significant leverage with international nuclear reactor vendors in establishing the terms for nuclear plant imports into the region. Such leverage could further be increased if multiple reactor orders are submitted, for instance by two or more countries ordering similar types of plants to be installed at various sites in their territories. The added value of the uranium exports from Central Asia does not have to be measured only in terms of supporting the development of fuel cycle

  11. Central depression of nuclear charge density distribution

    International Nuclear Information System (INIS)

    The center-depressed nuclear charge distributions are investigated with the parametrized distribution and the relativistic mean-field theory, and their corresponding charge form factors are worked out with the phase shift analysis method. The central depression of nuclear charge distribution of 46Ar and 44S is supported by the relativistic mean-field calculation. According to the calculation, the valence protons in 46Ar and 44S prefer to occupy the 1d3/2 state rather than the 2s1/2 state, which is different from that in the less neutron-rich argon and sulfur isotopes. As a result, the central proton densities of 46Ar and 44S are highly depressed, and so are their central charge densities. The charge form factors of some argon and sulfur isotopes are presented, and the minima of the charge form factors shift upward and inward when the central nuclear charge distributions are more depressed. Besides, the effect of the central depression on the charge form factors is studied with a parametrized distribution, when the root-mean-square charge radii remain constant.

  12. Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals; Determinacion de actividad por espectrometria gamma de radionucleidos presentes en tambores de residuos generados en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, J.C.; Fernandez, J. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, Ciudad Autonoma de Buenos Aires (Argentina)]. e-mail: jaguiar@cae.arn.gov.ar

    2006-07-01

    The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

  13. Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals

    International Nuclear Information System (INIS)

    The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

  14. Nuclear Safety in Central and Eastern Europe

    International Nuclear Information System (INIS)

    Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union. In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the ''Performance Evaluation Guide'', which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body. Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary

  15. Loss of power of a 220 VAC safety bus bar at Embalse NPP

    International Nuclear Information System (INIS)

    Embalse nuclear power plant is located at the Cordoba Province, 5 kilometres Southern the town of Embalse. It is equipped with one 600 MWe CANDU reactor. At the time of the event, which occurred on 11 October 2004, the plant was operating normally at full power. The Embalse nuclear power plant electrical power system buses are classified, in reliability decreasing order, into the following four different levels: 1) Class I: uninterrupted direct current supplies for safety related and other essential loads; 2) Class II: uninterrupted alternating current supplies for safety related and other essential loads; 3) Class III: alternating current supplies to essential auxiliaries which can tolerate the short interruption required until to start up and load the on-site standby generators and 4) Class IV: normal alternating current supplies to auxiliaries which can tolerate long duration interruptions without affecting personnel or equipment safety (Class IV is the normal source of power to Class III system). In particular, the Class II 220 VAC uninterrupted monophasic safety bus bars are composed by three 220 VAC subsystems powered by the following two sources of power: Class I uninterrupted safety bus bars (5551 BUA, BUB and BUC bars) and Class III secondary distribution 5433-MCC5 and MCC6. The Class II 220 VAC bus bars are normally powered from Class I bus bars through static monophasic inverters. Beside, in a static monophasic out of service case, Class II bus bar affected could be powered from Class III bus bars via a transformer stabilizer. Class II bus bars supplies power to both control computers and the AC instrumentation and control devices. When 220 VAC (Class II) 5542-BUC-monophasic-inverter failure was coincident with a subsequent independent failure to transfer to the Class III through static commuter 5542-SVR-C, a loss of the 220 VAC uninterrupted monophasic safety bus bar (Class II) event was caused. (author)

  16. Fitoplancton de embalses subtropicales del noroeste argentino.

    Directory of Open Access Journals (Sweden)

    María Mónica Salusso

    2014-12-01

    Full Text Available Los embalses Cabra Corral y El Tunal de la cuenca del Juramento (ACJ, constituyen los reservorios de mayor relevancia de la provincia de Salta (Argentina. Se analizó la composición y estructura del fitoplancton en ambas presas en febrero, mayo y octubre en el período 1998-2011, utilizando técnicas normalizadas. El inventario algal comprendió un total de 334 spp., siendo los grupos más diversos: Chlorophyta (116, Bacillariophyta (112 y Cianophyta (64. La abundancia y diversidad de especies estuvieron asociadas con los cambios en las descargas de agua. Los valores más altos de riqueza y diversidad específicas, se alcanzaron durante los períodos de lluvias, siendo inversa la situación en estiaje, cuando incrementó la biomasa total; excepto durante los picos de floraciones de Dinophyta. La aparición de cianobacterias con potencial tóxico fue más significativa en el verano tardío y otoño. A pesar de que el número total de especies registrado es alto comparado con otros reservorios subropicales, sólo unas pocas pueden ser consideradas como comunes o frecuentes (Aulacoseira granulata, Cyclotella meneghiniana, Sphaerocystis schroeteri, Chroomonas minuta. La biomasa estuvo asociada a nivel local con las precipitaciones y el manejo del nivel hidrométrico y a nivel regional con el área superficial de los reservorios.

  17. Towards Quantum Transport for Central Nuclear Reactions

    CERN Document Server

    Danielewicz, Pawel; Barker, Brent

    2016-01-01

    Nonequilibrium Green's functions represent a promising tool for describing central nuclear reactions. Even at the single-particle level, though, the Green's functions contain more information that computers may handle in the foreseeable future. In this study, we explore slab collisions in one dimension, first in the mean field approximation and demonstrate that only function elements close to the diagonal in arguments are relevant, in practice, for the reaction calculations. This bodes well for the application of the Green's functions to the reactions. Moreover we demonstrate that an initial state for a reaction calculation may be generated through adiabatic transformation of interactions. Finally, we report on our progress in incorporating correlations into the dynamic calculations.

  18. Central depression of the nuclear charge distribution

    International Nuclear Information System (INIS)

    As a systematic feature of all measured charge distributions we find a shift in the form-factor zeroes as compared to a simple folding model. To first order, this shift can be interpreted as resulting from the central depression w, caused by the Coulomb repulsion. Accounting for it leads to an increase in the surface width of nuclear charge distributions by 0.105 fm. This interpretation of the experimental findings is compared with the droplet model, which relates w with the compression modulus K and the asymmetry energy J. Accounting for w leads to an increase in the extrapolated nuclear matter density by 7.5%. However, this macroscopic model is not able to describe the experimental results in detail since w is also influenced by shell effects. HF+BCS calculations with effective Skyrme-type interactions reproduce part of the data, revealing the influence of shells on w. Here, too, there remain discrepancies in details. A level of accuracy is reached at which most probably also the skewness of the charge distribution must be taken into account. (orig.)

  19. Fourth Regional Meeting: Nuclear Energy in Central Europe, Proceedings

    International Nuclear Information System (INIS)

    Fourth Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 89 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accidents, Ageing and Integrity, Thermal Hydraulics, NPP Operation Experiance, Radioactive Waste Management, Environment and Other Aspects, Public and Nuclear Energy, SG Replacement and Plant Uprating.

  20. Rol del fallo mecánico en la optimización del mantenimiento en una central nuclear//Role of the mechanical failure during the maintenance optimization in the nuclear power plant

    Directory of Open Access Journals (Sweden)

    Antonio Torres-Valle

    2012-05-01

    Full Text Available Entre las más recientes aplicaciones del Análisis Probabilista de Seguridad (1997 – 2003 de la Central Nuclear Embalse en Argentina, está el Programa de Mantenimiento Orientado a la Seguridad (2006– 2009 el cual se ha desarrollado con el empleo de la metodología de Mantenimiento Centrado en la Confiabilidad (RCM en inglés. El objetivo general del artículo es demostrar la alta contribución de los fallos mecánicos en el diseño de las políticas de mantenimiento de varios sistemas de la instalación a través del empleo de la metodología RCM. La composición, estructura y políticas de explotación de los sistemas tecnológicos de muchas instalaciones con riesgo asociado, similares a las de los sistemas analizados en este estudio, permite inferir que los resultados que se obtendrán serán equivalentes de aplicarse la metodología RCM en dichas instalaciones. Palabras claves: mantenimiento centrado en la confiabilidad, mantenimiento predictivo, mantenimiento preventivo, fallo mecánico, seguridad, confiabilidad, riesgo.______________________________________________________________________________ Abstract One of the most recent applications of Probabilistic Safety Analysis (1997 – 2003 to Embalse Nuclear Power Plant in Argentina, is the Safety Oriented Maintenance Program (2006 – 2009 developed with employment of the Reliability Centered Maintenance (RCM methodology. The general objective of the paper is to demonstrate the high contribution of the mechanical failures in the maintenance program design through the RCM methodology. The composition, structure and operation strategies of the technological systems of many risk associated facilities, similar to the analysed systems included in this study, allow deduce that the results will equivalent in case of application of RCM methodology in such facilities. Key words: reliability centered maintenance (RCM, predictive maintenance, preventive maintenance, mechanical failure, safety

  1. The French national system for centralized accounting of nuclear materials

    International Nuclear Information System (INIS)

    The French national system for centralized accounting of nuclear materials located on French soil is described. Texts of accountancy regulations and operator's obligations, which determine the technical conditions for nuclear material management are presented. The NUclear Material Operation Declaration Form used for declaring changes in inventory is considered. The hardware configuration of the automated accounting system for nuclear materials consists of multiprocessor mini-computer, SUN computers, a SYBASE relational database manager and optical fiber network

  2. Central Institute of Nuclear Research Rossendorf 25 years old

    International Nuclear Information System (INIS)

    A colloquium dedicated the 25th anniversary of the foundation of the Central Institute for Nuclear Research of the GDR Academy of Sciences was held on January, 21st, '81. 13 papers were given which dealt with aspects of the institute's history as well as with modern trends in nuclear and solid state physics, nuclear energy and chemistry, radioisotope production, radiation protection and nuclear information. (author)

  3. Studies on the Optimal behavior of Energy Storage in Reservoirs of a Hydroelectric system; Estudios sobre el comportamiento optimo del almacenamiento de energia en embalses de sistema hidroelectrico

    Energy Technology Data Exchange (ETDEWEB)

    Macedo Faria, Breno; Franco Barbosa, Paulo Sergio [Universidad Estatal de Campinas (Brazil)

    2002-09-01

    This work aims at studying the results of an optimisation model applied to the Paranaiba river basin, Brazil. This system is made by the junction of three river branches located in a region with a well-defined seasonal hydrological behavior. The ratio between the total energy storage in the system and the active storage for every reservoir is evaluated from the optimal operational results. This relationship allows recognizing systematic patterns on the relative use for every reservoir, when compared to the entire system. The main parameters that define reservoir behavior are identified, with highlights on the position of the power station in the cascade, the relationship between the river flow and the active storage, and the installed capacity of the power station. In addition, the parameter hydrological scenario is also another factor that defines the relative use of the reservoirs. [Spanish] El modelo del presente trabajo tiene como objetivo estudiar los resultados de una optimizacion para el sistema hidroelectrico de la cuenca del rio Paranaiba, Brasil, la cual esta formada por la confluencia de tres rios en una region de distribucion de lluvias bien definidas en terminos hidrologicos. Se analiza la relacion entre la energia total almacenada en el sistema y el volumen util de cada embalse a partir de los resultados operativos optimos. Esta relacion permite identificar resultados sistematicos en lo que se refiere a la utilizacion de cada embalse, en comparacion con el uso del sistema como un todo. Se identifican los principales parametros responsables por el comportamiento de los embalses, destacando la influencia de la posicion de la central hidroelectrica en la cascada, de la relacion caudal/volumen util y de la potencia de central. Ademas, el parametro escenario hidrologico tambien es otro factor determinante en el uso relativo de los embalses.

  4. Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

    International Nuclear Information System (INIS)

    Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information

  5. Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals; Actividades regulatorias relacionadas con la modficacion de la frecuencia de las paradas programadas de las centrales nucleares argentinas

    Energy Technology Data Exchange (ETDEWEB)

    Marino, E.; Calvo, J.; Waldman, R.; Navarro, R

    2006-07-01

    The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

  6. Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals

    International Nuclear Information System (INIS)

    The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

  7. Parametric study of the TANDEM cycle fuel material balance between Angra-1 and Embalse

    International Nuclear Information System (INIS)

    The TANDEM cycle fuel material balance between the Angra-I PWR in Brazil and Embalse CANDU reactor in Argentina is estimated. The analysis considers the discharge burnup of Angra-I and a dilution ratio (decontaminated uranium dioxide from the PWR: natural uranium dioxide) of 1.9:1.0 for the fuel of the Embalse CANDU reactor. Parametric studies involving the MOX fuel have been carried out for different dilution ratios and different PWR discharge burnups. (author)

  8. Nuclear Power in South-Central Brazil

    International Nuclear Information System (INIS)

    The region of South-Central Brazil includes the states of Sao Paulo, Rio de Janeiro, Guanabara and Minas Gerais. The most recent power study was made by Canambra Engineering Consultants Limited. This group reported that the public-grid electricity output for the area in 1962 was 2.16 GW (average generation), with an installed capacity of 3.41 GW and annual mean load factor of 63.4; an increase in power requirements for 1970 was forecast, corresponding to an average output of 5.37 GW and an installed capacity of 8.3 GW. This forecast was based on an annual growth rate of 11.9% in generation. ''The energy requirements have grown at an average annual rate of 10.9% since 1955; however, the present forecast is based on the assumption of power being available as required, and hence includes the suppressed demand resulting from existing restrictions in generating and distribution capacity''

  9. Embalse NGS: Abnormal event procedures development lifecycle

    International Nuclear Information System (INIS)

    Based on the present used philosophy in Canada and in Atucha Nuclear Generating Station (Argentina) it was decided to develop the Abnormal Event Procedures (EOP's) in a logical diagram format. The EOP's have in general two parts: the diagnosis and the operative action to mitigate the event. Some serious incidents can be resolved by the EOP's, but the philosophy is first, to satisfy the EOP's requirements. Taking into account the operating experience, the Final Safety Report and the results of simulations done by appropriate codes, it was possible to obtain the corresponding sequence for each abnormal event. With the information available in the Control Room (windows, alarms, trends, etc) for each part of the EOP's was associated the instrumentation that the operator must observe. 3 figs

  10. 30 years of Central Institute for Nuclear Research at Rossendorf

    International Nuclear Information System (INIS)

    A celebration and a scientific colloquium dedicated the 30th anniversary of the foundation of the Central Institute for Nuclear Research (CINR) of the GDR Academy of Sciences were held on January, 23rd and 24th, '86 at Rossendorf. The speaches and lectures given by the president of the GDR Academy of Sciences and by scientists of the CINR dealt with problems of policy of science, history of the CINR, nuclear methods, microelectronics, nuclear energy research, development and production of radioisotopes and scientific instruments. (author)

  11. U. S. Central Station Nuclear Power Plants: operating history

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission.

  12. U.S. Central Station Nuclear Power Plants: operating history

    International Nuclear Information System (INIS)

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

  13. Centrales nucleares en España : el parón nuclear

    OpenAIRE

    Sanz Díaz, Benito (1949-)

    1984-01-01

    Este libro constituye una oportuna y valiosa contribución a ese necesario debate nacional sobre la energía nuclear. Tiene como objetivo la central nuclear de Cofrentes, una de las postreras y más singulares —tanto por su modelo como por su emplazamiento e historia de construcción— de las centrales nucleares que entrarán en funcionamiento en nuestro país. El libro, sin embargo, aporta información sobre la totalidad del programa nuclear español y su permanente visión económica garantiza la vía ...

  14. The nuclear sector in Russia and Central Europe

    International Nuclear Information System (INIS)

    This document is a compilation of texts presented during a workshop at the French National Assembly (Paris, December 2, 1993). Participants are political, economical, technical or military specialists of the nuclear question in Eastern countries and Russia and comes from various French, European or international organisations involved in nuclear industry. The aim of the workshop is to debate about the economical and safety aspects of nuclear installations in Eastern and Central Europe countries, and about the financial and human means that occidental countries can provide for the improvement of installations safety. Also political and military aspects of the international control of nuclear trade, nuclear weapons and fissile materials management in the Independent States Community is discussed. (J.S.). 4 figs., 13 tabs

  15. Nuclear Research and Development Institutes in Central and Eastern Europe

    International Nuclear Information System (INIS)

    The science and technology (S and T) sector is faced today with complex and diverse challenges. National science budgets are under pressure, and many countries are changing how research and development (R and D) is funded, reducing direct subsidies and introducing competition for both governmental and alternative sources of revenue. On the other hand, the transition toward knowledge-based economies is creating new opportunities in the S and T sector as governments look to it to foster economic growth through innovation. A number of countries in Central and Eastern Europe have recently joined the European Union (EU) which has defined the Lisbon Strategy to create a 'knowledge triangle' of research, education and innovation to underpin the European economic and social model, and economic growth. This strategy seeks to increase investment in science and technology across the EU to a target of 3% of GDP by 2010, with two-thirds of funds coming from the private sector. By comparison, funding for R and D in most Central and Eastern European countries is only around 1% GDP, of which about 90% is provided by the governments. R and D has become more international, reflecting a more interdependent and globalized world. R and D progress is not only of interest to individual countries but also tries to respond to the needs of a broader society. Governments still maintain national networks, but increasingly emphasize international cooperation, both to avoid duplication of expensive infrastructure, and because scientific excellence requires an exchange of ideas and cooperation that crosses borders. These challenges and opportunities directly impact the research and development institutes (RDIs), including the nuclear RDIs. It is important for the nuclear RDIs to take account of these trends in the broader S and T sector in their vision and strategy. Several nuclear RDIs have become very successful, but others are struggling to adapt. The challenges have been particularly severe

  16. Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

    International Nuclear Information System (INIS)

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.)

  17. El proceso de ocupación en la cuenca del embalse la mariposa y sus efectos de deterioro en el embalse y sus aguas

    Directory of Open Access Journals (Sweden)

    Néstor Martínez Tirado

    2000-01-01

    Full Text Available El embalse La Mariposa localizado en la parte alta de la cuenca del río El Valle, municipio Los Salias, estado Miranda, Venezuela ha venido cumpliendo el papel de receptor de aguas crudas para abastecer una considerable parte de las demandas de agua potable por parte de la ciudad de Caracas. En 1949, cuando se pone en funcionamiento el Sistema, Caracas albergaba menos de un millón de habitantes, mientras que en la cuenca del Embalse se ubicaban unas 650 viviendas con una población aproximada de 3.000 habitantes. Actualmente, la situación ha cambiado radicalmente, producto del crecimiento poblacional y la expansión física urbana, con impactos directos de ocupación en la cuenca del Embalse, trayendo consigo factores que afectan la capacidad receptora del sistema y la calidad de sus aguas. Metodológicamente se ha procedido a levantar una cartografía básica utilizando S.I.G y posteriormente se ha realizado un trabajo de campo para indagar la magnitud del proceso de ocupación e identificar los factores generadores de deterioro al Sistema. Se ha detectado un fuerte proceso de sedimentación que afecta el espacio receptor del Embalse y sus aguas.

  18. Proceedings of the Second Regional Meeting on Nuclear Energy in Central Europe

    International Nuclear Information System (INIS)

    Second Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contains 75 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region

  19. Centrales hidroeléctricas del Zemm – Austria

    Directory of Open Access Journals (Sweden)

    Schmidt, W.

    1972-11-01

    Full Text Available In order to accommodate an increasing rate, doubled every ten years, of current consumption in this country, two hydroelectric power plants were constructed in the Zemm River. This type of power plant has the advantage of being able to produce energy at the time of consumption so as to be to handle peak energy production; while the normal power load requirement is covered by nuclear, petroleum and gas, and river power plants. These two plants have 517.500 kW, with a total annual yield of 648 GWh, or 778 GWh with pumping equipment. The gravity dam of the upper reservoir is 131 m high and 725 m long at the top. 960,000 m3 of concrete were used in its construction and it has an annual storage capacity of 127.4 millions m3. The earthen dam of the lower reservoir, which required 820,000 m3 to build, is about 28 m high and 480 m wide at the crown, with a capacity of 6,4 millions m3.Para poder hacer frente al aumento de consumo de corriente en el país, que se duplica cada 10 años, se construyeron dos centrales hidroeléctricas en el río Zemm. Este tipo de centrales tienen la ventaja de poder producir la energía en el mismo momento del consumo, por lo que se les confía la producción de energía de punta; mientras que la demanda de carga normal es cubierta por centrales de: energía nuclear; de petróleo y gas, y fluviales. Estas dos centrales tienen una potencia de 517.500 kW, con un rendimiento anual total de 648 GWh, ampliable en 130 GWh con el equipo de bombeo. La presa del embalse superior es de tipo gravedad, con 131 m de altura y una longitud de coronación de 725 m. Se emplearon 960.000 m3 de hormigón en su construcción. Tiene una capacidad de embalse anual de 127,4 millones de m3 En el embalse inferior, la presa es de tierra y se necesitaron 820.000 m3 para su construcción. Tiene una altura de unos 28 m, y una longitud de coronación de 480 m. Su capacidad es de 6,4 millones de m3.

  20. AP1000, a nuclear central of advanced design; AP1000, una central nuclear de diseno avanzado

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Viais J, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: nhm@nuclear.inin.mx

    2005-07-01

    The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

  1. Water temperature change caused by reservoirs; Alteracion que presenta la temperatura del agua por la existencia de embalses

    Energy Technology Data Exchange (ETDEWEB)

    Val, Rafael [Universidad Nacional Autonoma de Mexico (Mexico); Ninerola, Daniel; Pomares, Juan; Dolz, Jose [Universidad Politecnica de Cataluna (Spain); Armengol, Juan [Universidad de Barcelona (Spain)

    2006-01-15

    The water of a river exchanges heat with the atmosphere and with the riverbed; this process can reach its equilibrium along a stretch of river with similar geologic and climatic characteristics. This behavior can be modified by artificial effects; for example the use of the river water as a cooler in thermal power stations or in reservoir existent. The case of regions with Mediterranean climate, where the reservoirs here studied are found, the effects of changes in the natural thermal regime caused by dams and reservoirs are evaluated through: seasonal and daily thermal constancies, warmer winter water temperatures and reduced summer water temperature. Downstream from the power station or downstream the dam, the water temperature will evolve in such a way as to achieve the environmental equilibrium. The water temperature is a main factor in the ecology of the river; already it conditions in importance the life in fluvial reservoirs. [Spanish] El agua de un rio mantiene un intercambio de calor con la atmosfera y con el fondo. Este proceso puede alcanzar su equilibrio siempre y cuando las caracteristicas geologicas y climaticas a lo largo de un tramo del rio sean similares. Sin embargo, el comportamiento termico del rio puede ser alterado por los diversos usos del agua, como la refrigeracion de centrales termoelectricas, o por el almacenamiento del agua debido a la existencia de una presa. En el caso de las regiones con clima mediterraneo, donde se encuentran los embalses aqui estudiados, los efectos de las alteraciones en el regimen termico, resultado a su vez de dichos embalses, provocan una tendencia a la constancia termica estacional (elevacion de las temperaturas invernales y disminucion de las temperaturas estivales) y tambien un aumento de la uniformidad diaria. Aguas abajo de las termoelectricas o presas, la temperatura del agua evoluciona de tal forma que tiende a lograr el equilibrio con el medio ambiente.

  2. Annual progress report on nuclear data 1983 of the Central Bureau for Nuclear Measurements, Geel (Belgium)

    International Nuclear Information System (INIS)

    In this progress report of the Central Bureau for Nuclear Measurements at Geel (Belgium) researches related to neutron data and to non-neutron nuclear data are gathered. Neutron data are essentially related to cross-section measurements: for instance, concerning actinides, structural materials as Cr and Fe, fission products. Some studies are classified as concerning standard neutron data. Underlying physics is no forgotten neither than equipment (linear accelerator). Non-neutron nuclear data is concerned essentially with decay studies. Some compilations and evaluations are also given. Improvement of measurement and source preparation techniques is a part of this section

  3. Modelo de gestión de embalse multiescala con analisis de incertidumbre

    OpenAIRE

    Gómez Beas, Raquel

    2014-01-01

    En este trabajo se presenta el desarrollo de un modelo de gestión de agua en embalses que recoge el modelado semidistribuido de flujo de agua y sustancias en la cuenca vertiente, y su aplicación como herramienta de gestión de agua en embalses en clima mediterráneo. La naturaleza de las cuencas en este ambiente hace necesario compatibilizar la gestión del agua almacenada tras los excesos de lluvia y la atención de una amplia red de demandas, que llega a ser considerablemente ele...

  4. Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

    International Nuclear Information System (INIS)

    The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.)

  5. Nuclear legislation in Central and Eastern Europe and the NIS

    CERN Document Server

    2000-01-01

    This publication examines the legislation and regulations governing the peaceful uses of nuclear energy in eastern European countries. It covers 11 countries from Central and Eastern Europe and 11 countries from the New Independent States. The chapters follow a systematic format making it easier for the reader to carry out research and compare information. This study will be updated regularly. Albania Kazakhstan Armenia Latvia Belarus Lithuania Bosnia and Herzegovina Poland Bulgaria Republic of Moldova Croatia Romania Czech Republic Russian Federation Estonia Slovak Republic Former Yugoslav Re

  6. Operating experience management at Embalse N.P.P

    International Nuclear Information System (INIS)

    This report presents the operating experience management at Embalse N.P.P., Argentina. The internal operative experience in CNE is described. The analysis of internal events was regulated in 1983 when the first Significant Event Report Procedure was issued. In general it covered all the aspects of the event with the only exception of introducing the concept of root cause analysis, which occurred in later requirements. The internal operative experience in CNE is being performed successfully, in spite of the fact that there are efforts made to improve it, gathering most of the minor events and insisting in aspects such as Safety Culture, Quality Culture, Work Culture. Regarding the external operative experience in CNE, it has been acceptable until today, however some weak points, are: - There was not a specific group having the only responsibility of the study of such topic. The responsibility was shared by people who had other tasks or jobs to perform as well; - There were no ordered filed retrievable reports or evidences of the results of the analysis of the different events received in the power plant. However, the implemented corrective actions taken based on OPEX are indeed ordered and filed. With the new organization, integrative groups whose only function will be the operative experience it is believed that those weak points will be solved. The report is completed by the example of the event of a leak from a failed fuel detection system tubing. Description of the system is given as well as that of the event. The following steps are reported: 1. Affected tube repairing; 2. Quick inspection before the start-up; 3. The need of tubing inspection in planned outages; 4. Analysis of possible design changes

  7. Performance indicators at Embalse NPP: PSA and safety system indicators based on PSA models

    International Nuclear Information System (INIS)

    Several indicators have been implemented at Embalse NPP. The objective was selecting some representative parameters to evaluate the performance of both the plant and the personnel activities, important for safety. A first set of indicators was defined in accordance with plant technical staff criteria. A complementary set of them was addressed later based on WANO guidance. This report presents the set of indicators used at Embalse NPP, centering the description to related to safety systems performance indicators (SSPI). Some considerations are done about the calculation methods, the need for aligning and updating their values following Embalse Probabilistic Safety Assessment (PSA) development, and some pros and cons of using the PSA model for getting systems indicators. Owing to the fact that PSA ownership by utilities is also a subject of the meeting, some characteristics of the organization of the PSA Project are described at the beginning of the report. At Embalse NPP a Level 1 PSA has been developed under the responsibility of its own plant and with an important contribution from the IAEA. PSA was developed at the site, conducting this to a study strongly interactive with the station staff. (author)

  8. Appendix V: How to retain nuclear power plant staff when delays occur during construction (Argentina's experience with the Atucha and Embalse NPPs (Case study of human resource issues faced by NPP operating organizations, and how they were (or are being) addressed)

    International Nuclear Information System (INIS)

    It is common, especially, during the construction stage of the first NPP, to have some delays due to different causes (main components manufacturing, relevant field interferences, engineering modifications, etc). The first and second NPPs are typically contracted under the 'turnkey' modality. The training of the operating staff is also considered in the contract. Important milestones are established, including recruitment period, position profiles and minimal qualifications. The dates and duration of training overseas (main supplier's country) and inland are specified. The training duration and date of staff return to the site become relevant. If the owner and the main contractor do not adequately monitor the recruitment and training process, in case of construction delays, the site will start receiving a trained team too early that has no specific tasks assigned during the construction stage. Boredom may start in the members of this team. Depending upon the employment market or other industries' attraction, the integrity of a well-trained group may deteriorate. In case of resignations, it would be a tremendous effort for the owner to recruit, train and motivate a new staff. Sometimes, licensing on time may jeopardize the start-up milestone. This case study describes how retaining and motivation programmes were applied in order not to lose the previously trained personnel at the Atucha 1 and Embalse NPPs (Argentina)

  9. Piping information centralized management system for nuclear plant, PIMAS

    International Nuclear Information System (INIS)

    Piping works frequently cause many troubles in the progress of construction works, because piping is the final procedure in design and construction and is forced to suffer the problems in earlier stages. The enormous amount of data on quality control and management leads to the employment of many unskilled designers of low technical ability, and it causes confusion in installation and inspection works. In order to improve the situation, the ''piping information management system for nuclear plants (PIMAS)'' has been introduced attempting labor-saving and speed-up. Its main purposes are the mechanization of drafting works, the centralization of piping informations, labor-saving and speed-up in preparing production control data and material management. The features of the system are as follows: anyone can use the same informations whenever he requires them because the informations handled in design works are contained in a large computer; the system can be operated on-line, and the terminals are provided in the sections which require informations; and the sub-systems are completed for preparing a variety of drawings and data. Through the system, material control has become possible by using the material data in each plant, stock material data and the information on the revision of drawings in the design department. Efficiency improvement and information centralization in the manufacturing department have also been achieved because the computer has prepared many kinds of slips based on unified drawings and accurate informations. (Wakatsuki, Y.)

  10. Nuclear power in eastern and central Europe. Background paper

    International Nuclear Information System (INIS)

    The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab

  11. International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations

  12. El programa ERHIN y la gestión de embalses en áreas con alta precipitación nival = The ERHIN programme and reservoir management in areas of high nival precipitation

    OpenAIRE

    Arenillas Parra, Miguel; Cobos Campos, Guillermo; Mora Alonso-Muñoyerro, Justo

    2006-01-01

    El programa de Evaluación Recursos Hídricos procedentes de la Innivación (ERHIN) ha desarrollado un modelo hidrológico con subrutinas que contemplan el proceso de acumulación/fusión de nieve que permite el seguimiento del manto de nieve y su fusión , esencial para la previsión de avenidas en embalses cuyas cuencas vertientes recogen altos porcentajes de precipitación solida. En determinados sectores del territorio español (Pirineos, Cordilleras Cantábrica e Ibérica, Sistema Central y Sierra N...

  13. Quantification of individual of individual annual doses to the public due to Embalse NPP operation

    International Nuclear Information System (INIS)

    This paper compares the individual annual doses to the public produced during Embalse NPP operation and the natural radiation doses absorbed in everyday life by the same individuals. The basic idea is to show several examples that allow the comparison. Therefore, everybody will get a clear picture of the radiological contamination that surrounds us and the actual influence that Embalse NPP's operation has in the environment. The first concept to be considered is that the human body cells cannot distinguish whether radiation comes from a natural or an artificial source (a source created by man). This is of great importance in the case of the popular myth that says that radiation coming from artificial sources is the only damaging radiation, and that other types of radiation are innocuous, and represent no hazard to human health. We can preliminarily state that when considering the same dose, the effects of both kinds of radiation in human body are equal. (author)

  14. Proceedings of the International Conference Nuclear Energy in Central Europe 2001

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 98 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: reactor physics, thermal hydraulics, probabilistic safety assessment (PSA) and severe accidents, nuclear materials, NPP and research reactor operation, environmental issues and radiation measurement, fusion, radioactive waste and regulatory issues and public relations

  15. The effect of mixed-bed resin ingress into the Embalse PHTs

    International Nuclear Information System (INIS)

    Embalse NGS is provided four in-line autoclaves for a routine materials surveillance program. Through a cooperative program between the utility management and the Research and Development Branch of CNEA, the routine program was expanded to include Materials Tests according to the on-going R and D programs. The availability of the autoclave facilities and the joint Embalse/R and D program proved very valuable in occasion of the resin ingress into the PHTS due to the collapse of a Johnson strainer on April 9, 1988. The details of the incident have been communicated previously, and it is not the purpose of this presentation to describe the sequence of events on April 9, 1988, and following days. Rather, we present here the results of the materials surveillance program that was adopted to follow the materials behaviour and to check the possible negative impact of the resin ingress. The mixed bed resins were subjected to hydrothermal degradation under high radiation fields (the reactor went into hot shut-down state in two hours and was further cooled in a six hours' interval). Formation of ammonia, carbon dioxide, sulfate, nitrate and chloride are all possible. The long term surveillance program was carried out during the following 400 EFPD, on corrosion coupons provided by AECL and on additional samples prepared in CNEA on original materials from Embalse's PHTS. Comparisons were made of the behaviour of AECL materials ingressed in the Autoclave System in 1983, CNEA materials inserted in 1986, and additional CNEA coupons installed in 1988, after the incident

  16. Acumulación de metales pesados en microcrustáceos planctónicos provenientes de un embalse contaminado por relaves mineros, embalse Rapel (34° 10' S - 71° 29' W), Chile

    OpenAIRE

    Mercado Leal, S.I.

    2004-01-01

    El embalse Rapel, es un cuerpo de agua que está siendo sometido a un fuerte impacto antropogénico, por lo que evidencia severos signos de eutrofización. Esto último debido a que el embalse se ha transformado en el cuerpo receptor de una gran diversidad de efluentes (industriales, agrícolas y domésticos), que evacuan sus descargas sin ningún tipo de tratamiento. A lo cual se le debe agregar la recepción de aguas provenientes de los relaves de la mina de cobre “El Teniente”. Con el objetivo de ...

  17. Análisis del ciclo de carbono en embalses y su posible efecto en el cambio climático. Aplicación al embalse de Susqueda (río Ter, NE España)

    OpenAIRE

    Palau, Antoni; Alonso, Miguel; Corregidor, David

    2010-01-01

    Los embalses han sido considerados como sistemas emisores netos de carbono. Si bien es cierto que son sistemas forzados a descomponer toda la materia orgánica que queda cubierta por el agua tras la puesta en carga, esta fase inicial de maduración remite con los años hasta niveles de emisión de carbono similares a las de lagos de estado trófico equivalente. No todos los embalses tienen un comportamiento similar en el procesado de la materia orgánica carbonatada. El balance de ca...

  18. US central station nuclear electric generating units: significant milestones

    International Nuclear Information System (INIS)

    Listings of US nuclear power plants include significant dates, reactor type, owners, and net generating capacity. Listings are made by state, region, and utility. Tabulations of status, schedules, and orders are also presented

  19. Collective phenomena in non-central nuclear collisions

    Energy Technology Data Exchange (ETDEWEB)

    Voloshin, Sergei A.; Poskanzer, Arthur M.; Snellings, Raimond

    2008-10-20

    Recent developments in the field of anisotropic flow in nuclear collision are reviewed. The results from the top AGS energy to the top RHIC energy are discussed with emphasis on techniques, interpretation, and uncertainties in the measurements.

  20. Las comunidades de zooplancton de los embalses españoles

    OpenAIRE

    García Sánchez-Colomer, Manuel Ramón

    2001-01-01

    Los embalses son unos ecosistemas similares a los lagos aunque presentan algunas características que los hacen muy peculiares. Entre éstas destacan algunas tensiones a las que están sometidos por tratarse de medios semiartificiales, como son las corrientes de agua longitudinales y la eutrofización. El estudio de sus comunidades zooplanctónicas representa un campo de investigación ecológica con aplicaciones prácticas. El autor repasa algunas características de los principales constituyentes de...

  1. Nuclear magnetic resonance imaging of the central nervous system

    International Nuclear Information System (INIS)

    In this article a review is given of the use of magnetic resonance imaging for the central nervous system. An example of the screening of the population for multiple scelerosis is given. A good preliminary examination and the supply of relevant information to the person which performs the imaging is necessary. (R.B.). 9 figs.; 4 tabs

  2. The Staffing of Central Electricity Generating Board Nuclear Power Stations

    International Nuclear Information System (INIS)

    An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author)

  3. Harmonisation of Nuclear Emergency Preparedness in Central and Eastern Europe

    International Nuclear Information System (INIS)

    Under its Technical Co-operation programme the International Atomic Energy Agency has implementing a Regional Project RER/9/050:- Harmonisation of Regional Nuclear Emergency Preparedness for its Member States in the Europe region since 1997. The background of the project together with its achievements and future plans are presented in this paper. (author)

  4. Estimación de la evaporación en embalses de riego mediante un modelo de balance de energía

    OpenAIRE

    Molina Martínez, José Miguel; Martínez Álvarez, Victoriano; BAILLE, Alain; González-Real, Mª Milagros

    2006-01-01

    El artículo presenta un modelo de estimación de la evolución anual de la temperatura del agua y de la evaporación en embalses de regulación de riego. El modelo está basado en un balance de energía en la superficie del embalse, considerando la hipótesis de comportamiento isotermo. Precisa, como datos de entrada, la geometría del embalse (superficie y profundidad) y los datos climáticos diarios habitualmente disponibles en las estaciones meteorológicas (radiación global solar, velocidad del vie...

  5. Swedish support programme on nuclear non-proliferation in Central and Eastern Europe and Central Asia

    International Nuclear Information System (INIS)

    At the request of the Swedish Government, the Swedish Nuclear Power Inspectorate has established a support and co-operation programme in the area of nuclear non-proliferation with Russia and several of the republics of the former Soviet Union. The Programme was initiated in 1991 and an overall goal is to accomplish national means and measures for control and protection of nuclear material and facilities, in order to minimise the risk of proliferation of nuclear weapons and illicit trafficking of nuclear material and equipment. The objective of the Swedish Support Programme is to help each, so called, recipient State to be able to, independently and without help from outside, take the full responsibility for operating a national non-proliferation system and thereby fulfil the requirements imposed through the international legal instruments. This would include both the development and implementation of a modern nuclear legislation system, and the establishment of the components making up a national system for combating illicit trafficking. The support and co-operation projects are organised in five Project Groups (i.e. nuclear legislation, nuclear material control, physical protection, export/import control, and combating of illicit trafficking), which together cover the entire non-proliferation area. Up till June 2000, support and co-operation projects, completed and on-going, have been carried out in ten States, namely Armenia, Azerbaijan, Belarus, Georgia, Kazakstan, Latvia, Lithuania, Moldova, Russia and Ukraine. Furthermore, programmes have been initiated during the first part of 2000 with Estonia, Uzbekistan, Kyrgyzstan and Tajikistan. In addition, assistance has been given to Poland on a specific nuclear material accountancy topic. All projects are done on request by and in co-operation with these States. The total number of projects initiated during the period 1991 to June 2000 is 109, thereof 77 have been completed and 32 are currently on-going. It is the

  6. AP1000, a nuclear central of advanced design

    International Nuclear Information System (INIS)

    The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

  7. Nuclear power plant insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

    It was only after the decay of the Warsaw Pact, accompanied by emerging democratic structures and abolishment of the state monopolies, that an insurance market with private insurance companies had a chance to develop in these countries. West European insurance companies and their associations assisted and participated in this development by sending representatives and establishing branch offices. The paper reviews the current insurance regime for nuclear power plants of the Russian design types from the angle of international insurers as well as German insurance companies, referring to achievements so far and the foreseeable development. (orig./CB)

  8. Fuel operation of EDF nuclear fleet presentation of the centralized organization for operational engineering at the nuclear generation division

    International Nuclear Information System (INIS)

    The main feature of EDF Nuclear Fleet is the standardization, with 'series' of homogeneous plants (same equipment, fuel and operation technical documents). For fuel operation, this standardization is related to the concept of 'fuel management scheme' (typical fuel reloads with fixed number and enrichment of fresh assemblies) for a whole series of plants. The context of the Nuclear Fleet lead to the choice of a centralized organization for fuel engineering at the Nuclear Generation Division (DPN), located at UNIPE (National Department for Fleet Operation Engineering) in Lyon. The main features of this organization are the following: - Centralization of the engineering activities for fuel operation support in the Fuel Branch of UNIPE, - Strong real-time link with the nuclear sites, - Relations with various EDF Departments in charge of design, nuclear fuel supply and electricity production optimization. The purposes of the organization are: - Standardization of operational engineering services and products, - Autonomy with independent methods and computing tools, - Reactivity with a technical assistance for sites (24 hours 'hot line'), - Identification of different levels (on site and off site) to solve core operation problems, - Collection, analysis and valorization of operation feedback, - Contribution to fuel competence global management inside EDF. This paper briefly describes the organization. The main figures of annual engineering production are provided. A selection of examples illustrates the contribution to the Nuclear Fleet performance. (authors)

  9. The central dose register for the nuclear industry in Sweden

    International Nuclear Information System (INIS)

    A central dose register which is operated by decentral terminals has many great advantages. The register is as fast as possible updated. Data from the register can be obtained within seconds. Special hot jobs can be supervised easily and without time delay for dose information. It is very easy to handle a large number of personnel travelling around the country for maintenance. The computer in the system is a CDC Cyber 172 placed at Studsvik and the terminals are connected via telephone lines. Most dose information is automatically transferred to the dose register from automatic TLD readers of the Studsvik type. The dose register system also supervises the condition of the TLD readers and their calibration by the use of dosimeters which have been given a reference dose. The information from the system can be obtained on many different listings for year, quarter, month, department, personal history, job number, etc

  10. Colour of the nucleus as a marker of nuclear hardness, diameter and central thickness

    OpenAIRE

    Gullapalli Vamsi; Murthy Praveen; Murthy K

    1995-01-01

    Hundred and thirty patients, aged above 40 years, with senile cataract were examined. Age and colour were selected as the probable preoperative indicators of nuclear hardness. The lens material collected after manual extracapsular extraction was washed and the nucleus isolated. The diameter and central thickness of the nucleus were measured; the mean diameter and mean central thickness were 7.13 mm ± 0.76 and 3.05 mm ± 0.48, respectively. The hardness of the nucleus was measured...

  11. The Text of the Agreement Between the Agency and Argentina for the Application of Safeguards to the Embalse Power Reactor Facility

    International Nuclear Information System (INIS)

    The text of the Agreement between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Embalse Power Reactor Facility is reproduced in this document for the information of all Members

  12. Annual report 89. Central Bureau for nuclear measurements

    International Nuclear Information System (INIS)

    This report covers CBNM's activities during the second year of the multiannual programme 1988-91. Its contents and form reflect the change in the role and in the working conditions of the Joint Research Center of which CBNM is an institute. The main task of CBNM as covered by the European Communities Framework Programme is defined as the specific programme Nuclear Measurements and Reference Materials. The activities of the CBNM - like for the other institutes of the JRC - are only in part funded as Specific Programme. A small proportion of the specific programme budget is allotted to Exploratory Research, in preparation of possible extensions of existing competences or of potential new activities. Parts of the funding are coming from Support to Other Commission Services and from Work for Third Parties on the basis of contracts. 36 contributions have been presented during a series of international conferences; 24 articles have been submitted for publication in scientific/technical journals

  13. NATO nuclear reductions and the assurance of Central and Eastern European Allies

    OpenAIRE

    Guthe, Kurt

    2013-01-01

    Recent years have seen a debate within NATO over the issue of whether U.S. nonstrategic nuclear weapons in Europe should be retained in their current status, reduced in number, or withdrawn from the Continent. Some countries, including Germany, the Netherlands, and Belgium have advocated removal of the weapons. Others, notably member states in Central and Eastern Europe (CEE) are wary of changes in the nuclear posture of the alliance. The position of the United States and NATO as a whole i...

  14. Nuclear safety in the newly independent states in central and eastern Europe

    International Nuclear Information System (INIS)

    The Chernobyl nuclear reactor accident in 1986 has led to a reassessment of safety issues in the nuclear industry's of the Commonwealth of Independent States (CIS) and in central and eastern Europe. Three aspects of the problem are explained and addressed here, design inadequacies in the RBMK and other reactor types, less than adequate operational safety procedures and lack of independent government regulation of state utilities, allowing economic targets to overcome safe operation of plants. (UK)

  15. Overview of nuclear legislation in Central and Eastern Europe and the NIS

    International Nuclear Information System (INIS)

    This study provides an overview of current legislation governing the peaceful uses of nuclear energy in Central and Eastern European countries and the New Independent States. Revised to include information obtained since its original publication in October 1995, the current issue focuses on the institutional and legal frameworks which have been established in the countries under consideration. The competent nuclear authorities, the legislation in force, draft legislation and regulations, international conventions and membership in nuclear organisations of each country in the region are presented. (K.A.)

  16. Energy and Centrality Dependences of Charged Multiplicity Density in Relativistic Nuclear Collisions

    Institute of Scientific and Technical Information of China (English)

    SA; Ben-hao; Bonasera; A; TAI; An

    2002-01-01

    Using a hadron and string cascade model, JPCIAE, the energy and centrality dependences of chargedparticle pseudo rapidity density in relativistic nuclear collisions were studied. Within the framework ofthis model, both the relativistic p + p experimental data and the PHOBOS and PHENIX Au + Au data at

  17. Nuclear power in Central and Eastern Europe at the turn of Millennium

    International Nuclear Information System (INIS)

    In Central and Eastern European countries the use of nuclear energy for electricity generation begun in late 1950's and reached a stage of industrial maturity since 1970. In mid - 1998 there were 65 nuclear units connected to the grid, with the total installed capacity of 44.3 GWe and a nuclear electricity generation exceeding 249 TWh, supplying almost 22% of the total electricity produced in this region. Other 14 nuclear units with a total generating capacity of over 11.5 GWe were under construction in five countries: 4 in Ukraine and Russia, 3 in Slovakia, 2 in the Czech Republic and 1 in Romania. Although nuclear power has become an important energy source in many Central and Eastern European countries, especially in those countries with poor fossil energy resources (Lithuania - 82%, Bulgaria - 45.4%, Slovakia - 44%, Hungary - 40.8%), it still relies heavily on ex-Soviet and Russian - design technology (WWER and RBMK - type reactors). This implies large-scale implementation of upgrading and modernization programs for safe and reliable operation, in order to achieve levels of safety comparable with Western European standards, along with the eventual decommissioning of first generation nuclear units having serious functioning failures (e.g. Chernobyl 1, Ignalina 1 and 2, Kozloduy 1 and 2). In some countries, following the implementation of short and long term investment schemes for further improvement of the reliability and safety of operating NPP's performances, the capacity factor has reached the highest figures: Krsko NPP (Slovenia) - 88.3%, Paks NPP (Hungary) - 86.6% and Dukovany NPP (Czech Rep.) - 81%. In Romania the first CANDU - 6 unit in Europe, operable at Cernavoda since December 1996, had very satisfactory results, generating 9.7% of the country's electricity production, with a good overall load factor - 87.27%. The Chernobyl nuclear accident had immediate consequences upon the operation of NPPs and a number of restrictions were imposed. But, actually

  18. Ground acceleration in a nuclear power plant; Aceleracion del suelo en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pena G, P.; Balcazar, M.; Vega R, E., E-mail: pablo.pena@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

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

  19. Research study on operability in large-scale centralized control room. Regarding nuclear technology

    International Nuclear Information System (INIS)

    This study was performed to establish man-machine technology for panel-less instrumentation applicable to large-scale centralized control rooms of nuclear power plants. Work-load analysis of the operator in a large-scale centralized control room was performed and the basic constitution of an operator control station examined. Operability of panel-less instrumentation on based on a CRT touch-screen was examined with a mock-up operator control station manufactured according to the result of work-load analysis. The results of this study culminated in a design guideline for panel-less instrumentation. (author)

  20. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007

    International Nuclear Information System (INIS)

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  1. The AP1000 registered philosophy fits nuclear new build in Central Europe

    International Nuclear Information System (INIS)

    The World Nuclear Association estimates a steady growth in the number of reactors to be built in the next 20 years. The number of reactors in operation worldwide today is about 440 and will rise within the next couple of decades. It is speculated that Western Europe (including Germany) will have more reactors coming offline than online in the future due to limited lifetime versus plans for new build. In contrast, Eastern Europe (including Russia) is forecasting an increase in their nuclear generating capacity. This includes new market entrants such as Poland as well as expansion projects in the Czech Republic and Hungary; Germany's eastern neighbors. Unfortunately, as Germany and Switzerland phase out nuclear the net capacity in Western Europe is expected to drop even more. In addition to the phase out of nuclear, the federal German government decided to increase the power generation of renewables, focusing on wind and solar. The consequence of simultaneously implementing these new requirements is the creation of high frequency load changes from wind fluctuations or solar peaks without having the nuclear base load to maintain a constant capacity. These decisions on Germany's energy polices has extenuating circumstances which create challenges for local transmission system operators, as well as for neighboring countries' transmission system operators due to the synchronous grid of Continental Europe. This challenge will force the countries connected to Germany by the synchronous grid to place even more importance on their nuclear new build programs in the years to come. Though Germany is phasing out nuclear all together, its neighboring countries in Central and Eastern Europe are continuing with nuclear new build efforts. Therefore, it is still important for the German public to understand the options the nuclear industry have when selecting nuclear reactor vendors. The designs of today are more technically advanced, however the AP1000 registered plant stands out

  2. Central Asian Nuclear-Weapon-Free-Zone and the Collective Security Treaty

    International Nuclear Information System (INIS)

    In February 1997 Kazakhstan, Kyrgyzstan, Tajikistan, Turkmenistan, and Uzbekistan decided to establish Central Asian Nuclear-Weapon-Free-Zone (CANWFZ). As a matter of fact, negotiations on establishing that zone started in 1998 when Kyrgyzstan proposed draft basic element of a treaty on CANWFZ. After almost two years rather successful work on drafting the treaty, since April 2000 no meetings take place between diplomats of the five Central Asian states. It is recognized by many experts that it is the Tashkent 1992 Collective Security Treaty (CST) which caused a deadlock. Usually CST is interpreted as allowing the deployment of Russian nuclear weapons on the territory of the CST member states, for example, of Kazakhstan. However, more detailed analysis shows, that CST cannot a serious obstacle for creating CANWFZ

  3. IAEA activities to improve occupational radiation protection in nuclear power plants in Central and Eastern Europe

    International Nuclear Information System (INIS)

    The following aspects are highlighted: developing standards, ISOE (Information System on Occupational Exposure), providing assistance, and intercomparisons. By means of these coordinated efforts, the IAEA aims at improving occupational radiation protection in nuclear power plants in Central and Eastern Europe. The objective is not only transfer of knowledge and technology but also encouraging cooperation between health physicists in those countries as well as with health physicists in Western countries. (P.A.)

  4. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Yussup, F.; Ibrahim, M. M.; Haris, M. F.; Soh, S. C.; Hasim, H.; Azman, A.; Razalim, F. A. A.; Yapp, R.; Ramli, A. A. M.

    2016-01-01

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

  5. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering

  6. Regional Strategies Concerning Nuclear Fuel Cycle and HLRW in Central and Eastern European Countries

    International Nuclear Information System (INIS)

    In March 2009 a regional meeting on national strategies concerning nuclear fuel cycle and high level radioactive waste (HLRW) was held in Budapest with the participation of Central and Eastern European countries, Russia and France. Following the meeting a Task Force was set-up with fuel cycle experts from different countries in order to analyse the possible fuel cycle strategies in the region. The Task Force produced an Opinion Paper in spring 2010 on the Regional Strategies Concerning Nuclear Fuel Cycle and HLRW in Central and Eastern European Countries with several recommendations. The Opinion Paper emphasizes that the countries in the Central and Eastern European region are small, and they have modest NPP capacities compared to large nuclear countries. Spent fuel reprocessing facilities are not available in the region, but Russia and France offer such services for these countries. Deep geological repositories are not in operation in any of these countries, and in some of the countries the geological conditions do not allow to design such facilities. For these reasons the countries of the region may need special services and a regional approach could produce common benefit for waste management. (author)

  7. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    Energy Technology Data Exchange (ETDEWEB)

    Yussup, F., E-mail: nolida@nm.gov.my; Ibrahim, M. M., E-mail: maslina-i@nm.gov.my; Soh, S. C.; Hasim, H. [Instrumentation and Automation Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Haris, M. F. [Information Technology Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Azman, A. [Prototype and Development Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Razalim, F. A. A.; Yapp, R. [Health Physics Group, Radiation Safety and Health Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Ramli, A. A. M. [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia)

    2016-01-22

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

  8. Nuclear power plants making a comeback in Japan; El retorno de la centrales nucleares en Japon

    Energy Technology Data Exchange (ETDEWEB)

    Torralbo, J. R.

    2016-08-01

    We reproduce in this magazine the interesting article published by the president of the SNE in issue 46 of Cuadernos de Energia in October 2015, which describes the events that have taken place since the March 11, 2011 earthquake in Japan, the largest in its history, and the subsequent tsunami, which affected the Fukushima power plant, as well as the measures implemented since then and how some of this country nuclear power plants are being started up again. (Author)

  9. Annual progress report on nuclear data 1989. Central Bureau for nuclear measurements

    International Nuclear Information System (INIS)

    In 1989 the efforts for the improvement of the set of standard neutron cross sections and other quantities selected within the INDC/NEANDC Standards File continued. In particular a detailed study of the nuclear mass and charge distribution of the cold and near cold fission of 252Cf yielded understanding of cold mass rearrangements in nuclei. Accuracy of alpha-particle emission probabilities for major transitions in the decay of 236Pu, 239Pu and 243Am was improved to better than 0.5%. In the field of nuclear data for fission technology work was concentrated on European requests in the NEA High Priority Request List. The number of neutrons emitted per neutron absorbed, was obtained for 235U between 2 and 100 meV neutron energy. Using the weighting function determined at CBNM for neutron capture detectors, a new value was obtained for the neutron width of the 1.15 keV resonance in 56FeΓn = (62.9 ± 2.1) meV. In the field of nuclear data for fusion technology, measurements continued aiming at an improvement of relevant data for neutron transport calculations in the blanket and for prediction of gas production. The radionuclide metrology subproject follows three lines: determination of decay-scheme data, preparation of special standards and the improvement of measurement techniques including international comparisons

  10. Shipping of spent nuclear fuel to Central and Eastern Europe, and other nuclear waste deals

    International Nuclear Information System (INIS)

    In its reply to a written question in Parliament, the German federal government puts emphasis on the fact that all agreements concerning industrial or economic cooperation in the nuclear sector, concluded between the GDR and the Soviet Union, have been declared to be terminated in 1991. Hence the government declares that there are no international treaties any more that might serve as a vehicle for performing spent fuel shipments to Russia or any other state of the CIS. The German federal government further states to be prepared to contribute its share to the multinational assistance programme adopted in 1992 at the World Economic Summit Conference for the purpose of enhancing the safety of Soviet-design nuclear power plant. A number of projects, the government states, are in preparation with the competent institutions in the CIS, as e.g. projects for reactor safety analysis, improvement of reactor operating safety, safer nuclear fuel supply and waste management, and installation of a system for environmental radioactivity monitoring. (orig./HSCH)

  11. Creation of zone free nuclear weapon (ZFNW) in the Central Asia

    International Nuclear Information System (INIS)

    Issues on non-proliferation of mass demolition weapons are of special importance for people of Kazakhstan. The whole damage brought to nature and people's health by nuclear tests at the Semipalatinsk test site (STS) is not revealed yet. Kazakhstan contributed much to the matter of nuclear disarmament. More than six years ago for the first time in the world by RK President's resolution an operating nuclear test site closed. Kazakhstan was the first to fulfill obligations in accordance with Lisbon protocol. Kazakhstan liquidated the fourth nuclear potential in the world. It's time to undertake further steps in the field of non-proliferation. One of such steps is the creation of a ZFNW in the central Asia. The idea of ZFNW creation is being acknowledged more and more during last 30 years. All the four present zones include more than 100 countries. If the Antarctic Region is taken into account the zones cover more than 50% of dry land. Regional ZFNWs attract attention as a means of reflecting and rewarding general valuers in the sphere of nuclear disarmament and armament control. Such zones help tj narrow geographical sphere of military nuclear activity and to strengthen non-proliferation regime. The importance of ZFNW in the process of strengthening global and regional peace and safety is confirmed by the documents of Conference for countries joined the agreement on non-proliferation (AN) of 1995 and the first meeting of the Organizing Committee for Conference of 2000

  12. Security central processing unit applications in the protection of nuclear facilities

    International Nuclear Information System (INIS)

    New or upgraded electronic security systems protecting nuclear facilities or complexes will be heavily computer dependent. Proper planning for new systems and the employment of new state-of-the-art 32 bit processors in the processing of subsystem reports are key elements in effective security systems. The processing of subsystem reports represents only a small segment of system overhead. In selecting a security system to meet the current and future needs for nuclear security applications the central processing unit (CPU) applied in the system architecture is the critical element in system performance. New 32 bit technology eliminates the need for program overlays while providing system programmers with well documented program tools to develop effective systems to operate in all phases of nuclear security applications

  13. Knowledge management in nuclear power plants; Gestion del conocimiento en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cal, C. de la; Barasoain, F.; Buedo, J. L.

    2013-03-01

    This article aims to show the importance of knowledge management from different perspectives. In this first part part of the article, the overall approach that performs CNAT of knowledge management is described. In the second part, a specific aspect of knowledge management in ANAV, tacit knowledge transfer is showed. finally, the third part discusses the strategies and actions that are followed in CNCO for knowledge management. All this aims to show an overview of knowledge management held in the Spanish Nuclear Power Plants. (Author)

  14. Bivalves and their control at the process water system in Embalse N.P.P

    International Nuclear Information System (INIS)

    Embalse NPP is a 648 Mwe CANDU®-600 type pressurized heavy water reactor (PHWR). The primary heat transport system (PHTS) has two separated heat transport circuits, each of them with two steam generators (SGs) of the recirculating type. The SGs have Alloy 800 tubes and the PHTS piping is made of carbon steel (CS). The primary coolant is lithiated heavy water pHa25oC = 10.2-10.4, hydrogen content 3-10 cm3/kg D2O. The Secondary Circuit (SC) has mixed metallurgy, i.e., copper alloys in the condenser tubing, Carbon Steel piping and Stainless Steel Alloys in some specific locations of the Steam/Water Cycle. In the Secondary Circuit ethanolamine is dosed for pH control and hydrazine for oxygen remosion. The process water and circulation water circuit (main condenser cooling water) source is fresh water from the Embalse Lake. As in other countries, bivalve larvae were transported to La Plata River, Parana River and then to other rivers and lakes located in the interior of the country. This caused serious inconveniences and concern not only in water intakes for drinking water production, but also in electric power production and manufacturing industries. During the observations and inspections that were carried out in different components of the Plant (pipes, heat exchangers), mollusks were found inside the process water and circulation water circuit. This phenomenon reached a peak in 2004 and 2005. Although experience has been taken from other countries, the products to be dosed must be the specific ones to be used in local organisms, local flora and fauna and environmental regulations. In order to study and control this problem, a research study was performed by experts from Buenos Aires Universities and a work plan was established, which consists in three stages: to construct a biobox, that is set in the circuit containing precolonized plates so as to obtain information about the efficiency and the conditions of use of chlorine and an alternative non-oxidizing toxic

  15. Scope for nuclear weapon-free zone in central and eastern Europe

    International Nuclear Information System (INIS)

    The idea of a Central Europe free of nuclear weapons has its roots, of course, in the end of the cold war and the break-up of the former Union. These historical developments created the necessary conditions for the Lisbon Protocol, the successful withdrawal of all nuclear weapons from Belarus, Ukraine, and Kazakhstan as well as these countries' accession to the Non-Proliferation Treaty. It is admitted that even before these steps had been achieved, Belarus had put forward the nuclear-free zone initiative at the United Nations General Assembly in 1991. Like all the other nuclear weapon-free zones, existing or potential, a proposal for such a zone entails that it be analysed in the context of its political environment, regional specificity as well as the role, and implications of the relevant outside powers. These include Warsaw Pact dissolution and its impact on control of tactical nuclear weapons as well as the North Atlantic Treaty Organisation (NATO's) expansion eastwards. It is equally important to look at the issue in the context of its history, or, in other words, the past attempts

  16. Aislamiento de algas del embalse del Neusa por medio de cultivos In Vitro

    Directory of Open Access Journals (Sweden)

    Moreno E.

    2000-12-01

    Full Text Available

    EI cultivo de algas a nivel mundial es un oficio de vieja data, pero en Colombia se encuentra en sus primeras etapas de desarrollo. El presente trabajo desarrollado en el Laboratorio de Bioensayos, Departamento de Biología, Universidad Nacional de Colombia está encaminado a aportar técnicas en el desarrollo del cultivo de algas. En la parte practica del trabajo se utilizaron muestras de agua del embalse del Neusa las cuales se cultivaron en medios líquido y solido. Se observo un mejor crecimiento de cianofíceas filamentosas en medio solido y algas verdes en medio líquido. Las clamidomonas se ven favorecidas en ambos medios, hecho que permitió aislar una sepa pura de este tipo de algas. Las diatorneas por el hecho de crecer en relación con algas verdes generan un problema metodológico para su aislamiento, que aun se encuentra sin resolver.

  17. Effectiveness of a large mimic panel in an existing nuclear power plant central control board

    International Nuclear Information System (INIS)

    We conducted the analysis of the nuclear power plant (NPP) operators' behaviors under emergency conditions by using training simulators as a joint research project by Japanese BWR groups for twelve years. In the phase-IV of this project we executed two kinds of experiments to evaluate the effectiveness of the interfaces. One was for evaluations of the interfaces such as CRTs with touch screen, a large mimic panel, and a hierarchical annunciator system introduced in the newly developed ABWR type central control board. The other was that we analyzed the operators' behaviors in emergency conditions by using the first generation BWR type central control board which was added new interfaces such as a large display screen and demarcation on the board to help operators to understand the plant. The demarcation is one of the visual interface improvements and its technique is that a line enclosing several components causes them to be perceived as a group.The result showed that both the large display panel Introduced in ABWR central control board and the large display screen in the existing BWR type central control board improved the performance of the NPP operators in the experiments. It was expected that introduction of the large mimic panel into the existing BWR type central control boards would improve operators' performance. However, in the case of actual installation of the large display board into the existing central control boards, there are spatial and hardware constraints. Therefore the size of lamps, lines connecting from symbols of the pumps or valves to the others' will have to be modified under these constraints. It is important to evaluate the displayed information on the large display board before actual installation. We made experiments to solve these problems by using TEPCO's research simulator which is added a large mimic panel. (author)

  18. 35% of fracture in one of the Embalse nuclear power plant's entrance collectors

    International Nuclear Information System (INIS)

    The purpose of this work is to simulate an accident of a 35% of fracture at the reactor's entrance collector with the FIREBIRD III code, Mod. 1.0, in order to compare the results obtained with those stated in the Safety Report, and besides, to verify the capacity to foresee the steam generator's secondary boundary behaviour on the basis of the actually available models. For this type of fractures, it is expected that this does not basically affect the Heat Transport Primary Loop behaviour since the main heat drain is the fracture. (Author)

  19. Study of the heat transport primary system flow of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    In this work, the HTPS coolant channels flow and associate aleatory errors are estimated. The objective of this estimation is to verify the validity of the flow calculated using the Canadian thermalhydraulic design code 'NUCIRC'. From measurements it can also be observed the evolution of the calculated flow with power of the reactor and to correct the maximum flow with power. The percentage of standard deviation discrepancies of flow estimated by measurements and those calculated using NUCIRC code is 5,7%. As the average aleatory error in flow estimation is 8,0%, it is concluded that the flow distribution calculated using NUCIRC is representative of the current state of the reactor channels. (author)

  20. CNE (Embalse nuclear power plant): probabilistic safety study. Electric power supply. Events sequence

    International Nuclear Information System (INIS)

    The plant response to the occurrence of the starting event 'total loss of electric power supply to class IV and class III' is analyzed. This involves the study of automatical actions of safety and process systems as well as the operator actions. The probabilistic evaluation of starting event frequency is performed through fault-tree techniques. The frequency of occurrence 'loss of electric power supply to class IV (λIV = 0.56/year) and the probability of failure to demand of 'reserve' generating groups (Pd III 6.79 x 10-3) contribute to the mentioned frequency. As soon as the starting event occurs, the reactor power must be reduced to 0%, the fuel must be cooled through the thermo siphon and decay heat has to be removed. The events sequence analysis leads to the conclusion that the non shutting down of the reactor with any of the shutdown systems is 'incredible' (10-6/year). In all cases the fuel is cooled by building the thermo siphon except when a substantial inventory loss exist due to a closure failure of some valve of pressure and inventory control system. The order of magnitude of the failure of decay heat removal through the steam generators is 4 x 10-4. This removal would be assured by the emergency water system. Therefore, the frequency of the sequence of possible core meltdown, when the reactor does not shut down is: λ = 5 x 10-9/year and for the failure of heat removal: λ = 2 x 10-6/year. (Author)

  1. Outline and operation results of centralized radwaste treatment facility in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    In the Fukushima Nuclear Power Station I (Daiichi), Unit 1 started operation in 1971 and Unit 6 in 1979; the six power plants are now in steady operation. The Centralized Radwaste Treatment Facility, whose construction was started in 1980 and completed in 1984, is located south of Unit 4. Its total floor space is 36,000 m2, the main building being of the size of a 1,100 MW reactor building. The following equipments in Centralized Radwaste Treatment Facility are described, including features and operation results: radioactive liquid volume reduction treatment facility, laundary-center waste water concentration treatment facility, machinery drain water treatment facility, combustible solids incineration facility. (Mori, K.)

  2. Evaluation of cable ageing in Nuclear Power Plants; Evaluacion del envejecimiento de cables en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Vergara, T. [Empresarios Agrupados, A. I. E. Madrid (Spain); Alonso Chicote, J. [TECNATOM, S. A. (Spain); Burnay, S. [AEA Technology (UK)

    2000-07-01

    The majority of power, control and instrumentation cables in nuclear power plants use polymers as their basic material for insulation and jacket. In many cases, these cables form part of safety-related circuits and should therefore be capable of operating correctly under both normal and accident conditions. Since polymeric materials are degraded by the long term action of the radiation and thermal environments found in the plant, it is important to be able to establish the cable condition during the plant lifetime. Nowadays there are a number of different methods to evaluate the remaining lifetime of cables. In the case of new plants, or new cables in old plants, accelerated ageing tests and predictive models can be used to establish the behaviour of the cable materials under operating conditions. There are verified techniques and considerable experience in the definition of predictive models. This type of approach is best carried out during the commissioning stage or in the early stages of operation. In older plants, particularly where there is a wide range of cable types in use, it is more appropriate to use condition monitoring methods to establish the state of degradation of cables in-plant. Over the last 10 years there have been considerable developments in methods for condition monitoring of cables and a tool-box of practical techniques are now available. There is no single technique which is suitable for all cable materials but the range of methods covers nearly all of the types currently in use, at present, the most established methods are the indented, thermal analysis (OIT, OITP and TGA) and dielectric loss measurements, All of these are either non-destructive methods or require only micro-samples of material. (Author) 15 refs.

  3. Five years of partnership between nuclear power stations in Germany and the CIS and Central European states

    International Nuclear Information System (INIS)

    For five years, partnerships have existed between German nuclear power stations and nuclear power stations in the CIS and central European states with the object of increasing the nuclear safety and reliability of nuclear power stations through the interchange of experience by experts at all operational organisational levels. In this period, about 200 reciprocal meetings, exchanges of groups of experts, secondments into the partners' plants and seminars, of which about two-thirds have been in German nuclear power stations, have taken place. Improvements and a change in safety-responsibility awareness are clearly established. In this area, the partnerships have made an important contribution. (orig.)

  4. A position paper for a central procurement organization for the nuclear power industry

    International Nuclear Information System (INIS)

    This paper integrates the results of numerous nuclear utility industry meetings with commercial business practices. The Central Procurement Organization (CPO) is designed to achieve an immediate 30%--50% reduction in total procurement, engineering qualification, warehousing, and distribution cost. Three (3) areas define a CPO success criteria: (1) Lean, credible, and cost-effective issues discussed include facility cost, operational cost, staff expertise, product priorities, warehousing, and distribution, (2) Common technical, commercial, and quality requirement issues discussed include current industry practices and proposed future methodologies, and (3) Financial survivability issues which are the most critical since the CPO must exist during changing internal and external utility environments

  5. Permission of change of limits in the vapor generators of the Atucha I Nuclear Central

    International Nuclear Information System (INIS)

    In the mark of the modification of the Atucha-I Nuclear Central Installation (CNA-I) as consequence of the Introduction of the System 'Second Drain of Heat' (SSC), the Entity Responsible for the CNA-I (NASA) requested authorization to the Nuclear Regulatory Authority (ARN) to modify the value of the minimum level of water in the secondary side in the Steam generators (GVs) to activate the signal 'shoot of the Cut of the Reactor' (RESA-LLV). As the level in the GVs is one of those parameters that are used to shoot the Emergency Feeding System (RX), component of the SSC System, also was analyzed the change in the activation of the shoot signal of the 'Second Drain of Heat' (2SSC-LLV). The ARN uses for the study of the nuclear safety of nuclear power plants, the series of prediction programs RELAP5/MOD3.X. It participates of the evaluation and maintenance activities of these codes through specific agreements with the U.S. Nuclear Regulatory Commission (US-NRC). It is necessary to account with programs of this type since the ARN it licenses the construction and operation of Nuclear Power Plants (NPPs) and other outstanding facilities and it inquires its operation according to its own standards. With these tools its are auditing the calculations that the Responsible Entities of the operation make to guarantee the operability of the NPPs assisting the mentioned standards. The analysis with computational codes is used as a tool to achieve the best understanding in the behavior of the plant in union with the engineering approach, the manual calculations, the data analysis and the experience in the operation of the machine. (Author)

  6. Center for Nuclear Safety in Central and Eastern Europe: a platform for co-operation

    International Nuclear Information System (INIS)

    The paper presents a summary of the current status and the activities of the Centre of Nuclear Safety in Central and Eastern Europe (CENS). The CENS is a non-profit and independent association supported by the Swiss and Slovak Governments. The main mission of the CENS is to provide an independent platform for technical co-operation between the regulatory authorities of the Western and Eastern countries. The key partners of the CENS are the Swiss Federal Nuclear Safety Inspectorate (HSK), the International Atomic Energy Agency (IAEA), the US Department of Energy (US DOE), the Nuclear Regulatory Authority of the Slovak Republic (UJD), the Gesellschaft fuer Anlagen-und Reaktorsicherheit mbH (GRS), Germany and the Institute of Radiation Protection and Nuclear Safety (IRSN), France. The CENS programs for 2003-2004 are presented. It can be considered as a complement to the IAEA activities in the area of short-term and event urgent planning. CENS projects as an example are presented. CENS proposals for co-operation with the Bulgarian institutions are made in connection with the topics of the forum round table discussions

  7. International collaboration to study the feasibility of implementing the use of slightly enriched uranium fuel in the Embalse CANDU reactor

    International Nuclear Information System (INIS)

    In the last few years, Nucleoelectrica Argentina S.A. and Atomic Energy of Canada Limited have collaborated on a study of the technical feasibility of implementing Slightly Enriched Uranium (SEU) fuel in the Embalse CANDU reactor in Argentina. The successful conversion to SEU fuel of the other Argentine heavy-water reactor, Atucha 1, served as a good example. SEU presents an attractive incentive from the point of view of fuel utilization: if fuel enriched to 0.9% 235U were used in Embalse instead of natural uranium, the average fuel discharge burnup would increase significantly (by a factor of about 2), with consequent reduction in fuel requirements, leading to lower fuel-cycle costs and a large reduction in spent-fuel volume per unit energy produced. Another advantage is the change in the axial power shape: with SEU fuel, the maximum bundle power in a channel decreases and shifts towards the coolant inlet end, consequently increasing the thermalhydraulics safety margin. Two SEU fuel carriers, the traditional 37-element bundle and the 43-element CANFLEX bundle, which has enhanced thermalhydraulic characteristics as well as lower peak linear element ratings, have been examined. The feasibility study gave the organizations an excellent opportunity to perform cooperatively a large number of analyses, e.g., in reactor physics, thermalhydraulics, fuel performance, and safety. A Draft Plan for a Demonstration Irradiation of SEU fuel in Embalse was prepared. Safety analyses have been performed for a number of hypothetical accidents, such as Large Loss of Coolant, Loss of Reactivity Control, and an off-normal condition corresponding to introducing 8 SEU bundles in a channel (instead of 2 or 4 bundles). There are concrete safety improvements which result from the reduced maximum bundle powers and their shift towards the inlet end of the fuel channel. Further improvements in safety margins would accrue with CANFLEX. In conclusion, the analyses identified no issues that would

  8. Comparative Analysis of Thermohydraulic Margins in Embalse Power Station, CARA Vs. CANDU with Cobra IV-HW

    International Nuclear Information System (INIS)

    Comparative analysis of thermohydraulic margins were studied of the CANDU 37 and CARA fuel bundles (FB) in Embalse power station with COBRA IV-HW code ., the geometry of the bundle laying on the channel was particularly modeled and discussing the results in comparison with former calculations with 1/6 simetry .The CARA design with enriched uranium (0.9 %) and extended burn up lets maintain the current thermohydraulic nominal margins , while compared with CANDU 37 rods FB enriched , the CARA design permits widely improve the current margins

  9. Colour of the nucleus as a marker of nuclear hardness, diameter and central thickness.

    Science.gov (United States)

    Gullapalli, V K; Murthy, P R; Murthy, K R

    1995-12-01

    Hundred and thirty patients, aged above 40 years, with senile cataract were examined. Age and colour were selected as the probable preoperative indicators of nuclear hardness. The lens material collected after manual extracapsular extraction was washed and the nucleus isolated. The diameter and central thickness of the nucleus were measured; the mean diameter and mean central thickness were 7.13 mm +/- 0.76 and 3.05 mm +/- 0.48, respectively. The hardness of the nucleus was measured with a lens guillotine designed by us. Regression analysis was applied to the parameters measured and these were compared with the colour and age. The parameters measured had the following relationship: Colour vs hardness (r value = 0.7569) (p 0.05) Age vs diameter (r value = 0.0987) (p > 0.05) Age vs central thickness (r value = 0.1700) (p > 0.05) The values showed that colour had a statistically significant relationship with all the 3 parameters (p cataractous lens nucleus, the preoperative knowledge of which would help the surgeon in planning small-incision surgery including phacoemulsification. PMID:8655196

  10. Colour of the nucleus as a marker of nuclear hardness, diameter and central thickness

    Directory of Open Access Journals (Sweden)

    Gullapalli Vamsi

    1995-01-01

    Full Text Available Hundred and thirty patients, aged above 40 years, with senile cataract were examined. Age and colour were selected as the probable preoperative indicators of nuclear hardness. The lens material collected after manual extracapsular extraction was washed and the nucleus isolated. The diameter and central thickness of the nucleus were measured; the mean diameter and mean central thickness were 7.13 mm ± 0.76 and 3.05 mm ± 0.48, respectively. The hardness of the nucleus was measured with a lens guillotine designed by us. Regression analysis was applied to the parameters measured and these were compared with the colour and age. The parameters measured had the following relationship: Colour vs hardness (r value = 0.7569 (p < 0.001 Colour vs diameter (r value = 0.3962 (p < 0.001 Colour vs central thickness (r value = 0.4785 (p < 0.001 Age vs hardness (r value = -0.0499 (p > 0.05 Age vs diameter (r value = 0.0987 (p > 0.05 Age vs central thickness (r value = 0.1700 (p > 0.05 The values showed that colour had a statistically significant relationship with all the 3 parameters (p < 0.001, while age had no significant relationship with the same parameters. The results indicated that colour can be used more reliably to predict physical characteristics of the cataractous lens nucleus, the preoperative knowledge of which would help the surgeon in planning small-incision surgery including phacoemulsification.

  11. Experience from the operation of the Swedish Central Interim Storage Facility for Spent Nuclear Fuel, CLAB

    International Nuclear Information System (INIS)

    Currently, about 50% of the electric power in Sweden is generated by means of nuclear power. The Swedish nuclear programme comprises 12 plants. According to political decisions, no more nuclear power plants will be built and the existing plants will not be operated beyond the year 2010. The programme will give rise to not more than 7800 t U of spent fuel, which will be directly disposed of in the crystalline bedrock without reprocessing. A keystone in the spent fuel management strategy is the Central Interim Storage Facility for Spent Nuclear Fuel, CLAB. After intensive pre-project work, the licensing of CLAB according to the Building, Environment Protection and Atomic Energy Acts took place in 1978-1979. After a total licensing time of about 20 months, the last permit was obtained in August 1979. By August 1994, CLAB had received and unloaded some 720 fuel transport casks, corresponding to about 2000 t U, and 60 casks containing highly active core components. The performance of the plant has been very satisfactory and with increasing experience it has been possible to reduce the operating and maintenance costs. The extensive efforts during the design phase have resulted in a collective dose of 25-30% of the dose calculated in the final safety report. Owing to a low activity release from the fuel and optimized management of the used water filtering agents, the number of waste packages emanating from CLAB has been less than 10% of what was originally expected. The activity release to air and water from the facility during the first five years of operation has been around 0.01% of the permissible release. In order to postpone the building of additional storage pools, new storage canisters have been developed which has increased the storage capacity from 3000 to 5000 t U. (author). 1 fig

  12. Treatment of operational experience of nuclear power plants in WANO; Tratamiento de la experiencia operativa de las centrales nucleares en WANO

    Energy Technology Data Exchange (ETDEWEB)

    Ibanez, M.

    2013-09-01

    The article describes the activities associated to the Operating Experience Programme of the World Association of Nuclear Operators. The programme manages the event reports submitted by the nuclear power plants to the WANO database for the preparation by the Operating Experience Central Team of some documents like the significant Operating Experience Reports and Significant Event Reports that help the stations to avoid similar events. (Author)

  13. Energy and centrality dependences of charged multiplicity pseudorapidity density in relativistic nuclear collisions

    CERN Document Server

    Zhou Dai Mei; Sá Ben-Hao; Li Zhong Dao

    2002-01-01

    Using a hadron and string cascade model, JPCIAE, and the corresponding Monte Carlo events generator, the energy and centrality dependences of charged particle pseudorapidity density in relativistic nuclear collisions were studied. Within the framework of this model, both the relativistic p anti p experimental data and the PHOBOS and PHENIX Au + Au data could be reproduced fairly well without retuning the model parameters. The author shows that since is not a well defined physical variable both experimentally and theoretically, the charged particle pseudorapidity density per participant pair can increase and also can decrease with increasing of , so it may be hard to use charged particle pseudorapidity density per participant pair as a function of to distinguish various theoretical models for particle production

  14. Energy and centrality dependences of charged multiplicity pseudorapidity density in relativistic nuclear collisions

    International Nuclear Information System (INIS)

    Using a hadron and string cascade model, JPCIAE, and the corresponding Monte Carlo events generator, the energy and centrality dependences of charged particle pseudorapidity density in relativistic nuclear collisions were studied. Within the framework of this model, both the relativistic p anti p experimental data and the PHOBOS and PHENIX Au + Au data could be reproduced fairly well without retuning the model parameters. The author shows that since part> is not a well defined physical variable both experimentally and theoretically, the charged particle pseudorapidity density per participant pair can increase and also can decrease with increasing of part>, so it may be hard to use charged particle pseudorapidity density per participant pair as a function of part> to distinguish various theoretical models for particle production

  15. Nuclear policies in Central Europe. Environmental policy and enlargement of the European Union: Austria's policies towards Nuclear Reactors in neighboring countries

    International Nuclear Information System (INIS)

    Austria's anti-nuclear policies are rooted in the successful anti-nuclear referendum on the Zwentendorf nuclear power plant (Lower Austria) in 1978 and the great impact of the Chernobyl catastrophe on Austria in 1986. Since about 1990, official Austria has pursued anti-nuclear policies not only at home but also abroad. In particular, reactors in Central and Eastern European Countries (CEEC) are the focal points of Austria's foreign anti-nuclear policies. Strategies include increasing nuclear safety, promoting energy efficiency and sustainable energy sources (such as renewable resources), and extending international legal frameworks to account for nuclear safety. Involvement in domestic energy issues in other countries is not an easy task, and while Austrian policy makers have had some success in increasing awareness of nuclear safety in Europe, they have also made a number of strategic mistakes. Notwithstanding real and substantiated concerns regarding nuclear safety, Austrian policies have lost credibility during recent years. This book explores the history and the development of Austrian anti-nuclear policies, and discusses the political economy of such policies. Particular emphasis is laid on the 2002 referendum against the Temelin reactor in the neighboring Czech Republic. (orig.)

  16. Análisis geomorfológico para la determinación de la susceptibilidad en las laderas de los embalses. Aplicación a los embalses de Dañador, Guadalmena y Tranco de Beas (cuenca del Guadalquivir, España).

    OpenAIRE

    Fernández García, Paloma; García de Domingo, Alfredo; Alameda Revaldería, Jose

    2008-01-01

    El conocimiento de los factores condicionantes en la estabilidad de las laderas de los embalses, requiere un detallado estudio de los principales procesos dinámicos actuantes en el entorno del vaso. En este sentido, la cartografía geomorfológica ofrece excelentes resultados en la identificación de inestabilidades naturales y de su grado de susceptibilidad. Este trabajo estudia las características geológicas y geomorfológicas de la zona más próxima a los embalses de Dañador, Guadalmen...

  17. Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

    International Nuclear Information System (INIS)

    The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.

  18. Rapid Prototyping of the Central Safety System for Nuclear Risk in ITER

    International Nuclear Information System (INIS)

    Full text of publication follows: In the current ITER Baseline design, the Central Safety System for Nuclear Risk (CSS-N) is the safety control system in charge to assure nuclear safety for the plant, personnel and environment. In particular it is envisaged that the CSS shall interface to the plant safety systems for nuclear risk and shall coordinate the individual protection provided by the intervention of these systems by the activation, where required, of additional protections. The design of such a system, together with its implementation, strongly depends on the requirements, particularly in terms of reliability. The CSS-N is a safety critical system, thus its validation and commissioning play a very important role, since the required level of reliability must be demonstrated. In such a scenario, where a new and non-conventional system has to be deployed, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the system requirements, and they will be used to test and validate the control logic. Furthermore these tools can be used to rapid design the safety system and to carry out hardware-in-the-loop (HIL) simulations, which permit to assess the performance of the control hardware against a plant simulator. Both a control system prototype and a safety system oriented plant simulator have been developed to assess first the requirements and then the performance of the CSS-N. In particular the presented SW/HW framework permits to design and verify the CSS protection logics and to test and validate these logics by means of HIL simulations. This work introduces both the prototype and plant simulator architectures, together with the methodology adopted to design and implement these validation tools. (authors)

  19. Puente sobre el embalse de Barrios de Luna /León/España

    Directory of Open Access Journals (Sweden)

    López Sáiz, José Manuel

    1984-05-01

    Full Text Available The bridge Carlos Fernández Casado covers the principal arm of the reservoir of Barrios de Luna, at the height of the former bridge of San Pedro de Luna, today covered by high waters. It is a suspension bridge with 440 m of space between its towers, with lateral bays each of 65 m. In carrying out the work the following phases were contemplated: — Counterweights. — Towers. — Braces. — Lintel. — Suspension. — Construction of the board. — Auscultation and control. The bridge is articulated in the center and with free longitudinal movement in order to permit the movements produced by retraction, flow and dilatation. This situation demands the carrying out, in the center of the bay, of a cap which permits vertical gyrations and horizontal displacements along the axle of the bridge and which prevents the rest of the movements. Both the project and the construction have been directed not only toward a viable construction from the point of view of resistance but also to obtain a balanced and esthetic work for the users of the highway.El puente Carlos Fernández Casado salva el brazo principal del embalse de Barrios de Luna, a la altura del antiguo pueblo de San Pedro de Luna, hoy inundado en aguas altas. Se trata de un puente atirantado de 440 m de luz entre sus torres, con vanos laterales de 65 m cada uno. En su ejecución se han contemplado las siguientes fases: — Contrapesos. — Torres. — Riostras. — Dintel. — Tirantes. — Construcción del tablero. — Auscultación y control. El puente está articulado en el centro y con libre movimiento longitudinal para permitir los movimientos producidos por retracción, fluencia y dilatación. Esta situación exige la ejecución, en el centro del vano, de una rótula que permita giros verticales y desplazamientos horizontales a lo largo del eje del puente y que impida el resto de los movimientos. Tanto el proyecto como la construcción se han

  20. Análisis ecológico de la cuenca de captación y del embalse de Tominé

    Directory of Open Access Journals (Sweden)

    Guillot Monroy Gabriel Hernando

    2000-06-01

    Full Text Available La cuenca del embalse de Tominé se encuentra en la parte alta de la cordillera oriental, en ungradiente altitudinal que va desde los 2.580 msnm en el espejo de agua, hasta los 3.600 msnm.Esta localización determina la presencia de un gradiente climático y la localización de diversosecosistemas, tales como páramo y bosque alto andino. Los procesos de colonización y deasentamiento humano en la cuenca, en asocio con las actividades de desarrollo, han llevado a modificaciones del régimen de circulación y de la calidad del agua. La construcción de poblaciones como Guatavita y el incremento de las actividades agrícolas y ganaderas, ha inducido cambios en la cobertura vegetal y con ello en los procesos naturales del ciclo hidrológico en la cuenca. A esto se suma el manejo que se ha hecho del recurso agua y la utilización de los drenajes como vertedero de aguas residuales domésticas e industriales (cultivos de flores. En la actualidad ya se observan procesos acentuados de erosión originados inicialmente por la pérdida de cobertura vegetal y acelerados por la praderización y explotación ganadera. Al reconocer que la problemática ambiental de una cuenca de captación se ve reflejada en las
    características físico-químicas y biológicas de los ecosistemas acuáticos de la misma, es claro que el análisis de dicha problemática debe ser abordada desde un punto de vista ecosistémico, tomando como unidad mínima la cuenca de captación y no sólo el cuerpo de agua. Se aborda la problemática del deterioro del embalse desde el punto de vista del análisis ecológico de la cuenca de captación y del mismo embalse, involucrando los componentes físico, biótico y socioambiental. Después de utilizar 16 criterios diferentes tanto físicos, químicos como biológicos de clasificación trófica, se observa que son muy pocos los índices que clasifican al embalse de Tominé en un nivel EUTRÓFICO, y que en el caso en que se presente,

  1. Nuclear power production costs

    International Nuclear Information System (INIS)

    The economic competitiveness of nuclear power in different highly developed countries is shown, by reviewing various international studies made on the subject. Generation costs (historical values) of Atucha I and Embalse Nuclear Power Plants, which are of the type used in those countries, are also included. The results of an international study on the economic aspects of the back end of the nuclear fuel cycle are also reviewed. This study shows its relatively low incidence in the generation costs. The conclusion is that if in Argentina the same principles of economic racionality were followed, nuclear energy would be economically competitive in the future, as it is today. This is of great importance in view of its almost unavoidable character of alternative source of energy, and specially since we have to expect an important growth in the consumption of electricity, due to its low share in the total consumption of energy, and the low energy consumption per capita in Argentina. (Author)

  2. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    International Nuclear Information System (INIS)

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia

  3. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Si Pyo; Kim, Cheol Jung; Yoo, Bung Duk; Kim, Jae Woo; Lee, Myung Ho; Kim, Kyung Pyo

    2006-02-15

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia.

  4. Condicionantes en la explotación ordinaria de los embalses gestionados por la agencia catalana del agua

    OpenAIRE

    Diéguez, José Miguel

    2009-01-01

    La gestión de los recursos hídricos de las cuencas internas de Cataluña se caracteriza por un precario equilibrio entre éstos y las demandas a satisfacer. La capacidad de regulación hiperanual de los embalses es prácticamente inexistente y motiva que entre los episodios de sequía, frecuentes y característicos en el clima mediterráneo, se deban adoptar criterios de gestión que garanticen la gestión de los usos considerados prioritarios y la utilización más eficiente de las reservas. Por ot...

  5. International Conference Nuclear Energy in Central Europe 99, V. 2. Proceedings. Embedded Meeting Neutron Imaging Methods to Detect Defects in Materials

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The second book of proceedings contain 14 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics cover Neutron Imaging Methods

  6. Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995

    International Nuclear Information System (INIS)

    The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author)

  7. Role of nuclear factor kappa B in central nervous system regeneration

    Institute of Scientific and Technical Information of China (English)

    Christian Engelmann; Falk Weih; Ronny Haenold

    2014-01-01

    Activation of nuclear factor kappa B (NF-κB) is a hallmark of various central nervous system (CNS) pathologies. Neuron-speciifc inhibition of its transcriptional activator subunit RelA, also referred to as p65, promotes neuronal survival under a range of conditions, i.e., for ischemic or excitotoxic insults. In macro-and microglial cells, post-lesional activation of NF-κB triggers a growth-permissive program which contributes to neural tissue inlfammation, scar formation, and the expression of axonal growth inhibitors. Intriguingly, inhibition of such inducible NF-κB in the neuro-glial compartment, i.e., by genetic ablation of RelA or overexpression of a trans-dominant negative mutant of its upstream regulator IκBα, significantly enhances functional recovery and promotes axonal regeneration in the mature CNS. By contrast, depletion of the NF-κB subunit p50, which lacks transcriptional activator function and acts as a transcriptional repressor on its own, causes precocious neuronal loss and exacerbates axonal degeneration in the lesioned brain. Collectively, the data imply that NF-κB orchestrates a multicellular pro-gram in whichκB-dependent gene expression establishes a growth-repulsive terrain within the post-lesioned brain that limits structural regeneration of neuronal circuits. Considering these subunit-speciifc functions, interference with the NF-κB pathway might hold clinical potentials to improve functional restoration following traumatic CNS injury.

  8. Masses and Scaling Relations for Nuclear Star Clusters, and their Coexistence with Central Black Holes

    CERN Document Server

    Georgiev, Iskren Y; Leigh, Natan; Lützgendorf, Nora; Neumayer, Nadine

    2016-01-01

    Galactic nuclei typically host either a Nuclear Star Cluster (NSC, prevalent in galaxies with masses $\\lesssim 10^{10}M_\\odot$) or a Massive Black Hole (MBH, common in galaxies with masses $\\gtrsim 10^{12}M_\\odot$). In the intermediate mass range, some nuclei host both a NSC and a MBH. In this paper, we explore scaling relations between NSC mass (${\\cal M}_{\\rm NSC}$) and host galaxy total stellar mass (${\\cal M}_{\\star,\\rm gal}$) using a large sample of NSCs in late- and early-type galaxies, including a number of NSCs harboring a MBH. Such scaling relations reflect the underlying physical mechanisms driving the formation and (co)evolution of these central massive objects. We find $\\sim\\!1.5\\sigma$ significant differences between NSCs in late- and early-type galaxies in the slopes and offsets of the relations $r_{\\rm eff,NSC}$--${\\cal M}_{\\rm NSC}$, $r_{\\rm eff, NSC}$--${\\cal M}_{\\star,\\rm gal}$ and ${\\cal M}_{\\rm NSC}$--${\\cal M}_{\\star,\\rm gal}$, in the sense that $i)$ NSCs in late-types are more compact at...

  9. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007; Padrao da mortalidade da populacao circunvizinha a Central Nuclear Almirante Alvaro Alberto / 1986 a 2007

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Angra dos Reis, RJ (Brazil). Centro de Informacoes sobre Radioepidemiologia; Xavier, Diego Ricardo [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil). lnst. de Comunicacao e Informacao Cientifica e Tecnologica; Silva, Roseli Monteiro da [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil)

    2011-05-15

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  10. The stress tests performed by the Spanish nuclear power plants.; Las pruebas de resistencia realizadas a las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, J. R.

    2011-07-01

    In the wake of the accident that occurred at Fukushima nuclear power plant in Japan, the European Union decided to subject the European plants to a reassessment of their safety margins, in accordance with the lessons learned from that accident. On December 31st last, following a process of exhaustive analysis, the Nuclear Safety Council submitted the final reports corresponding to the evaluations performed by the Spanish nuclear power plants, with the results obtained and conclusions drawn. Also detailed are the actions proposed to improve the nuclear safety of these facilities in response to extreme situations. (Author)

  11. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

  12. Las abejas de Porce familia colletidae (hymenoptera: apoidea notas y claves para los géneros presentes en la zona de influencia del embalse Porce ii.

    Directory of Open Access Journals (Sweden)

    Smith Pardo Allan H.

    1999-12-01

    Full Text Available Se presentan claves taxonómicas a nivel de género para la identificación de las abejas colletidas de la zona de Influencia del Embalse Porce II (Porce, Antioquía, Colombia S.A. Adicionalmente se presentan algunas notas para los géneros de colletidos capturados durante el inventario de las abejas silvestres de la zona.

  13. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

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

  14. Búsqueda y análisis de nuevos métodos de seguimiento del funcionamiento de centrales nucleares PWR

    OpenAIRE

    Roca-Cusachs Maennicke, Beatriz

    2006-01-01

    El siguiente proyecto ha sido realizado en el departamento STEP (Simulation and information technologies for power generation systems) de la división R&D (investigación y desarrollo) en la empresa EDF (Electricité de France). Este proyecto estudia nuevas metodologías de seguimiento del funcionamiento de una central nuclear mediante el programa CEF (Contrôle Economique du Fonctionnement), utilizado por las centrales para controlar el funcionamiento termodinámico del circuito secundario. El obj...

  15. EFECTO ESTACIONAL DE LOS AFLUENTES EN LA ESTRUCTURA TÉRMICA DE UN PEQUEÑO EMBALSE NEOTROPICAL, LA FE - COLOMBIA

    Directory of Open Access Journals (Sweden)

    RICARDO ROMÁN-BOTERO

    2013-01-01

    Full Text Available Se investigó la evolución estacional de la estructura térmica en el embalse tropical La Fe, con base en información de variables físicas del cuerpo de agua y variables climatológicas obtenidas en los años 2010 y 2011 y en la aplicación del modelo hidrodinámico ELCOM. El embalse recibe fuentes naturales y agua importada mediante un sistema de bombeo en períodos de estiaje. Se encontró que la influencia del ciclo anual en los flujos de calor atmósfera-lago es relativamente baja, a pesar de que se presentaron condiciones climáticas de El Niño, transición y La Niña. Los cambios en la estructura térmica obedecieron principalmente a las condiciones hidrológicas de los afluentes naturales y a la operación del sistema de bombeo. Se advirtió que el cuerpo norte del embalse está dominado por las plumas de entrada de los afluentes naturales y la captación, mientras el cuerpo sur por la pluma del agua importada.

  16. Argentina: Nuclear power development and Atucha 2

    International Nuclear Information System (INIS)

    In 2014, nuclear energy generated about 5,257 GWh of electricity or a total share of 4.05 % of the total electrical energy of about 129,747.63 GWh kWh produced in Argentina and there has been a trend for this production to increase. Argentina currently has a nuclear production capacity of 1,010 megawatts of electrical energy. However, when the Atucha 2 nuclear power plant is completed and starts commercial operation, it will add 745 megawatts to this electrical production capacity. There are two sites with nuclear power plants in Argentina: Atucha and Embalse. The Embalse nuclear power plant went into operation in 1984. At the Atucha site, the Atucha-1 nuclear power plant started operation in 1974. It was the first nuclear power plant in Latin America. Construction of Atucha-2 started in 1981 but advanced slowly due to funding and was suspended in 1994 when the plant was 81 % built. In 2003, new plans were approved to complete the Atucha 2. I summer 2014 the plant went critical for the first time. The construction was completed under a contract with AECL.

  17. Argentina: Nuclear power development and Atucha 2

    Energy Technology Data Exchange (ETDEWEB)

    Nogarin, Mauro

    2015-08-15

    In 2014, nuclear energy generated about 5,257 GWh of electricity or a total share of 4.05 % of the total electrical energy of about 129,747.63 GWh kWh produced in Argentina and there has been a trend for this production to increase. Argentina currently has a nuclear production capacity of 1,010 megawatts of electrical energy. However, when the Atucha 2 nuclear power plant is completed and starts commercial operation, it will add 745 megawatts to this electrical production capacity. There are two sites with nuclear power plants in Argentina: Atucha and Embalse. The Embalse nuclear power plant went into operation in 1984. At the Atucha site, the Atucha-1 nuclear power plant started operation in 1974. It was the first nuclear power plant in Latin America. Construction of Atucha-2 started in 1981 but advanced slowly due to funding and was suspended in 1994 when the plant was 81 % built. In 2003, new plans were approved to complete the Atucha 2. I summer 2014 the plant went critical for the first time. The construction was completed under a contract with AECL.

  18. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    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.)

  19. Allocation of responsibilities between central and local authorities concerning nuclear power plant licensing

    International Nuclear Information System (INIS)

    This paper examines Belgian regulations on licences to construct and operate nuclear power plants in the context of implementation of the 1980 Act concerning regionalisation. It also reviews the relevant nuclear legislation in certain other countries. (NEA)

  20. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    Science.gov (United States)

    2010-03-03

    ... and support an indigenous civil nuclear industry--the first of many milestones laid out by the... Slovakia is still a year or more away from releasing a nuclear tender, language included in the...

  1. Neutron-skin effect and centrality dependence of high-$p_{\\mathrm{T}}$ observables in nuclear collisions

    CERN Document Server

    Helenius, Ilkka; Eskola, Kari J

    2016-01-01

    We report on our studies of the neutron-skin effects in high-$p_{\\mathrm{T}}$ observables at the LHC. We study the impact of the neutron-skin effect on the centrality dependence of inclusive direct photon, high-$p_{\\mathrm{T}}$ hadron and $W^{\\pm}$ production in nuclear collisions at the LHC. The neutron-skin effect refers to the observation that in spherical heavy nuclei, the tail of the neutron distribution extends farther than the distribution of protons, which can affect observables sensitive to electroweak phenomena in very peripheral collisions. We quantify this effect for direct photons, charged hadrons and W bosons as a function of the collision centrality. In the case of direct photons we find that it will be difficult to resolve the neutron-skin effect, given the uncertainties in the nuclear PDFs and their spatial dependence. With charged hadrons and W's, however, up to 20~\\% unambiguous effects are expected for most peripheral collisions.

  2. US central station nuclear electric generating units: significant milestones (status as of April 1, 1982)

    International Nuclear Information System (INIS)

    Milestone dates are presented concerning the licensing and operating activities of US nuclear power plants. Listings of US nuclear power plants are also presented in alphabetical arrangement by state and alphabetical arrangement by electric utility. Projected US nuclear power plant growth is presented through the year 1990

  3. Central nuclear almirante Alvaro Alberto: study on the phytoplanktonic variation in the region of unity 1 - Angra dos Reis - RJ

    International Nuclear Information System (INIS)

    By according of ''staff'' which has elaborated the first works in phitoplankton, in initial phasis (before operation) of Central Nuclear Almirante Alvaro Alberto - CNAAA Unidade 1, Angra dos Reis, Rio de Janeiro, Brazil we carry out a search about physic - chemicals parameters at same area, during the times of 11 months, too. The efluent region presents a phytoplanktonic comunity of reasonable environmental conditions. The evaluation of biological parameters, or in the words, a natural environment in equilibrium. (author)

  4. Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Massuet, J.; Sabater, J.; Mirallas Esteban, S.

    2016-08-01

    The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

  5. Development of 3D models of buildings for containment of the nuclear power plant of Almaraz and of the Trillo Nuclear with the GOTHIC 8.0 code; Desarrollo de modelos 3D de los edificios de conten cion de la Central Nuclear de Almaraz y de la Central Nuclear de Trillo con el codigo GOTHIC 8.0

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, G.; Bocanegra Melian, R.; Fernandez Cosils, K.; Barreira Pereira, P.; Rey Peinado, L.; Posada Barral, J. M.

    2014-07-01

    The objective of the first phase of the research of CNAT and the UPM project is the construction of several three-dimensional models detailed GOTHIC 8.0 code of containment of a buildings plant type PWR-W and KWU, corresponding to the Central Nuclear de Almaraz (CNA) and Trillo (CNT) respectively. (Author)

  6. Anàlisis de contenció en un accident termohidràulic d'una central nuclear

    OpenAIRE

    Zamora Povea, Imanol

    2013-01-01

    Aquest projecte és el resultat de la cooperació entre el món universitari i l’empresa privada, doncs ha requerit de la cooperació de la Secció d'Enginyeria Nuclear de la Universitat Politècnica de Catalunya i l’àrea Nuclear Services de l’enginyeria IDOM S.A. El treball desenvolupat ha tingut dues vessants diferenciades. La primera línia de treball ha sigut l’elaboració d’un model de la contenció de la central nuclear Vandellòs II mitjançant el codi GOTHIC v7.2a. Així mateix, s’ha tractat d...

  7. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities

    International Nuclear Information System (INIS)

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic

  8. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    Energy Technology Data Exchange (ETDEWEB)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle

    2012-01-31

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic

  9. Evaluation of the radiological impact due to the operation of nuclear power stations in Argentina

    International Nuclear Information System (INIS)

    There are at present in Argentina two commercial nuclear power stations in operation, Atucha I and Embalse, generating about 10% of the total electrical energy output. Atucha I NPP, equipped with a pressure vessel reactor, has an output capacity of 345 MW(e), while Embalse NPP is equipped with Candu-type reactor and its output capacity is 670 MW(e). Both plants operate with natural uranium as a fuel, and heavy water as a coolant and as a moderator. During the operation of both nuclear installations, radioactive fission and activation products are produced. These radioactive materials are for the most part retained within the fuel elements. Most of the radionuclides with diffuse into or are formed within the coolant are removed by the gaseous and liquid waste processing systems. Low-level releases which occur during normal operation are controlled and monitored. Radionuclides may reach the environment through either the gaseous or liquid effluents streams

  10. ¿Es cierto que una central térmica de carbón da lugar a más emisiones radiactivas que una central nuclear?

    OpenAIRE

    J.A. Menéndez

    2009-01-01

    Se ha dicho que, por unidad de energía producida, una central térmica de carbón emite, principalmente en las cenizas volantes, una cantidad de radiactividad 100 veces superior a la que emite una central nuclear de fisión. ¿Es esto cierto?

  11. ¿Es cierto que una central térmica de carbón da lugar a más emisiones radiactivas que una central nuclear?

    Directory of Open Access Journals (Sweden)

    J.A. Menéndez

    2009-08-01

    Full Text Available Se ha dicho que, por unidad de energía producida, una central térmica de carbón emite, principalmente en las cenizas volantes, una cantidad de radiactividad 100 veces superior a la que emite una central nuclear de fisión. ¿Es esto cierto?

  12. Algunos aspectos bioecológicos de la Trucha arcoiris en el embalse Pantano Redondo Cundinamarca, Colombia

    Directory of Open Access Journals (Sweden)

    Forero Eduardo

    2004-12-01

    Full Text Available En el trópico, como especie foránea, la trucha arcoiris tuvo éxito, a pesar de mostrar signos de mal nutrición. Los factores tanto biológicos como ambientales son igualmente importantes para la implantación de cualquier especie en condiciones naturales. La trucha fue introducida
    a los sistemas de alta montañas sin desarrollar estudios ecológicos suficientes, ya que se tuvo en cuenta solamente la temperatura promedio del agua tanto en el trópico como en la zona templada, y no variables ecológicas como el factor determinante de tipo biológico. El embalse
    Pantano Redondo se encuentra ubicado a 6 km de Zipaquirá en la vía a Pacho, Cundinamarca. Coordenadas geográficas 5° 02’N 74° 02’O, a una altitud de 3.160 msnm., la vegetación circundante de coníferas y parches de vegetación nativa. La trucha arcoiris (Onchorhynchus mikiss es un salmonido que presenta cuerpo alargado, fusiforme y cabeza que termina en una boca grande puntiaguda, hendida hacia el nivel de los ojos y con una fila de dientes fuertes en cada una de las mandíbulas que le permiten aprisionar las presas. Onchorhynchus significa nariz ganchuda, característica que se manifiesta con mayor énfasis en los machos en la época de reproducción. Este estudio pretende ofrecer criterios para un adecuado manejo piscícola del embalse, conociendo cuantitativamente y cualitativamente el alimento natural ingerido por la trucha arcoiris. Teniendo en cuenta la inquietud de los pescadores en cuanto a la talla de las presas capturadas a través de todo el año, comparadas con las recolectadas en otros sitios del país. Los parámetros físico-químicos indican una gran uniformidad en cuanto a los componentes medidos y similares condiciones en todas las profundidades haciendo que los hábitats de las truchas sean similares, aunque los ambientes poco profundos originaran condiciones para que las macrófitas o plantas acuáticas originen un hábitat diferente y recurso

  13. A high resolution record of chlorine-36 nuclear-weapons-tests fallout from Central Asia

    Energy Technology Data Exchange (ETDEWEB)

    Green, J.R. E-mail: jaromy.green@gcccks.edu; Cecil, L.D.; Synal, H.-A.; Santos, J.; Kreutz, K.J.; Wake, C.P

    2004-08-01

    The Inilchek Glacier, located in the Tien Shan Mountains, central Asia, is unique among mid-latitude glaciers because of its relatively large average annual accumulation. In July 2000, two ice cores of 162 and 167 meters (m) in length were collected from the Inilchek Glacier for (chlorine-36) {sup 36}Cl analysis a part of a collaborative international effort to study the environmental changes archived in mid-latitude glaciers worldwide. The average annual precipitation at the collection site was calculated to be 1.6 m. In contrast, the reported average annual accumulations at the high-latitude Dye-3 glacial site, Greenland, the mid-latitude Guliya Ice Cap, China, and the mid-latitude Upper Fremont Glacier, Wyoming, USA, were 0.52, 0.16 and 0.76 m, respectively. The resolution of the {sup 36}Cl record in one of the Inilchek ice cores was from 2 to 10 times higher than the resolution of the records at these other sites and could provide an opportunity for detailed study of environmental changes that have occurred over the past 150 years. Despite the differences in accumulation among these various glacial sites, the {sup 36}Cl profile and peak concentrations for the Inilchek ice core were remarkably similar in shape and magnitude to those for ice cores from these other sites. The {sup 36}Cl peak concentration from 1958, the year during the mid-1900s nuclear-weapons-tests period when {sup 36}Cl fallout was largest, was preserved in the Inilchek core at a depth of 90.56 m below the surface of the glacier (74.14-m-depth water equivalent) at a concentration of 7.7 x 10{sup 5} atoms of {sup 36}Cl/gram (g) of ice. Peak {sup 36}Cl concentrations from Dye-3, Guliya and the Upper Fremont glacial sites were 7.1 x 10{sup 5}, 5.4 x 10{sup 5} and 0.7 x 10{sup 5} atoms of {sup 36}Cl/g of ice, respectively. Measurements of {sup 36}Cl preserved in ice cores improve estimates of historical worldwide atmospheric deposition of this isotope and allow the sources of {sup 36}Cl in ground

  14. Environmental management systems implemented in the Spanish nuclear power plants; Sistemas de gestion ambiental implantados en las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Redondo, R.; Fernandez Guisado, M. B.; Hortiguela, R.; Bustamante, L. F.; Esparza, J. L.; Villareal, M.; Yague, F.

    2013-09-01

    The companies that own the Spanish Nuclear Power Plants, aware of social concern and in the context of a growing demanding environmental legislation, have a permanent commitment to the electricity production based on the principles of a maximum respect for the environment, safety, quality, professionalism and continuous improvement. In order to minimize the environmental impact of their plants they have implemented and Environmental Management System based on the ISO 14001 Standard. They minimize the environmental impact by identifying the significant environmental aspects and defining the corresponding objectives. This article describes the referred environmental management systems and their environmental objectives, as applied and defined by the Spanish Nuclear Power Plants. (Author)

  15. Accelerating the global nuclear renaissance: the central challenge of sustainable development

    International Nuclear Information System (INIS)

    The rebirth of nuclear energy has become an unmistakable reality that is gathering speed and momentum on the full world stage. All around the world, old-school anti-nuclear environmentalism is being eclipsed by a new realism that recognises nuclear energy's essential virtue: its capacity to deliver cleanly generated power safely, reliably, and on a massive scale. For serious environmentalists, the real challenge is that nuclear energy is not yet growing fast enough to play its needed role in the clean-energy revolution our world so desperately needs. A fair assessment shows that not one of the commonly cited ''public concerns'' poses a reasonable obstacle to a global expansion of nuclear power: Proliferation, Operational Safety, Cost Reduction, Waste Management. In three areas, governments must take decisive action to grow the nuclear industry: (1) Construct a comprehensive global regime to curtail greenhouse emissions; (2) Elevate nuclear investment to a national and international policy priority; and (3) Support educational development of the nuclear profession for an expanded global role. The global nuclear industry will be indispensable if humanity is to preserve the environment that enabled civilisation to evolve. Governments must emerge from postures of timidity and equivocation to act decisively in support of that industry. Our world is in dire peril, and we have no time to lose

  16. Modularization in construction processes New Nuclear Power Plants; Modularizacion en procesos de construccion de Nuevas Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, I.; Cobos, A.; Herrera Ropero, D.

    2012-07-01

    The aim of this work is that it has the capacity and expertise to analyze the suitability of modular technology design and construction compared to conventional nuclear plants. It will define the criteria for selecting the areas of modularity and the impact on design and its interfaces with engineering, supply, including logistics and construction.

  17. Molecular species identification of Central European ground beetles (Coleoptera: Carabidae using nuclear rDNA expansion segments and DNA barcodes

    Directory of Open Access Journals (Sweden)

    Raupach Michael J

    2010-09-01

    Full Text Available Abstract Background The identification of vast numbers of unknown organisms using DNA sequences becomes more and more important in ecological and biodiversity studies. In this context, a fragment of the mitochondrial cytochrome c oxidase I (COI gene has been proposed as standard DNA barcoding marker for the identification of organisms. Limitations of the COI barcoding approach can arise from its single-locus identification system, the effect of introgression events, incomplete lineage sorting, numts, heteroplasmy and maternal inheritance of intracellular endosymbionts. Consequently, the analysis of a supplementary nuclear marker system could be advantageous. Results We tested the effectiveness of the COI barcoding region and of three nuclear ribosomal expansion segments in discriminating ground beetles of Central Europe, a diverse and well-studied invertebrate taxon. As nuclear markers we determined the 18S rDNA: V4, 18S rDNA: V7 and 28S rDNA: D3 expansion segments for 344 specimens of 75 species. Seventy-three species (97% of the analysed species could be accurately identified using COI, while the combined approach of all three nuclear markers provided resolution among 71 (95% of the studied Carabidae. Conclusion Our results confirm that the analysed nuclear ribosomal expansion segments in combination constitute a valuable and efficient supplement for classical DNA barcoding to avoid potential pitfalls when only mitochondrial data are being used. We also demonstrate the high potential of COI barcodes for the identification of even closely related carabid species.

  18. US central station nuclear electric generating units: significant milestones (status as of July 1, 1980)

    International Nuclear Information System (INIS)

    The status of 189 US nuclear power plants is reported in a table which gives the name, owner, capacity, type, NSSS architect and contractor and data of public announcement, NSSS order, licensing, and initial operation. The plants are also indexed according to state, region, utility, and alphabetical name. The utility nuclear steam supply system orders are also listed

  19. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    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.)

  20. Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector

    International Nuclear Information System (INIS)

    In this work we study the collective phenomena in the central collisions of heavy ions for the Au + Au, Xe + CsI and Ni + Ni systems at incident energies from 150 to 400 MeV/nucleon with the data of the FOPI detector. In order to describe completely the flow of the nuclear matter, we fit the double differential momentum distributions with two-dimensional Gaussian. We study the characteristic parameters of the collective flow (flow range, aspect ratios, flow parameter) versus the charge and the mass of the fragments as well as the incident energy and the centrality of the collisions. The transverse energy is used for selecting the central collisions. The method of the Gaussian fits requires also to reconstruct the reaction plane of the event. Then we correct the parameters for the finite number of particles effects and account for the influence of the acceptance of the detector. We confirm the importance of the thermal motion for the light charge or mass fragments and, conversely, the predominance of the collective motion for the heavy fragments. A common flow angle for all the types of particles is highlighted for the first time, demonstrating the power of the method of the Gaussian fits; The evolution of the other parameters confirms the observations done with other methods of flow analysis. These results should contribute to put constraints on the collision models and to enlarge our knowledge of the properties of the nuclear matter. (author)

  1. Superiority of centralized procurement and its technical and economic analysis for nuclear power intensification construction

    International Nuclear Information System (INIS)

    The intensified management is the basic orientation for modernized enterprise group to improve efficiency and benefit. For most industrial enterprises, in the implementation of intensification management process, the centralized procurement is one of most efficient paths. At present most of the international's and domestic outstanding enterprises are studying and positively using this approach. This article indicated that the centralized procurement mode is inevitable during intensification construction process based on the theoretical analysis of the advantage of centralized procurement and the economic analysis of typical cases. (author)

  2. Internalization of externalities in the generation costs of electric power centrals of carbon, combined cycle and nuclear; Internalizacion de externalidades en los costos de generacion de centrales electricas de carbon, ciclo combinado y nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gomez R, M.C. [Universidad Anahuac del Norte (Mexico); Palacios H, J.; Ramirez S, R.; Alonso V, G. [ININ, Carretera Mexico-Toluca Km. 36.5 Ocoyoacac 52750 Edo. de Mexico (Mexico)]. e-mail: fgrivera@avantel.net

    2007-07-01

    The technologies of electric power generation that use fossil fuels, they incorporate in the Even Total Cost of Generation (CTNG) only the direct costs of generation (investment, fuel costs, operation costs and maintenance). nevertheless, the nuclear energy incorporates besides the direct costs, the externalities that causes to the human health and the environment. In this work the CTNG is calculated that incorporates the externalities, of a thermoelectric power station of coal, a plant of combined cycle and of four reactors of Generation III (ABWR, ACR, AP1000 and EPR). The obtained results show that the nuclear power station has smaller CTNG that the technologies that use fossil fuels. It is important to stand out that they are only considering the externalities of the stage of electricity generation, for what the mining phase and transport of the fuel toward the central are not considered in the present document. (Author)

  3. A prototype system dynamic model of nuclear and radiological export controls in Central Asia and the Caucasus; enhancing the effectiveness of preventing illicit nuclear material trafficking

    International Nuclear Information System (INIS)

    An urgent need calls out for improved border security and export control systems in the Central Asian and Caucasus regions to prevent illicit nuclear and radioactive materials trafficking. Effective nuclear and radiological exports controls are essential because these regions contain numerous nuclear facilities and radioactive materials as well as lie at the crossroads between seekers and suppliers of technologies that could be employed in nuclear and radiological weapons. Porous and unprotected borders compound these concerns. Moreover, the states within these regions are struggling with forming new regulations and laws, obtaining sufficient portal monitoring equipment, training customs and border security personnel, and coordinating these activities with neighboring states. Building this infrastructure all at once can severely task any government. Thus, unsurprisingly, most of these states have inadequate export control and border security systems. To enable each state in these regions determine how to better prevent illicit nuclear and radiological materials trafficking, the authors have developed a prototype system dynamics model focused on evaluating and improving of effectiveness of export controls. System dynamics modeling, a management tool that grew out of the field of system engineering and nonlinear dynamics, uses two structures: causal loop diagrams and stock and flow diagrams. The former shows how endogenous systematic factors interact with each other to produce feedback mechanisms that results in either balancing or reinforcing loops. A classic example is a arms race, modeled as a vicious cycle or reinforcing loop. In addition to interacting with each other, causal loops influence the flow of stock, which is material concern. In the export control system dynamics model, the stock represents nuclear and radioactive materials. System dynamics modelling is an iterative process that is continually modified by user input. Therefore, export control

  4. Deslizamientos de ladera y riesgos geológicos en el entorno del embalse de Itoiz (cuenca del Iarati, Navarra

    Directory of Open Access Journals (Sweden)

    CASAS, A.M., REBOLLO, A.

    2001-01-01

    Full Text Available El análisis geológico y geomorfológico de la cuenca del río Irati (incluyendo los ríos Irati y Urrobi entre Aoiz y Oroz-Betelu muestra la existencia de numerosos deslizamientos, originados por la dinámica natural de las vertientes, que han condicionado el propio curso de ambos ríos. El mayor de estos deslizamietos, de tipo complejo y polifásico, alcanza un volumen de 20 hm3. Los deslizamientos están asociados a las propias condiciones litológicas de la zona (materiales del flysch Eoceno de la cuenca de Jaca-Pamplona, a su estructura (variaciones de la dirección estructural pirenaica, y, fundamentalmente a la evolución del relieve de la zona en el terciario terminal y el cuaternario, que supuso el encajamiento rápido de la red fluvial. El llenado del denominado embalse de Itoiz, cuya presa principal, de más de 100 m. de altura presenta el estribo izquierdo anclado sobre el mayor deslizamiento encontrado en la cuenca, afectará negativamente a la estabilidad de la ladera y podría ocasionar una serie de riesgos catastróficos para las poblaciones situadas aguas abajo y arriba de la citada presa, que se detallan en el presente artículo.

  5. The reactor ALLEGRO and the sustainable nuclear energy in Central Europe

    OpenAIRE

    Gadó János

    2014-01-01

    The Visegrád-4 countries (CZ, HU, PL and SK) would like to use nuclear energy on the long run. The construction of new Generation 3+ nuclear units probably belong in each country to this realm. These reactors will provide safe and cheap electric energy approximately until the end of the 21st century. In order to use nuclear energy in the 22nd century, sustainability of fuel supply shall be achieved by applying Generation 4 breeder reactors with fast spectrum. The corresponding research and de...

  6. The reactor ALLEGRO and the sustainable nuclear energy in Central Europe

    Directory of Open Access Journals (Sweden)

    Gadó János

    2014-01-01

    Full Text Available The Visegrád-4 countries (CZ, HU, PL and SK would like to use nuclear energy on the long run. The construction of new Generation 3+ nuclear units probably belong in each country to this realm. These reactors will provide safe and cheap electric energy approximately until the end of the 21st century. In order to use nuclear energy in the 22nd century, sustainability of fuel supply shall be achieved by applying Generation 4 breeder reactors with fast spectrum. The corresponding research and development is organized now in the framework of the V4G4 Centre of Excellence establshed by the nuclear research institutes of the region with a strong technical support from the French CEA. The most important milestone of these efforts is the start-up of the ALLEGRO reactor that shall demonstrate the viability of the gas cooled fast reactor technology.

  7. The reactor ALLEGRO and the sustainable nuclear energy in Central Europe

    Science.gov (United States)

    Gadó, János

    2014-09-01

    The Visegrád-4 countries (CZ, HU, PL and SK) would like to use nuclear energy on the long run. The construction of new Generation 3+ nuclear units probably belong in each country to this realm. These reactors will provide safe and cheap electric energy approximately until the end of the 21st century. In order to use nuclear energy in the 22nd century, sustainability of fuel supply shall be achieved by applying Generation 4 breeder reactors with fast spectrum. The corresponding research and development is organized now in the framework of the V4G4 Centre of Excellence establshed by the nuclear research institutes of the region with a strong technical support from the French CEA. The most important milestone of these efforts is the start-up of the ALLEGRO reactor that shall demonstrate the viability of the gas cooled fast reactor technology.

  8. 1989 annual report of the Rossendorf Central Institute of Nuclear Research

    International Nuclear Information System (INIS)

    The research and development results are classified by research lines. Each section starts with an introduction summing up the developments of the particular field of work, followed by progress reports on specific projects, contributions on partial results not published so far, and summaries of 1989 publications. Research priorities are, among others, the fields of nuclear spectroscopy; ion-beam solid state physics; positron emission tomography; nuclear trace technology; neutron doping, and accelerator development. (DG)

  9. Radioisotope production using U-120 cyclotron, Central Institute for Nuclear Research, Rossendorf (DDR)

    International Nuclear Information System (INIS)

    The method of radionuclide production at the Rossendorf U-120 cyclotron and chemical reprocessing of the products produced into radiopharmaceuticals, aimed at application in nuclear medice, are described. The radionuclides are produced by target irradiation at nuclear reactions (4He, 2n), (d, 2n), (d, n), (d, α) and others. 67Ga, 81Rb-21mKr, 211At, 111In, 123I, 18F radionuclide production are considered in detail. The Rossendorf U-120 cyclotron beam parameters are also presented

  10. International assistance to upgrade the safety of Soviet-designed nuclear power plants. Selected activities in Eastern and Central Europe and the countries of the former Soviet Union

    International Nuclear Information System (INIS)

    The overview is merely a snapshot of nuclear safety activities to assist the countries of Eastern and Central Europe and the former Soviet Union. While many other activities are planned or ongoing, this publication is meant to provide a general overview of the world community's commitment to improving the safety of Soviet-designed nuclear reactors

  11. A cosmic-ray nuclear event with an anomalously strong concentration of energy and particles in the central region

    International Nuclear Information System (INIS)

    A cosmic-ray-induced nuclear event detected in an emulsion chamber is described. The event consist of 217 shower cores with ΣEγ=1.275 TeV. In a logarithmic scale, energy and particles are emitted most densely at the small lateral distance corresponding to 0.5 mm; 77% of the total energy and 61% of the total multiplicity are inside a radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and nonisotropic azimuthal distribution

  12. The service lifetime of Spain's nuclear plants; La vida util de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez-Bolanos, M.

    2008-07-01

    In recent years consideration has been given to the long-term operation of nuclear reactors, beyond their originally foreseen design lifetime. This article analyses the legal and safety requirements that this implies, in the wake of the document dealing with this issue that was approved by the Plenary of the CSN in April 2005. The article is completed with an interview with Dale Klein, president of the United States regulatory body, in which he describes the experience accumulated in his country, where lifetime extensions have already been approved for 50 plants. (Author)

  13. Decree no 77-623 of 6 June 1977 amending Decree no 73-278 of 13 March 1973 setting up a Superior Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

    International Nuclear Information System (INIS)

    Under this Decree, the Central Service for the Safety of Nuclear Installations is placed from now onwards within the Directorate of Mines which comes under the Ministry of Industry, Trade and Crafts. The Head of the Central Service for the Safety of Nuclear Installations and his deputy are appointed by Order of the Minister of Industry, Trade and Crafts, on the proposal of the Director of Mines. (NEA)

  14. Crecimiento y reproducción de la mojarra amarilla (Caquetaia kraussii Steindachner, 1878 en el embalse de Urrá, Colombia

    Directory of Open Access Journals (Sweden)

    Delio Solano-Peña

    2013-08-01

    Full Text Available Objetivo. Evaluar los parámetros biológicos de crecimiento y reproducción de la mojarra amarilla en el embalse de Urrá. Materiales y métodos. Se colectaron 593 individuos para estudiar las relaciones talla-peso y la biología reproductiva. La relación longitud-peso y el factor de condición se estimaron con WT =a LTb y Fc =WT/LTb, y se estimó proporción sexual, tallas e índices de madurez sexual, época de desove, diámetro de los ovocitos y fecundidad. Resultados. 235 individuos fueron hembras, 212 machos, 28 indiferenciados y 118 no sexados. La relación longitud-peso para sexos combinados fue WT =0.013 (± 0.04 LT3.07 (± 0.03, r =0.99, n =593. La proporción sexual fue 1.1:1, la talla media de madurez sexual para sexos combinados fue 11.0 cm LT, el diámetro de los ovocitos fue 1376 μm y la fecundidad promedio por desove fue 1732 ovocitos. Conclusiones. La mojarra amarilla mostró crecimiento isométrico en el embalse de Urrá, con talla media de captura menor que en el resto de la cuenca del río Sinú, sin dimorfismo sexual a la talla, período de reproducción prolongado y desoves parciales, ovocitos grandes y baja fecundidad, con correlación entre el factor de condición y el índice de madurez sexual, pero independientes del nivel de las aguas del embalse.

  15. Business plan of the Nuclear Information Center, Central Research Institute of Electric Power Industry

    International Nuclear Information System (INIS)

    The Nuclear Information Center was born on June 15, 1983, in the Research and Development Headquarters. The purpose of its establishment is to analyze and deliver synthetically the information on nuclear power generation as electric power industry by collecting all information, and to contribute to the safe operation and the improvement of reliability of nuclear power generation. The necessity of positively utilizing the information on the experience of nuclear power generation was recognized particularly owing to the TMI accident. The organization of the Center is composed of the divisions of statistical analysis, information analysis, technical development, information management and general affairs. The ''Committee of raising grade of nuclear power station information'', the ''Expert committee on information analysis and evaluation'' and so on are organized. The number of personnel of the Center is 21, and 12 of them are temporarily transferred from electric power companies. The business of the Center is as shown by the organization of the Center, and it is briefly explained. As the effective means to obtain the information from foreign countries, the Center has utilized the NOTEPAD system managed by the INPO of USA. Its information can be read through the communication networks of KDD and USA. (Kako, I.)

  16. Central depression in nuclear density and its consequences for the shell structure of superheavy nuclei

    International Nuclear Information System (INIS)

    The influence of the central depression in the density distribution of spherical superheavy nuclei on the shell structure is studied within the relativistic mean-field theory. A large depression leads to the shell gaps at the proton Z=120 and neutron N=172 numbers, whereas a flatter density distribution favors N=184 and leads to the appearance of a Z=126 shell gap and to the decrease of the size of the Z=120 shell gap. The correlations between the magic shell gaps and the magnitude of the central depression are discussed for relativistic and nonrelativistic mean field theories

  17. Central depression in nuclear density and its consequences for the shell structure of superheavy nuclei

    CERN Document Server

    Afanasjev, A V

    2005-01-01

    The influence of the central depression in the density distribution of spherical superheavy nuclei on the shell structure is studied within the relativistic mean field theory. Large depression leads to the shell gaps at the proton Z=120 and neutron N=172 numbers, while flatter density distribution favors N=184 for neutrons and leads to the appearance of a Z=126 shell gap and to the decrease of the size of the Z=120 shell gap. The correlations between the magic shell gaps and the magnitude of central depression are discussed for relativistic and non-relativistic mean field theories.

  18. Changes of the main parameters of the primary heat transport system of the Embalse NPP after the replacement of the divider plates of the steam generators

    International Nuclear Information System (INIS)

    Divider plates of the four steam generators were repaired at Embalse NPP during the outage of 2002. This task led to a reduction of heavy water by-pass from the hot to the cold side. As a consequence of this, some Primary Heat Transport System (PHTS) parameters were affected. The main results of this work are the following: a) Bulk PHTS flow did not change significantly; b) Inlet Header temperature dropped 2,8 C degrees at full power; c) Quality at Outlet Header is now practically negligible. (author)

  19. Metodología de evaluación de las reglas de operación de embalses en avenidas

    OpenAIRE

    Bianucci, Sandra Paola; Sordo Ward, Alvaro; Pérez Díaz, Juan Ignacio; García-Palacios, Jaime H.; Cuevas Velasquez, Victor; Garrote de Marcos, Luis

    2011-01-01

    El avance de la presión antrópica sobre las márgenes de los cauces, y la creciente dificultad técnica, política y social para ejecutar nuevos proyectos de grandes presas, promueve la necesidad de utilizar más eficientemente los sistemas de control de avenidas existentes. En el presente trabajo se presenta una metodología de análisis para evaluar y comparar las estrategias de gestión de embalses, considerando su operación individual, a fin de establecer la más adecuada. En particular se c...

  20. Incidencia de procesos AMD en la hidroquímica de embalses afectados en la Faja Pirítica Ibérica

    OpenAIRE

    Santisteban Fernández, María

    2015-01-01

    En Europa, los principales problemas de contaminación por metales pesados en ias aguas de ríos y embalses están asociados al drenaje ácido de mina, que tiene lugar en la Faja Pirftica Ibérica (FPI), situada en el SO Europeo, a lo largo de las provincias de Huelva y Sevilla, así como en el Sur de Portugal. La intensa actividad minera en esta zona metalogenética, ha dejado, en las cuencas de los ríos afectados un legado de 86 minas abandonadas, con sus pozos, socavones y cortas, sus innumerable...

  1. Variación espacio-temporal del nitrógeno y fósforo en el embalse del Neusa

    OpenAIRE

    Guillot Monroy Gabriel; Niño Garcia Juan Pablo

    2003-01-01

    El Embalse del Neusa es un cuerpo de agua oligo-mesotrófico ubicado en la cordillera oriental de los Andes colombianos, utilizado en la regulación de caudales

  2. Los suelos de la cuenca del Embalse del Añarbe. Propiedades e influencia de sus características en la calidad de las aguas.

    OpenAIRE

    Merino, A.

    1995-01-01

    Los suelos de la cuenca del Embalse del Añarbe se caracterizan,   en general, por su riqueza en materia orgánica, carácter   fuertemente ácido, niveles medios-bajos de fósforo biodisponible   e importantes contenidos de Al y Mn libres. Bajo condiciones de   buena cubierta vegetal existen bajas tasas de movilización de   elementos en suspensión. Sin emargo, debido a las fuertes   pendientes y elevada puvliosidad de la cuenca, en terrenos   desprovistos de vegetación pueden...

  3. Caracterización del estado de la edafofauna asociada a zonas intervenidas en los predios del Embalse de Chisacá

    OpenAIRE

    Díaz Triana Julián Esteban; Amat García Germán Domingo

    2006-01-01

    En los predios del embalse de Chisacá (Usme, Cundinamarca) se estudió la composición, riqueza, diversidad, abundancia y biomasa de las comunidades de artrópodos epígeos en vegetación secundaria introducida:
    pastizales, plantaciones de especies exóticas, parches de retamo (Ulex europaeus); y vegetación secundaria nativa: matorrales mixtos de vegetación de subpáramo. Se utilizaron trampas de caída (pitfall) para la captura
    de los organismos. Se estimaron índices y aplicaro...

  4. Cost comparison of central electric power generation using coal and nuclear fuels

    International Nuclear Information System (INIS)

    This paper addresses the current and expected future costs of generating electricity with the two available practical modes of power generation, coal and nuclear. It describes the procedures and inputs used to arrive at the conclusion that generation with nuclear fuels will be about 16% more economical than generation with the best coal alternative. Recognizing the uncertainty in long range estimates of this type, various sensitivity checks are developed to determine how much the capital, fuel, and operating costs would have to change to force a change in the ranking of the alternatives. The results are current estimates of the costs of generating electricity in the future in the middle western area of the United States with large nuclear units, and with comparably sized and comparably loaded coal units firing high and low sulfur coals

  5. Industrial risks - Traceability and the centralization of responsibilities are essential for nuclear safety

    International Nuclear Information System (INIS)

    A new regulation has been implemented in France concerning the safety and the transparency of nuclear activities. The main changes are the centralisation of the responsibilities through first, a clear reaffirmation that the operator of the facility is the only responsible for the facility operations and secondly the limitation of sub-contracting to the level 3 for instance a society chosen by EDF to provide services can sub-contract some of these services but the sub-contractor himself is not allowed to sub-contract. The transparency of nuclear activities is improved through making it compulsory to have a written record of any decision taken in a nuclear facility. (A.C.)

  6. International conference on a nuclear-weapon-free zone in central Asia, 15-16 September 1997 Tashkent, Uzbekistan. Building an integral part of the global nuclear security system

    International Nuclear Information System (INIS)

    This Conference is the first fruit of the joint effort by the Central Asian States to counter external threats and challenges. The decision to declare Central Asia a nuclear-weapon-free zone is a further manifestation of the Central Asian States' shared interest in ensuring security, stability and peace for all the inhabitants of the region and in creating the necessary -indeed, the essential- conditions for its sustainable development and prosperity

  7. Phylogeny and biogeography of Poecilia (Cyprinodontiformes: Poeciliinae) across Central and South America based on mitochondrial and nuclear DNA markers.

    Science.gov (United States)

    Ho, Adeljean L F C; Pruett, Christin L; Lin, Junda

    2016-08-01

    Poeciliids are a diverse group of small Neotropical fishes, and despite considerable research attention as models in ecology and evolutionary biology, our understanding of their biogeographic and phylogenetic relationships is still limited. We investigated the phylogenetic relationships of South and Central American Poecilia, by examining 2395 base pairs of mitochondrial DNA (ATPase 8/6, COI) and nuclear DNA (S7) for 18 species across six subgenera. Fifty-eight novel sequences were acquired from newly collected specimens and 20 sequences were obtained from previously published material. Analyses of concatenated and partitioned mitochondrial DNA and nuclear DNA sets resulted in a well-supported phylogeny that resolved several monophyletic groups corresponding to previously hypothesized subgenera and species complexes. A divergence-dating analysis supported the hypothesis of the genus Poecilia dispersing into Central America in the early Pliocene (ancestors of Psychropoecilia+Allopoecilia+Mollienesia: 7.3-2.0Mya) from predominantly South America. Subsequently, one lineage (subgenus Allopoecilia: 5.1-1.3Mya) expanded deeper into South America from Lower-Central America, and one lineage expanded from Nuclear-Central America into South America (subgenus Mollienesia: 0.71-0.14Mya). The subgenus Mollienesia diverged into three monophyletic groups that can be identified by nuptial male dorsal fin morphology and inner jaw dentition. A subclade of the unicuspid short-fins (subgenus Mollienesia) was the lineage that expanded into South America during the middle Pleistocene. Species in this subclade are now distributed across northern South America, where they are partially sympatric with Allopoecilia. However the P. (A.) caucana complex was not monophyletic, with P. (A.) wandae clustering in the Mollienesia subclade that expanded into South America. It is apparent that characters (body size, scale count, pigmentation, and gonopodium morphology) used to define the P. (A

  8. Nuclear fuel cycle facilities in the world (excluding the centrally planned economies)

    International Nuclear Information System (INIS)

    Information on the existing, under construction and planned fuel cycle facilities in the various countries is presented. Some thirty countries have activities related to different nuclear fuel cycle steps and the information covers the capacity, status, location, and the names of owners of the facilities

  9. Statistical analysis about corrosion in nuclear power plants; Analisis estadistico de la corrosion en centrales nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Naquid G, C.; Medina F, A.; Zamora R, L. [Instituto Nacional de Investigaciones Nucleares, Gerencia de Ciencia de Materiales, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    Nowadays, it has been carried out the investigations related with the structure degradation mechanisms, systems or and components in the nuclear power plants, since a lot of the involved processes are the responsible of the reliability of these ones, of the integrity of their components, of the safety aspects and others. This work presents the statistics of the studies related with materials corrosion in its wide variety and specific mechanisms. These exist at world level in the PWR, BWR, and WWER reactors, analysing the AIRS (Advanced Incident Reporting System) during the period between 1993-1998 in the two first plants in during the period between 1982-1995 for the WWER. The factors identification allows characterize them as those which apply, they are what have happen by the presence of some corrosion mechanism. Those which not apply, these are due to incidental by natural factors, mechanical failures and human errors. Finally, the total number of cases analysed, they correspond to the total cases which apply and not apply. (Author)

  10. Simulation of power pulses during large break LOCAs in natural and slightly enriched cores in the Embalse NPP

    International Nuclear Information System (INIS)

    In the frame of a joint technical feasibility study between Nucleoelectrica Argentina and Atomic Energy of Canada of using slightly enriched uranium fuel (with 0.9 w% U235) in Embalse NPP, a CANDU-6, loss of coolant accidents (LOCAs) simulations were performed. The power pulse due to two large breaks were simulated: 35% of a Reactor Inlet Header (RIH) and 80% of a Reactor Outlet Header (ROH). For each break size four simulations were performed for different initial conditions o scenarios and for Natural Uranium (NU) and slightly enriched uranium (SEU) cores. The power transients have been simulated using the 3D diffusion, spatial kinetics neutronic program PUMA (developed in Argentina) and the thermal-hydraulics program CATHENA. These codes were coupled by an iterative methodology. The CATHENA thermal-hydraulic simulation results (fuel temperatures and coolant temperatures and densities) were used as input of the PUMA calculation and the time dependent power distribution calculated by PUMA was later applied as input for a new CATHENA calculation. The process was repeated up to convergence. Single channel models were developed to calculate the relevant three key safety parameters: the maximum transient fuel centerline temperature, the maximum transient sheath temperature and the maximum transient stored energy. The main results of power pulse calculation show that the behavior of the SEU core are similar to the NU one. The result of the three safety parameter values show that in the hypothetical large break LOCA occurrence the fuel channel integrity is maintained. The maximum fuel temperature values are lower than the melting temperature of UO2 , the maximum stored enthalpies are lower than the fuel break-up limit and the maximum sheath temperature are lower than Zircalloy fusion temperature. The values of these safety parameters are similar or slightly lower for the SEU core compared with the NU one. (author)

  11. ASPECTOS REPRODUCTIVOS DEL PEJERREY PATAGÓNICO (Odontesthes hatcheri Eigenmann, 1909 EN EL EMBALSE EZEQUIEL RAMOS MEXIA (ARGENTINA

    Directory of Open Access Journals (Sweden)

    Alejandro Dománico A

    2008-12-01

    Full Text Available Objetivo. Estudiar el ciclo sexual y la fecundidad del pejerrey patagónico, especie de alto valor comercial y deportivo, en el embalse Ezequiel Ramos Mexía (Neuquén, Río Negro; Argentina. Materiales y métodos. Se colectaron 9307 ejemplares. El ciclo sexual se estudió mediante la observación macroscópica de las gónadas y la fecundidad absoluta se calculó con la técnica volumétrica. Resultados. La talla de primera madurez sexual (Lm 50% se estimó a través del ajuste de una curva logística. El desove tuvo lugar en primavera y principios de verano (septiembre a diciembre. La talla de primera madurez sexual, en las hembras, fue de 244,37 mm (Lt. La fecundidad absoluta varió entre 3.976 ovocitos en una hembra de 296 mm (Lt y 190 g y 20.879 ovocitos en una hembra de 420 mm (Lt y 704 g. Conclusiones. No se observó una relación significativa entre la fecundidad relativa y la longitud total de los ejemplares. La proporción de sexos resultó equilibrada en las clases de longitud intermedias, pero mostró una preponderancia de hembras en las mayores. El ciclo ovárico es altamente estacional y coincide con el de poblaciones de la especie en otros ambientes patagónicos. La fecundidad, en cambio, resultó más elevada que la observada en el lago Moreno, situado en la región cordillerana.

  12. The Fossil Nuclear Outflow in the Central 30 pc of the Galactic Center

    CERN Document Server

    Hsieh, Pei-Ying; Hwang, Chorng-Yuan; Shimajiri, Yoshito; Matsushita, Satoki; Koch, Patrick M; Iono, Daisuke

    2016-01-01

    We report a new 1-pc (30") resolution CS($J=2-1$) line map of the central 30 pc of the Galactic Center (GC), made with the Nobeyama 45m telescope. We revisit our previous study of the extraplanar feature called polar arc (PA), which is a molecular cloud located above SgrA* with a velocity gradient perpendicular to the Galactic plane. We find that the PA can be traced back to the Galactic disk. This provides clues of the launching point of the PA , roughly $6\\times10^{6}$ years ago. Implications of the dynamical time scale of the PA might be related to the Galactic Center Lobe (GCL) at parsec scale. Our results suggest that in the central 30 pc of the GC, the feedback from past explosions could alter the orbital path of the molecular gas down to the central tenth of parsec. In the follow-up work of our new CS($J=2-1$) map, we also find that near the systemic velocity, the molecular gas shows an extraplanar hourglass-shaped feature (HG-feature) with a size of $\\sim$13 pc. The latitude-velocity diagrams show tha...

  13. Central nervous system assessment in nuclear medicine. Clinical aspects: tracers and indications

    International Nuclear Information System (INIS)

    Nuclear neuroimaging techniques allow the study of functional and neurochemical aspects of the human brain in vivo. SPECT (Single Photon Emission Computed Tomography) as well as PET (Positron Emission Tomography) are non-invasive techniques which present two modalities: functional and biochemical. The functional one provides information about neuronal activity measured through metabolism (PET) or regional brain perfusion (SPECT, RMN f). Biochemical neuroimaging provides information on the chemical substrates involved in neurotransmission (receptors, transporters and enzymes) and allows the study of the synaptic activity through imaging of the different brain regions. This information about neurochemical aspects of neurotransmission is an exclusive field of nuclear neuroimaging techniques SPECT and PET. In this paper we discuss the tracers used for each modality of brain SPECT as well as their main clinical uses. (author)

  14. Hinkley point C: A new chance for nuclear power plant construction in central Europe?

    International Nuclear Information System (INIS)

    This text focuses on the decision of the European Commission on the admissibility of state support for the expansion of Hinkley Point C, a British nuclear power plant. The European Commission not only influenced the development of energy sector in the UK with its decision, but also sent a strong signal that it is possible to use state aid for new nuclear power plants in the EU. The example of the Czech Republic shows the way this signal may be perceived by governments and energy stakeholders and how it can influence the national debates about the construction of new nuclear power plants, even before the detailed information about the whole case of state aid for Hinkley Point C has been published. -- Highlights: •Text deals with the EU's decision on the state support for the NPP Hinkley Point C. •This decision sends a strong signal about possible state aid for new NPPs in the EU. •Other member states are possible to consider similar pattern of financing. •The case of the Czech Republic is used to demonstrate the situation

  15. ESTUDIO BIOGEOQUÍMICO DEL EMBALSE SUATA, VENEZUELA, DE ACUERDO AL CONTENIDO METÁLICO DE SUS SEDIMENTOS DE FONDO, AGUAS Y PECES

    Directory of Open Access Journals (Sweden)

    María A. Álvarez

    2012-01-01

    Full Text Available Se realizó un estudio biogeoquímico mediante el análisis del contenido metálico en muestras de sedimentos de fondo, aguas y peces colectadas mensualmente durante un año. Los sedimentos se encontraron enriquecidos antrópicamente con COT, Zn y Cd, presentando un nivel de contaminación de moderado a fuerte, y según la fracción biodisponible, un riesgo muy alto de Zn y mediano de Ni, Cd, Cr y Co. Estas especies llegarían al embalse, principalmente, mediante la escorrentía superficial de desechos de industrias de producción animal ubicadas en los alrededores y aportes del Rio Aragua. Aunque la desorción de los metales desde los sedimentos es improbable dado el pH donde se encuentran (8-9 y la concentración de los metales en las aguas y peces fue menor que las máximas permitidas en las normativas, se encontraron indicios de bioacumulación de Hg y Ni en el hígado de los peces que sugieren mantener el monitoreo del embalse.

  16. Model of automatic fuel management for the Atucha II nuclear central with the PUMA IV code

    International Nuclear Information System (INIS)

    The Atucha II central is a heavy water power station and natural uranium. For this reason and due to the first floor reactivity excess that have this type of reactors, it is necessary to carry out a continuous fuel management and with the central in power (for the case of Atucha II every 0.7 days approximately). To maintain in operation these centrals and to achieve a good fuels economy, different types of negotiate of fuels that include areas and roads where the fuels displace inside the core are proved; it is necessary to prove the great majority of these managements in long periods in order to corroborate the behavior of the power station and the burnt of extraction of the fuel elements. To carry out this work it is of great help that a program implements the approaches to continue in each replacement, using the roads and areas of each administration type to prove, and this way to obtain as results the one regulations execution in the time and the average burnt of extraction of the fuel elements, being fundamental this last data for the operator company of the power station. To carry out the previous work it is necessary that a physicist with experience in fuel management proves each one of the possible managements, even those that quickly can be discarded if its don't fulfill with the regulatory standards or its possess an average extraction burnt too much low. For this it is of fundamental help that with an automatic model the different administrations are proven and lastly the physicist analyzes the more important cases. The pattern in question not only allows to program different types of roads and areas of fuel management, but rather it also foresees the possibility to disable some of the approaches. (Author)

  17. Central depression in nuclear density and its consequences for the shell structure of superheavy nuclei

    OpenAIRE

    Afanasjev, A. V.; Frauendorf, S.

    2006-01-01

    The influence of the central depression in the density distribution of spherical superheavy nuclei on the shell structure is studied within the relativistic mean field theory. Large depression leads to the shell gaps at the proton Z=120 and neutron N=172 numbers, while flatter density distribution favors N=184 for neutrons and leads to the appearance of a Z=126 shell gap and to the decrease of the size of the Z=120 shell gap. The correlations between the magic shell gaps and the magnitude of ...

  18. Nuclear starburst-driven evolution of the central region in NGC 6764

    CERN Document Server

    Leon, S; Laine, S; Kotilainen, J K; Schinnerer, E; Lee, S -W; Krips, M; Reunanen, J; Scharwächter, J

    2007-01-01

    We study the CO and the radiocontinuum emission in an active galaxy to analyze the interplay between the central activity and the molecular gas. We present new high-resolution observations of the CO(1-0) and CO(2-1) emission lines, and 3.5 cm and 20 cm radio continuum emission in the central region of the LINER/starburst galaxy NGC 6764. The galaxy has an outflow morphology in radio continuum, spatially coincident with the CO and H$\\alpha$ emission, and centered slightly off the radio continuum peak at the LINER nucleus. The total molecular gas mass in the center is about 7x10^8 \\msun, using a CO luminosity to total molecular gas conversion factor that is three times lower than the standard one. CO(1-0) emission is found near the boundaries of the radio continuum emission cone. The outflow has a projected expansion velocity of 25 km/s relative to the systemic velocity of NGC6764. About 4x 10^6 \\msun of molecular gas is detected in the outflow. The approximate location (~1 kpc) of the dynamical inner Lindblad ...

  19. Inspection experience with RA-3 spent nuclear fuel assemblies at CNEA's central storage facility

    International Nuclear Information System (INIS)

    Aluminum-based spent nuclear fuel from Argentina's RA-3 research reactor is to be shipped to the Savannah River Site near Aiken, South Carolina, USA. The spent nuclear fuel contains highly enriched uranium of U.S. origin and is being returned under the US Department of Energy's Foreign Research Reactor/Domestic Research Reactor (FRR/DRR) Receipt Program. An intensive inspection of 207 stored fuel assemblies was conducted to assess shipping cask containment limitations and assembly handling considerations. The inspection was performed with video equipment designed for remote operation, high portability, easy setup and usage. Fuel assemblies were raised from their vertical storage tubes, inspected by remote video, and then returned to their original storage tube or transferred to an alternate location. The inspections were made with three simultaneous video systems, each with dedicated viewing, digital recording, and tele-operated control from a shielded location. All 207 fuel assemblies were safely and successfully inspected in fifteen working days. Total dose to personnel was about one-half of anticipated dose. (author)

  20. Toward fostering the scientific and technological literacy establishment of the 'Central Scientific and Technological Museum-Institute' and nuclear development

    International Nuclear Information System (INIS)

    The public in general does not necessarily have enough knowledge for the reasonable decision making in the application of scientific and technological development even in the ear of the Information Society. However strongly the necessity of the consensus in the scientific policy like nuclear R and D is required, it is impossible to attain the goal, unless the scientific literacy of the general public is. In order to improve it the role of the scientific museum as a social educational facility is very important. In this respect, there still remains vast room to improve in the Japanese museum system and its activities. The concept of the 'Central Scientific and Technological Museum-Institute', which also operates very small-sized reactor for the educational use, is developed in this paper. (author)

  1. Theoretical study of the central depression of nuclear charge density distribution by electron scattering

    International Nuclear Information System (INIS)

    The charge form factors of elastic electron scattering for isotones with N=20 and N=28 are calculated using the phase-shift analysis method, with corresponding charge density distributions from relativistic mean-field theory. The results show that there are sharp variations at the inner parts of charge distributions with the proton number decreasing. The corresponding charge form factors are divided into two groups because of the unique properties of the s-states wave functions, though the proton numbers change uniformly in two isotonic chains. Meanwhile, the shift regularities of the minima are also discussed, and we give a clear relation between the minima of the charge form factors and the corresponding charge radii. This relation is caused by the diffraction effect of the electron. Under this conclusion, we calculate the charge density distributions and the charge form factors of the A=44 nuclei chain. The results are also useful for studying the central depression in light exotic nuclei. (authors)

  2. Desarrollo e implantación en un APS de una metodologia para identificar los fallos de inicio de vida en una Central Nuclear

    OpenAIRE

    González Celades, María

    2015-01-01

    El proyecto Desarrollo e implantación en un Análisis Probabilista de Seguridad de una metodología para identificar los fallos de inicio de vida en una central nuclear tiene como objetivo el desarrollo de una herramienta para identificar qué fallos de componente forman parte del período de inicio de infancia, de una central nuclear. Estos fallos deberían ser eliminados de la Base de Datos del Análisis Probabilista de Seguridad (BD APS) ya que no son representativos de la operación real de la c...

  3. The peaceful uses of nuclear energy and national borders in Central Europe

    International Nuclear Information System (INIS)

    The German National Group of AIDN/INLA also invited to its Regensburg meeting representatives from neighbouring states. The main theme of the meeting was the legal problems resulting from transfrontier impacts of the peaceful uses of nuclear energy, and the Chernobyl accident just added topical importance to this subject that already before had been a problem of burning interest. The papers and discussions encompass the whole range of principle legal problems as well as the differing approaches adopted by the various national legal systems and the resulting problems encountered in practice. Solutions already existing - as e.g. on the basis of multi- or bilateral agreements - were summarised, and outline solutions and lines of orientation for future practice were discussed. (orig.)

  4. CAE meteorological database for the PC CREAM program. Atmospheric dilution factor in different points of the CAE (Centro Atomico Ezeiza) and of the argentine nuclear power plants

    International Nuclear Information System (INIS)

    In the first part of this work, the EZEIZA.MET file, with the meteorological database of the surroundings of the Ezeiza Atomic Center, is prepared and incorporated into the library of the PC CREAM program. This program was developed by the National Radiological Protection Board and the European Union. Information provided by the National Meteorological Service was used, corresponding to the Ezeiza Meteorological Station during the period 1996-2005. In the second part, a methodology to estimate the atmospheric dilution factor at a point using the PLUME module of the PC CREAM, is presented. The developed methodology was used to estimate the dilution factor at points close to the Ezeiza Atomic Center and nuclear power plants Atucha I and Embalse. The developed methodology was used to estimate the dilution factor at points close to the Ezeiza Atomic Center and nuclear power plants Atucha I and Embalse. In the first case the file with the generated meteorological database is used, whereas for the nuclear power plants the already existing ATUCHALO.MET and EMBALSE.MET files are used. The dilution factors obtained are compared with those obtained in previous work. The proposed methodology is a useful tool to estimate the dilution factors in a simple and systematic way, and simultaneously allows the update of the meteorological information used in the estimations. (author)

  5. Volcanic and seismic hazards at a proposed nuclear power site in central Java

    Science.gov (United States)

    McBirney, Alexander R.; Serva, Leonello; Guerra, M.; Connor, Charles B.

    2003-08-01

    A nuclear power plant site has been proposed near the base of Mount Muria, a long-dormant volcano in Indonesia. Over a period of eight years the volcanic and seismic hazards were investigated, first by the contractor and later by a joint team of Indonesian geologists and consultants to the International Atomic Energy Agency. In order to assess the risk posed by a large volcano for which there is no record of historical eruptions, it was necessary to determine the age of the last activity by geological and geochronological means and to deduce from this whether the volcano posed a credible risk. Similarly, because there was no adequate record of seismic activity, the seismic hazards were investigated mainly by geological, geomorphological, and geophysical methods that identified and characterized potential seismogenic sources related to the volcano or tectonic movements (i.e. active/capable faults). Muria Volcano has not erupted since about two thousand years ago, but the last activity was sufficiently recent to rule out any assumption that the volcano is extinct. Detailed studies indicated that the proposed site may be vulnerable to the effects of air-borne tephra, pyroclastic flows and surges, debris flows, lahars, and opening of new vents. A more serious factor, however, was the poor geotechnical properties of the foundation material that required a careful analysis of the seismic hazards. Although the project was suspended, the study proved useful, because it provided an opportunity to develop procedures and techniques that could be applied in similar studies elsewhere.

  6. Development of the process of energy transfer from a nuclear Power Plant to an intermediate temperature electrolyse; Desarrollo del proceso de transferencia de energia desde una central nuclear a un electrolizador de temperatura intermedia

    Energy Technology Data Exchange (ETDEWEB)

    Munoz Cervantes, A.; Cuadrado Garcia, P.; Soraino Garcia, J.

    2013-07-01

    Fifty million tons of hydrogen are consumed annually in the world in various industrial processes. Among them, the ammonia production, oil refining and the production of methanol. One of the methods to produce it is the electrolysis of water, oxygen and hydrogen. This process needs electricity and steam which a central nuclear It can be your source; Hence the importance of developing the transfer process energy between the two. The objective of the study is to characterize the process of thermal energy transfer from a nuclear power plant to an electrolyzer of intermediate temperature (ITSE) already defined. The study is limited to the intermediate engineering process, from the central to the cell.

  7. Nuclear fragmentation in central collisions: Ni + Au from 32 to 90 A*MeV

    International Nuclear Information System (INIS)

    Heavy ion collisions are one of tools for studying nuclear system far away from its equilibrium state. This work concerns the most violent collisions in the Ni + Au system for incident energies ranging from 32 up to 90 AMeV. These events were detected with the multidetector INDRA and selected by the Principal Component Analysis (multidimensional analysis). This method classifies the events according their detection features and their degree of dissipation. We observed two deexcitation mechanisms: a fusion/fission - evaporation process and a multifragmentation process. Those two coexist from 32 to 52 AMeV whereas only one subsists at 90 AMeV. For those two mechanisms, an component was observed which seems to be linked to the initial phase of the reaction. The energy fluctuations of this component leads to variations in the energy deposit which determines the deexcitation of the system. The experimental multifragmentation data of the Ni + Au system (52 and 90 AMeV) were compared to the predictions of a statistical model and to the experimental data of the system Xe + Sn at 50 AMeV (also detected with INDRA). These comparisons show the lack of collective radial energy for fragments (Z≥10) in the Ni + Au system, and show that the degree of multifragmentation depends of the thermal excitation energy. Mean kinetic energies of particles and lights fragments (Z≥10) are larger in the Ni + Au system than the Xe + Sn system. This observation shows that these particles are more sensitive to the entrance channel for an asymmetric system than for a symmetric system (for the same number of nucleons). (author)

  8. Genkai Nuclear Power Station Units 1 and 2. Upgrading of central instrumentation equipment

    International Nuclear Information System (INIS)

    Genkai Unit No.1 started commercial operation in October 19754 and Genkai Unit No.2 in March 1981. They are two-loop PWR plants with the electrical power output of 559 MW each. Units No.1 and 2 have been successfully operation and accumulated good results to data. Meanwhile, striving to maintain and enhance reliability, Kyushu Electric Power Company has been systematically implementing upgrade and repair works by reflecting knowledge acquired from nuclear power plant operating experience in Japan and overseas and the outcome of technological developments. The main control boards had been modified several times, as had other equipment before this upgrading project started. Although there was no significant problem in the safe and stable plant operation using the boards as they were, the scalability and maintainability became worse. This would become a problem in future in view of the continuation of safe and stable plant operation for a long time. We thought to enhance the reliability, operability and monitorability further and decided to replace the main control boards with new ones equipped with more CRTs that are the same type as those used in the latest Genkai Units No.3 and 4 located in the same site. And, the related systems, including the primary and secondary system control systems, plant computers, and alarm and monitor cabinets, were replaced with the units featuring the latest technology. Hereafter, this project may be called as CBR in short. The replacement work was implemented by coinciding with the 20th refueling outage (March 6 to August 18, 2001) for Unit No.1 and with the 16th refueling outage (March 16 to September 20, 2001) for Unit No.2. (author)

  9. ARGOS PHWR 380. Argentine offer of a safer pressurized heavy-water reactor of 380 MW. '...a many-eyed guardian...' concerned about nuclear power plant safety

    International Nuclear Information System (INIS)

    Reactor vendors in most countries have had lean pickings for the past decade, and ordering seems unlikely to show much growth until the shock wave from the Chernobyl accident has died away. Paradoxically, however, at least one firm sees a niche in the market. ENACE - the Empresa Nuclear Argentina de Centrales Electricas, or Argentine Nuclear Power Plant Corporation - is stepping out into the market place with a newly-designed 380 MWe nuclear power plant. The plant is equipped with a pressurized heavy-water reactor of the pressure vessel type (PHWR). ENACE has adopted new boundary design conditions and has embodied a number of special features to assure safety and economy in operation. The major shareholder in ENACE is the Argentine National Atomic Energy Commission (CNEA). ENACE is the architect-engineer for the NPP projects of the Argentine nuclear programme. It has a licensing agreement with Siemens AG's Kraftwerk Union AG, which is its minor shareholder. Under this agreement, ENACE has the right to use the Siemens-KWU PHWR technology, which was originally developed for the MZFR reactor in the Federal Republic of Germany, as well as their know-how in pressurized (light-) water reactors (PWRs) design and construction. The CNEA also has agreements with Atomic Energy of Canada Ltd. for the transfer of technology related to CANDU-type PTHWRs. The CNEA and ENACE have acquired considerable practical experience from the construction and operation of the 367 MWe Atucha I PHWR and the 648 MWe Embalse PTHWR; ENACE is currently building Argentina's third nuclear power plant, Atucha II, a 745 MWe PHWR. (author)

  10. Variaciones temporales del fitoplancton de los ríos tributarios y emisario del embalse C. Gelsi (Tucumán, Argentina)

    OpenAIRE

    Silvia N Martinez de Marco; Beatriz C Tracanna

    2012-01-01

    En este trabajo se estudiaron las variaciones temporales del fitoplancton de los tributarios (ríos Salí, Tapia y Vipos) y del emisario (río Salí) del embalse C. Gelsi. La abundancia algal mínima se obtuvo en verano con una biomasa de 0,19-0,58 µg Cl-a L-1 y la máxima en invierno o primavera con una biomasa de 5,43-6,79 µg Cl-a L-1. En los tributarios se destacaron las diatomeas pennadas sobresaliendo Diatoma vulgare y Cymbella affinis y en el río Salí (emisario) dominaron las céntricas especi...

  11. EFECTO DE TILAPIA Oreochromis niloticus SOBRE LA PRODUCCIÓN PESQUERA DEL EMBALSE EL GUÁJARO ATLÁNTICO - COLOMBIA

    Directory of Open Access Journals (Sweden)

    Pedro Caraballo G, M.Sc.

    2009-12-01

    Full Text Available Objetivo. Evaluar el efecto de tilapia Oreochromis niloticus sobre la producción pesquera en el embalse de El Guájaro, departamento del Atlántico, Colombia. Materiales y métodos. El embalse tiene un área aproximada de 14.000 ha y allí pescan diariamente 2.500 pescadores provenientes de ocho municipios que rodean el ecosistema. Por medio de evaluaciones mensuales del desembarco durante 48 horas en todos los puertos, fue evaluada la composición y abundancia de las capturas en 1988 y 2002. Los resultados de la evaluación hecha en 2002 fueron comparados con los obtenidos en 1988. Resultados. 38 especies de peces, perteneciendo a 14 familias fueron identificadas. Sólo las dos especies que dominan las capturas, presentaron una variación en su participación global. La producción durante 2002 fue de 431 ton/mes, superior a las 84 ton/mes evaluadas en el año 1988. Durante 2002, las capturas fueron dominadas por tilapia Oreochromis niloticus (53% y arenca Triportheus magdalenae (36% lo que representa una variación en la composición de las capturas que, durante 1988 fueron respectivamente de 13% y 73%. Esta variación no afectó la proporción de herbívoros y carnívoros que se mantuvo en 90-10%. Conclusiones. La variación en la composición y abundancia de la producción total implica el desplazamiento de una especie nativa (Triportheus magdalenae por una exótica (Oreochromis niloticus, hecho que viene siendo observado en toda la cuenca del Magdalena en esta década.

  12. Radiation exposure and central nervous system cancers: A case-control study among workers at two nuclear facilities

    International Nuclear Information System (INIS)

    A nested case-control study was conducted among workers employed between 1943 and 1977 at two nuclear facilities to investigate the possible association of primary malignant neoplasms of the central nervous system (CNS) with occupational exposure to ionizing radiation from external and internal sources. Eighty-nine white male and female workers, who according to the information on death certificates dies of primary CNS cancers, were identified as cases. Four matched controls were selected for each case. External radiation exposure data were available from film badge readings for individual workers, whereas radiation dose to lung from internally deposited radionuclides, mainly uranium, was estimated from area and personnel monitoring data and was used in analyses in lieu of the dose to the brain. Matched sets were included in the analyses only if information was available for the case and at least one of the corresponding controls. Thus, the analyses of external radiation included 27 cases and 90 matched controls, and 47 cases and 120 matched controls were analyzed for the effects of radiation from internally deposited uranium. No association was observed between deaths fron CNS cancers and occupational exposure to ionizing radiation from external or internal sources. However, due to the small number of monitored subjects and low doses, a weak association could not be ruled out. 43 refs., 1 fig., 15 tabs

  13. Statistical analysis of the wind around a nuclear power plant; Analisis estadistico del viento alrededor de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Tejeda, A; Alvarez, Oscar; Contreras, A. D.; Jauregui, E. [Universidad Veracruzana, (Mexico)

    1996-12-31

    In order to show an appropriate methodology for the climatic analysis of the wind, some of the recent results in the investigation of the field flow around the Laguna Verde Nuclear Power Station, at Veracruz State (Mexico,) through the angular correlation coefficients and contingency tables among the registered wind directions by a meteorological tower at the levels of 10 and 60 meters high are presented. Finally, by applying an objective analysis of the data some conclusions are obtained in connection with the local winds with the mesoscale systems. [Espanol] Con el objeto de mostrar una metodologia apropiada en el analisis climatico del viento, se presentan algunos resultados recientes en la investigacion del campo de flujo en los alrededores de la central nucleoelectrica de Laguna Verde, Veracruz (Mexico), a traves de los coeficientes de correlacion angulares y de tablas de contingencia entre las direcciones del viento registradas por una torre meteorologica en los niveles de 10 y 60 metros de altura. Finalmente, aplicando analisis objetivo de los datos, se obtienen algunas conclusiones sobre la conexion de los vientos locales con los sistemas de mesoescala.

  14. El zooplancton como indicador de la calidad del agua en embalses: un estudio en el ámbito de actuación de la Confederación Hidrográfica del Júcar

    OpenAIRE

    García Chicote, Jara

    2015-01-01

    En este trabajo se estudia la ecología del zooplancton en embalses situados en cuencas mediterráneas, utilizando los datos obtenidos en invierno y verano, durante los años 2006 a 2009, en 20 embalses del ámbito de actuación de la Confederación Hidrográfica del Júcar. Con esta información se evalúa el potencial del zooplancton como bioindicador de la eutrofización; de modo que se propone su inclusión en los estudios de seguimiento de calidad de aguas en el ámbito de la Directiva Marco del Agu...

  15. Evaluación del impacto hidrológico del rompimiento de la presa del embalse "El Isiro" en las zonas residenciales y agrícolas ubicadas en la planicie del río Coro

    Directory of Open Access Journals (Sweden)

    Miguel Ángel Perozo Ynestroza

    2011-01-01

    Full Text Available Los estudios hidrológicos de la cuenca del río Coro han desestimado los alivios y el colapso de la presa del embalse "El Isiro", el cual se encuentra en dicha cuenca y sirve de fuente para el abastecimiento de agua potable a la ciudad de Coro en Venezuela. Aguas abajo de este embalse, se encuentra la planicie de inundación de dicho río, la cual está en proceso de urbanización. Además, en la actualidad se está desarrollando un proyecto agrícola para aprovechar las bondades que en este sentido tiene la planicie en cuestión. Por lo tanto, este trabajo se ocupó de incorporar la subcuenca que drena al embalse "El Isiro" y tomar en cuenta la posibilidad del rompimiento de la presa usando los software HEC-HMS y HEC-GeoHMS, los cuales permiten el uso de Sistemas de Información Geográfica (SIG, para optimizar la formulación del modelo conceptual de la cuenca. De acuerdo con los resultados obtenidos, se puede apreciar el alto impacto de considerar el rompimiento de la presa del embalse "El Isiro" en las zonas residenciales y agrícolas, en términos de caudales máximos y volúmenes escurridos. Este trabajo representa un aporte muy valioso para la gestión del riesgo de inundación en la zona en estudio.

  16. Nuclear magnetic resonance imaging of the central nervous system; A good use of the possibilities. Kernspinresonantie-tomografie van het centrale zenuwstelsel; Een goed gebruik van de mogelijkheden

    Energy Technology Data Exchange (ETDEWEB)

    Knaap, M.S. van der (Rijksuniversiteit Utrecht (Netherlands). Academisch Ziekenhuis); Valk, J. (Vrije Universiteit, Amsterdam (Netherlands). Afdeling Radiodiagnostiek en Neuroradiologie)

    1989-12-09

    In this article a review is given of the use of magnetic resonance imaging for the central nervous system. An example of the screening of the population for multiple scelerosis is given. A good preliminary examination and the supply of relevant information to the person which performs the imaging is necessary. (R.B.). 9 figs.; 4 tabs.

  17. Investigation on the environmental radioactivity of the proposed location for Nuclear Power Plant Station in Ujung Watu area, Central Java

    International Nuclear Information System (INIS)

    During the period of November 1981 and March 1983, preliminary investigation of the environmental radioactivity at the proposed location of nuclear power station in Ujung Watu area in Central Java has been carried out. The investigated area covers an area within a radius of 5 km of the proposed location. During this period a total of about 319 environmental samples which consist of soils, grasses, drinking and surface waters, several food-item of agricultural and sea product have been collected. Measurement of exposure and absorbed dose level were also carried out at 52 and 27 locations within the investigated area. Measurement of exposure dose was carried out using scintillation probe detector coupled to rate meter and absorbed dose level was measured using TL-dosemeter. The samples were analysed for the gross - α and β radioactivity, the content of H-3, Cs-137 and Sr-90. Results showed that the radiation level of the area has a range of 4 ± 18 mR/h with an average of about 4.6 x 1.4 mR/h. Absorbed dose showed a value within the range of 4.5 - 6.9 x 10-7 Gy/day with an average value of 6.2 ± 1.2 x 10-7 Gy/day. The value area is within the normal range of natural level. Measurement of fall-out indicated that the integral impact of Cs-137 and Sr-90 from fall-out to this area were about 2.6 MBq/km2 and 1.5 MBg/km2 respectively. However, no Cs-137 and Sr-90 were detected in the samples collected during this study. (author). 9 refs

  18. Masses and scaling relations for nuclear star clusters, and their co-existence with central black holes

    Science.gov (United States)

    Georgiev, Iskren Y.; Böker, Torsten; Leigh, Nathan; Lützgendorf, Nora; Neumayer, Nadine

    2016-04-01

    Galactic nuclei typically host either a nuclear star cluster (NSC, prevalent in galaxies with masses ≲1010 M⊙) or a massive black hole (MBH, common in galaxies with masses ≳1012 M⊙). In the intermediate-mass range, some nuclei host both an NSC and an MBH. In this paper, we explore scaling relations between NSC mass (M_NSC) and host-galaxy total stellar mass (M_{star ,gal}) using a large sample of NSCs in late- and early-type galaxies, including a number of NSCs harbouring an MBH. Such scaling relations reflect the underlying physical mechanisms driving the formation and (co)evolution of these central massive objects. We find ˜1.5σ significant differences between NSCs in late- and early-type galaxies in the slopes and offsets of the relations reff,NSC-M_NSC, reff,NSC-M_{star ,gal} and M_NSC-M_{star ,gal}, in the sense that (i) NSCs in late types are more compact at fixed M_NSC and M_{star ,gal}; and (ii) the M_NSC-M_{star ,gal} relation is shallower for NSCs in late types than in early types, similar to the M_BH-M_{star ,bulge} relation. We discuss these results in the context of the (possibly ongoing) evolution of NSCs, depending on host-galaxy type. For NSCs with an MBH, we illustrate the possible influence of an MBH on its host NSC, by considering the ratio between the radius of the MBH sphere of influence and reff,NSC. NSCs harbouring a sufficiently massive black hole are likely to exhibit surface brightness profile deviating from a typical King profile.

  19. Central-to-peripheral nuclear modification factors in Pb-Pb collisions at $\\sqrt{s_{NN}}$= 17.3 GeV

    CERN Document Server

    Antinori, F; Badalà, A; Barbera, R; Belogianni, A; Bhasin, A; Bloodworth, Ian J; Bombara, M; Bruno, G; Bull, S A; Caliandro, R; Campbell, M; Carena, W; Carrer, N; Clarke, R F; Dainese, A; De Haas, A P; De Rijke, P C; Di Bari, D; Di Liberto, S; Divià, R; Elia, D; Evans, D; Feofilov, G A; Fini, R A; Ganoti, P; Ghidini, B; Grella, G; Helstrup, H; Hetland, K F; Holme, A K; Jacholkowski, A; Jones, G T; Jovanovic, P; Jusko, A; Kamermans, R; Kinson, J B; Knudson, K; Kolojvari, A A; Kondratiev, V; Králik, I; Kravcakova, A; Kuijer, P; Lenti, V; Lietava, R; Løvhøiden, G; Manzari, V; Martinská, G; Mazzoni, M A; Meddi, F; Michalon, A; Morando, M; Nappi, E; Navach, F; Norman, P I; Palmeri, A; Pappalardo, G S; Pastircák, B; Pisút, J; Pisútová, N; Platt, R J; Posa, F; Quercigh, Emanuele; Riggi, F; Röhrich, D; Romano, G; Safarík, K; Sándor, L; Schillings, E; Segato, G F; Sené, M; Sené, R; Snoeys, W; Soramel, F; Spyropoulou-Stassinaki, M; Staroba, P; Toulina, T A; Turrisi, R; Tveter, T S; Urbán, J; Valiev, F F; Van den Brink, A; Van de Ven, P; Van den Vyvre, P; van Eijndhoven, N; Van Hunen, J J; Vascotto, Alessandro; Vik, T; Villalobos Baillie, O; Vinogradov, L I; Virgili, T; Votruba, M F; Vrláková, J; Závada, P

    2005-01-01

    We present central-to-peripheral nuclear modification factors, R_CP, for the p_T distributions of K^0_S, Lambda, Anti-Lambda, and negatively charged particles, measured at central rapidity in Pb-Pb collisions at top SPS energy. The data cover the 55% most central fraction of the inelastic cross section. The K^0_S and Lambda R_CP(p_T) are similar in shape to those measured at sqrt{s_NN} = 200 GeV at RHIC, though they are larger in absolute value. We have compared our K^0_S R_CP data to a theoretical calculation. The prediction overestimates the data at p_T \\approx 3-4 GeV/c, unless sizeable parton energy loss is included in the calculation.

  20. Fuel cycle management by the electric enterprises and spanish nuclear Power plants; Gestion del ciclo de combustible por las empresas electricas y centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Celma, E. M.; Gonzalez, C.; Lopez, J. V.; Melara, J.; Lopez, L.; Martinez, J. C.; Culbras, F.; Blanco, J.; Francia, L.

    2015-07-01

    The Nuclear Fuel Group reports to the Technology Committee of the UNESA Nuclear Energy Committee, and is constituted by representatives of both the Spanish Utilities and the Nuclear Power Plants. The Group addresses the nuclear plant common issues in relation to the operation and management of the nuclear fuel in their different stages of the Fuel Cycle. The article reviews the activities developed by the Group in the Front-End, mainly in the monitoring of international programs that define criteria to improve the Fuel Reliability and in the establishment of common bases for the implementation of changes in the regulation applying the nuclear fuel. Concerning the Back-End the Group focuses on those activities of coordination with third parties related to the management of used fuel. (Author)

  1. Engineering and maintenance applied to safety-related valves in nuclear power plants; Ingenieria y mantenimiento aplicado a valvulas relacionadas con la seguridad en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Verdu, M. F.; Perez-Aranda, J.

    2014-04-01

    Nuclear Division in Iberdrola engineering and Construction has a team with extensive experience on engineering and services works related to valves. Also, this team is linked to UNESA as Technical support and Reference Center. Iberdrola engineering and construction experience in nuclear power plants valves, gives effective response to engineering and maintenance works that can be demanded in a nuclear power plant and it requires a high degree of qualification and knowledge both in Operation and Outages. (Author)

  2. El pretensado y su vigilancia en las centrales nucleares españolas : Descripción y análisis histórico de los resultados

    OpenAIRE

    Codinach Fitó, Marc

    2008-01-01

    La utilización del pretensado en las centrales nucleares es un tema singular que difiere de la utilización que se le suele dar a un sistema de armadura activa convencional. En esta tesina se hace un estado del conocimiento de esta tecnología situándolo en el contexto de las centrales nucleares españolas. Además se analizan los datos obtenidos de las vigilancias realizadas hasta hoy en los diferentes edificios de contención de las centrales nucleares españolas y se extraen la...

  3. Analysis of the evolution of the collective dose in nuclear power plants in Spain; Analisis de la evolucion de la dosis colectiva en las centrales nucleares de Espana

    Energy Technology Data Exchange (ETDEWEB)

    Ponjuan Reyes, G.; Ruibia Rodiz, M. A. de la; Rosales Calvo, M.; Labarta Mancho, T.; Calavia Gimenez, I.

    2011-07-01

    This article presents an analysis of the evolution of occupational collective dose of the Spanish nuclear power plants during the period 2000 - 2008 within the international context, by the Nuclear Safety Council (CSN) in order to have information contrasted to assessing the extent of application of the ALARA criteria in the Spanish plants and identify areas of priority attention.

  4. The Nuclear Safety Council's Instruction IS-30 on program requirements of fire protection at nuclear power plants; La instruccion IS-30 del consejo de Seguridad Nuclear sobre requisitos del programa de proteccion contraincendios en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

    The Nuclear Safety Councils Instrumentation IS-30 is the standard that establishes the fire protection program requirements for the Spanish nuclear power plants with operating license in order to satisfy the two fire protection objectives, which are the adoption of the defense-in-depth principle for fire protection and, by fire area confinement, to ensure that one train of components needed to achieve and maintain the safe shutdown conditions is free of fire damage, and that radioactive liberation is minimized. (Author)

  5. Bacterial diversity in the sediments of a temperate artificial lake, Rapel reservoir Diversidad bacteriana en sedimentos de un lago artificial temperado, embalse Rapel

    Directory of Open Access Journals (Sweden)

    CRISTINA DORADOR

    2007-06-01

    Full Text Available Rapel reservoir is an eutrophic system in Chile that has undergone a series of anthropogenic impacts in recent decades. To provide a better understanding of the processes occurring in the reservoir, we examined bacterial composition from surface sediments using traditional microbiology techniques and molecular biology tools. Our results showed significant temporal variation in the physical and chemical composition of the water column, but no depth-related differences during the study period. To detect temporal changes in bacterial composition, cultivable heterotrophic bacteria, heterotrophic iron oxidizing bacteria, and sulfate-reducing bacteria were extracted from the surface sediments and their concentration measured. Microbial diversity in sediments was represented by closest relatives of eight different bacterial phyla. The most frequently recovered phylotypes in the clone library of 16S rDNA were related to sulfate-reducing bacteria belong to the Deltaproteobacteria groupEl embalse Rapel es un sistema eutrófico en Chile que ha experimentado diversos impactos antropogénicos en las últimas décadas. Para conocer mejor los posibles procesos que ocurren en el embalse, la composición bacteriana fue estudiada en la zona superficial de los sedimentos utilizando técnicas microbiológicas tradicionales y herramientas de biología molecular. Nuestros resultados mostraron variación temporal significativa en la composición física y química del agua, no encontrándose diferencias de las variables medidas entre superficie y fondo en la columna de agua durante el período de estudio. Para detectar cambios temporales en la concentración y composición bacteriana, se midieron bacterias heterótrofas, heterótrofas oxidantes de fierro y bacterias reductoras de sulfato extraídas de la superficie de los sedimentos. La diversidad bacteriana en los sedimentos estuvo representada por 8 diferentes Phyla del dominio Bacteria. Los filotipos m

  6. Evaluation of fatigue damage in nuclear power plants: evolution and new tools of analysis; Evaluacion del dano a fatiga en centrales nucleares: evolucion y nuevas herramientas de analisis

    Energy Technology Data Exchange (ETDEWEB)

    Cicero, R.; Corchon, F.

    2011-07-01

    This paper presents new fatigue mechanisms requiring analysis, tools developed for evaluation and the latest trends and studies that are currently working in the nuclear field, and allow proper management referring facilities the said degradation mechanism.

  7. Law no. 111/1996 on the safe deployment of nuclear activities - A law central to the Romanian nuclear law system

    International Nuclear Information System (INIS)

    Law no. 111/1996 on the safe deployment of nuclear activities was published in its original form in the Official Gazette of Romania, Part no. 267 of 29th October 1996. The complexity of this law prevents from performing a comprehensive analysis of the legal provisions thereof for which reason the author shall review only those aspects he consider to be relevant to the issues dealt with by this law. Furthermore, as the author intends his undertaking to be a comparative analysis of Law no. 111/1996 in its successive stages - from its issue till the present - he uses mostly the present tense even though the law has been amended and in some respects the changes are quite significant. The presentation contains the following three sections: 1. Passing of Law no. 111/1996 on the safe deployment of nuclear activities - a turning point in the development of the Romanian nuclear law; 2. The successive modifications of Law no. 111/1996 on safe deployment of nuclear activities; 3. Law no. 193/2003 for the modification and completion of Law no. 111/1996 on the safe deployment of nuclear activities - a key moment in the modernization of Romanian nuclear law and harmonization with the relevant international requirement. In conclusion, the issue of Law no. 111/1996 on safe deployment of nuclear activities represents a turning point in the development of Romanian nuclear law. From this moment on one may regard it as a modern area of the Romanian law, European in spirit. The pre-existent legal framework - namely the Law no. 61/1974 on the deployment of activities in the Romanian nuclear field - was no longer up to the existing standards and its replacement by a new, modern law, fully harmonized with the European and NATO accession requirements was a must. Such a new, European law was to fully guarantee the safe deployment of nuclear activities for exclusively peaceful purposes, so that the requirements regarding the nuclear safety, protection of professionally exposed personnel

  8. Fifth research coordination meeting on the measurement and evaluation of transactinium isotope nuclear data. Central Bureau for Nuclear Measurements, Geel, Belgium, 1-3 September 1982

    International Nuclear Information System (INIS)

    Proceedings of the fifth meeting of the participants in the IAEA Coordinated Research Programme to measure and evaluate the required nuclear decay data of heavy element radionuclides, convened by the IAEA Nuclear Data Section on 1-3 September 1982 at CBNM, Geel, Belgium. The meeting participants reviewed the data requirements, updated and extended the recommended list of half-lives, and continued to review the status of alpha and gamma radiation spectra emitted in the decay of transactinium isotopes. (author)

  9. IGALL, key factor in long-term operation of nuclear power plants; IGALL, factor clae en la operacion a largo plazo de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calatayud, M. A.; Sainero, J.

    2014-10-01

    The ageing management is a key factor during the Long Term Operation of Nuclear Power Plants and also during the licensed period; IGALL is an international accepted reference guide that shows how the manage it. The knowledge of the reasons to develop this project, how the results have been reached and the public access to them for future use of the Nuclear Power Plants, are the purpose of this article. (Author)

  10. Experience with a mobile data storage device for transfer of studies from the critical care unit to a central nuclear medicine computer

    International Nuclear Information System (INIS)

    The introduction of mobile scintillation cameras has enabled the more immediate provision of nuclear medicine services in areas remote from the central nuclear medicine laboratory. Since a large number of such studies involve the use of a computer for data analysis, the concurrent problem of how to transmit those data to the computer becomes critical. A device is described using hard magnetic discs as the recording media and which can be wheeled from the patient's bedside to the central computer for playback. Some initial design problems, primarily associated with the critical timing which is necessary for the collection of gated studies, were overcome and the unit has been in service for the past two years. The major limitations are the relatively small capacity of the discs and the fact that the data are recorded in list mode. These constraints result in studies having poor statistical validity. The slow turn-around time, which results from the necessity to transport the system to the department and replay the study into the computer before analysis can begin, is also of particular concern. The use of this unit has clearly demonstrated the very important role that nuclear medicine can play in the care of the critically ill patient. The introduction of a complete acquisition and analysis unit is planned so that prompt diagnostic decisions can be made available within the intensive care unit. (author)

  11. Final results of the cadmium and spectral ratios obtained inside of the fuel rod positioned in the central position of the IPEN/MB-01 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bitelli, Ulysses d' Utra; Mura, Luiz Ernesto C.; Santos, Diogo Feliciano dos, E-mail: ubitelli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Lambiasi, Beatriz G.N. [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

    2015-07-01

    The spectral ratios are very important to determine some nuclear reactors parameters such as reaction rates, fuel lifetime, etc and some safety operational conditions. This study aims to determine the spectral ratios in 2 (two) spatial positions located inside the core of the Nuclear Reactor IPEN/MB-01. These places are at the central position of the nuclear reactor core in an asymptotic neutron flux region. The experiment consists in inserting different activation foil detectors inside an experimental fuel rod. The experimental rod is assembled at the central position of the reactor core. Activation neutron foil detectors of different elements such as {sup 197}Au, {sup 238}U, {sup 45}Sc, {sup 58}Ni, {sup 24}Mg, {sup 47}Ti and {sup 115m}In were used to cover a large range of neutron spectrum. Saturation activity per target nucleus was obtained by gamma spectrometry using a HPGe system. The experimental cadmium ratios compared with values computed by MCNP-4C code show good agreement. (author)

  12. Hallazgo de un endocarpo del genero Acer en niveles del Cretácico superior del embalse de Pedrezuela (Guadalix de la Sierra

    Directory of Open Access Journals (Sweden)

    Lesiak, M. A.

    1996-12-01

    Full Text Available In this paper is described and discussed an endocarp of Acer genus that exhibits a morphology like the living species A. buergerianum Miquel. The fruit was met in the upper part of Cretaceous series from the Pedrezuela barrier of Madrid Community. We propose a new denomination for the plant that contains this endocarp: Acer palaeobuergerianum n. fsp. This name has only taxonomic value. The prefix is give in order to the age and -buergerianum by its similarity with the actual species.Se describe y discute un endocarpo fósil perteneciente al género Acer, encontrado en el Cretácico superior del embalse de Pedrezuela (Madrid. Este fruto muestra una marcada semejanza con los endocarpos de la especie actual Acer buergerianum Miquel. Se propone una nueva denominación, con valor taxonómico, para la planta: Acer palaeobuergerianum n. fsp. El prefijo palaeo sugiere su edad y la denominación - buergerianum su semejanza morfológica con la especie actual.

  13. Caracterización del estado de la edafofauna asociada a zonas intervenidas en los predios del Embalse de Chisacá

    Directory of Open Access Journals (Sweden)

    Díaz Triana Julián Esteban

    2006-12-01

    Full Text Available En los predios del embalse de Chisacá (Usme, Cundinamarca se estudió la composición, riqueza, diversidad, abundancia y biomasa de las comunidades de artrópodos epígeos en vegetación secundaria introducida:
    pastizales, plantaciones de especies exóticas, parches de retamo (Ulex europaeus; y vegetación secundaria nativa: matorrales mixtos de vegetación de subpáramo. Se utilizaron trampas de caída (pitfall para la captura
    de los organismos. Se estimaron índices y aplicaron fórmulas para calcular los parámetros estudiados mediante
    herramientas informáticas. La comunidad de mayor diversidad, riqueza y número de grupos exclusivos fue la de matorrales mixtos. Se encontró mayor similitud entre las comunidades de pastizales y plantaciones de exóticas, y el grupo más representativo en abundancia y biomasa fue Diptera. Comparando la estructura trófica de las comunidades se observó variaciones en la riqueza, abundancia y biomasa de los grupos tróficos; estos cambios se deben a efectos de disturbios antrópicos en el área que alteraron y reemplazaron el bosque altoandino y la artropofauna nativa.

  14. Nuclear

    International Nuclear Information System (INIS)

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  15. Physical start up of the Dalat nuclear research reactor with the core configuration having a central neutron trap

    International Nuclear Information System (INIS)

    After the reactor has reached physical criticality with the core configuration exempt from central neutron trap on 1 November 1983, the core configuration with a central neutron trap has been arranged in the reactor and the reactor has reached physical criticality with this core configuration at 17h48 on 18 December 1983. The integral worths of different control rods are determined with accuracy. 2 refs., 24 figs., 18 tabs

  16. Strain measurements of nuclear power plant steam generator antiseismic supports

    International Nuclear Information System (INIS)

    The nuclear power plants steam generators have different types of structural supports. One of these types are the antiseismic supports, which are intended to be under stress only if a seismic event takes place. Nevertheless, the antiseismic supports lugs, that are welded to the steam generator vessel, are subjected to thermal fatigue because of the temperature cycles related with the shut down and start up operations performed during the life of the nuclear power plant. In order to evaluate the stresses that the lugs are subjected to, several strain gages were welded on two supports lugs, positioned at two heights of one of the Embalse nuclear power plant steam generators. In this paper, the instrumentation used and the strain measurements obtained during two start up operations are presented. The influence of the plant start up operation parameters on the lugs strain evolution is also analyzed. (author)

  17. Actinides inventory of the nuclear power plant of Laguna Verde Unit 1; Inventario de actinidos de la Central Nuclear Laguna Verde Unidad 1

    Energy Technology Data Exchange (ETDEWEB)

    Martinez C, E.; Ramirez S, J. R. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Alonso V, G., E-mail: eduardo.martinez@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U. P. Adolfo Lopez Mateos, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

    2013-10-15

    At the present time 435 nuclear power reactors exist for the electricity generation operating in the world and 63 in construction. Mexico has two reactors type BWR in the nuclear power plant of Laguna Verde. The nuclear fuel that is used in the nuclear reactors is retired of the reactor core when the energy that this contained has been extracted. This used fuel is known as spent nuclear fuel, the problem with this fuel is that was irradiated inside the reactor and continuous emitting a high radiation, as well as a significant heat quantity when being extracted, for what is necessary to maintain it in cooling and with some shielding to be protected of the radiation that emits. This objective is achieved confining the fuel in the spent nuclear fuel pool, where it is cooled and the same pool provides the necessary shielding to maintain the surroundings in safety radiation levels for the personnel that work in the power plant. An inconvenience of the pools is its limited storage capacity and that after certain time is necessary to remove the fuel, according to the established regulation to continue operating. To correct this inconvenience, two alternatives of spent fuel disposition exist, 1) the final disposition in deep geologic repositories and 2) the reprocessing and recycled of spent fuel. Each alternative presents its particularities and specific problems; however taking many years to be able to implement anyone of them. To carry out the second option, is indispensable to estimate the total mass of actinides generated in the spent nuclear fuel, that which represents to develop a methodology for it, this action is the main purpose of the present work. Inside our calculation method was necessary to appeal to diverse computation tools as the codes Origin-S and Keno V.a. Later on the obtained were compared with a problem type Benchmark, being obtained a smaller absolute error to 1.0%. (Author)

  18. A Validation Process for the Groundwater Flow and Transport Model of the Faultless Nuclear Test at Central Nevada Test Area

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed Hassan

    2003-01-01

    Many sites of groundwater contamination rely heavily on complex numerical models of flow and transport to develop closure plans. This has created a need for tools and approaches that can be used to build confidence in model predictions and make it apparent to regulators, policy makers, and the public that these models are sufficient for decision making. This confidence building is a long-term iterative process and it is this process that should be termed ''model validation.'' Model validation is a process not an end result. That is, the process of model validation cannot always assure acceptable prediction or quality of the model. Rather, it provides safeguard against faulty models or inadequately developed and tested models. Therefore, development of a systematic approach for evaluating and validating subsurface predictive models and guiding field activities for data collection and long-term monitoring is strongly needed. This report presents a review of model validation studies that pertain to groundwater flow and transport modeling. Definitions, literature debates, previously proposed validation strategies, and conferences and symposia that focused on subsurface model validation are reviewed and discussed. The review is general in nature, but the focus of the discussion is on site-specific, predictive groundwater models that are used for making decisions regarding remediation activities and site closure. An attempt is made to compile most of the published studies on groundwater model validation and assemble what has been proposed or used for validating subsurface models. The aim is to provide a reasonable starting point to aid the development of the validation plan for the groundwater flow and transport model of the Faultless nuclear test conducted at the Central Nevada Test Area (CNTA). The review of previous studies on model validation shows that there does not exist a set of specific procedures and tests that can be easily adapted and

  19. First Central and Eastern European Workshop on Quality control, patient dosimetry and radiation protection in diagnostic and interventional radiology and nuclear medicine

    International Nuclear Information System (INIS)

    First Central and Eastern European Workshop on Quality Control, Patient Dosimetry and Radiation Protection in Diagnostic and Interventional Radiology and Nuclear Medicine, scientifically supported and accredited as a CPD event for medical physicists by EFOMP, National 'Frederic Joliot-Curie' Research Institute for Radiobiology and Radiohygiene (NRIRR), Budapest, Hungary, April 25-28, 2007. Topics of the meeting included all areas of medical radiation physics except radiation therapy. A unique possibility was realized by inviting four European manufacturers of quality control instrumentation, not only for exhibiting but they also had 45 minutes individual presentations about each manufacturer's product scale and conception. Further sessions dealt with dosimetry, optimization, quality control and testing, radiation protection and standardization, computed tomography and nuclear medicine, in 29 oral presentations and 1 poster of the participants. (S.I.)

  20. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1991-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  1. Training-related activities for nuclear power plant personnel in the countries of Central and Eastern Europe and the former Soviet Union. Working material

    International Nuclear Information System (INIS)

    A Technical Cooperation Meeting on Training-Related Activities for NPP Personnel in the Countries of Central and Eastern Europe and the Former Soviet Union was held at the IAEA, Vienna. The main objective of the meeting was to identify, through information exchange and discussion, possible TC projects and assistance related to nuclear power plant (NPP) personnel training, which would meet overall coherent national goals and would demonstrate and important impact and relevance for national policy priorities. An array of such projects were identified for each participating country of the CEEC and FSU as were a number of regional cooperation projects. Refs, figs and tabs

  2. Notions and methodologies for uncertainty analysis in simulations of transitory events of a nuclear central; Nociones y metodologias para analisis de incertidumbre en simulaciones de eventos transitorios de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alva N, J. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Ingenieria Nuclear, Avenida IPN S/N Colonia Lindavista, 07738 Mexico D.F. (Mexico); Ortiz V, J.; Amador G, R.; Delfin L, A. [ININ, Carretera Mexico-Toluca SN La Marquesa, 52750 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: neriaesfm@gmail.com

    2007-07-01

    The present work has as objective to gather the basic notions related with the uncertainty analysis and some of the methodologies to be applied in the studies of transitory events analysis of a nuclear power station, in particular of those thermal hydraulics phenomena. The concepts and methodologies mentioned in this work are the result of an exhaustive bibliographical investigation of the topic in the nuclear area. The methodologies of uncertainties analysis have been developed by diverse institutions and they are broadly used at world level for their application in the results of the computer codes of the class of better estimation in the thermal hydraulics analysis and safety of plants and nuclear reactors. The main sources of uncertainty, types of uncertainty and aspects related with the models of better estimation and better estimation method are also presented. (Author)

  3. Permission of change of limits in the vapor generators of the Atucha I Nuclear Central; Permiso de cambio de limites en los GVs de la CNA-I

    Energy Technology Data Exchange (ETDEWEB)

    Ventura, M. [Autoridad Regulatoria Nuclear, Av. Libertador 8250 (1429), Capital Federal (Argentina)]. e-mail: mventura@sede.arn.gov.ar

    2006-07-01

    In the mark of the modification of the Atucha-I Nuclear Central Installation (CNA-I) as consequence of the Introduction of the System 'Second Drain of Heat' (SSC), the Entity Responsible for the CNA-I (NASA) requested authorization to the Nuclear Regulatory Authority (ARN) to modify the value of the minimum level of water in the secondary side in the Steam generators (GVs) to activate the signal 'shoot of the Cut of the Reactor' (RESA-LLV). As the level in the GVs is one of those parameters that are used to shoot the Emergency Feeding System (RX), component of the SSC System, also was analyzed the change in the activation of the shoot signal of the 'Second Drain of Heat' (2SSC-LLV). The ARN uses for the study of the nuclear safety of nuclear power plants, the series of prediction programs RELAP5/MOD3.X. It participates of the evaluation and maintenance activities of these codes through specific agreements with the U.S. Nuclear Regulatory Commission (US-NRC). It is necessary to account with programs of this type since the ARN it licenses the construction and operation of Nuclear Power Plants (NPPs) and other outstanding facilities and it inquires its operation according to its own standards. With these tools its are auditing the calculations that the Responsible Entities of the operation make to guarantee the operability of the NPPs assisting the mentioned standards. The analysis with computational codes is used as a tool to achieve the best understanding in the behavior of the plant in union with the engineering approach, the manual calculations, the data analysis and the experience in the operation of the machine. (Author)

  4. Nuclear Activities in Argentina. A short Review. Part 2

    International Nuclear Information System (INIS)

    The second part of this historical review covers the 'industrial' period of nuclear energy in Argentina. The National Atomic Energy Commission (CNEA), after a feasibility study carried out by argentine experts, in 1968 signed a contract to build a nuclear power plant. This PHWR plant, Atucha 1, of 310 MWe was inaugurated in 1973 and it is still operating. The same year the CNEA signed a new contract to build a CANDU type plant of 600 MWe, Embalse, that was finally inaugurated in 1983. The construction of a third plant, Atucha 2 of 745 MWe also a PHWR, was started in 1980 but was arrested in 1994, when more than 80% was completed, and it is still waiting a political decision to reach completion. Within the development of the nuclear power program, a fuel element production plant for the Argentine power reactors was built by the CNEA and a heavy water production plant of 250 tons/year was inaugurated in 1993 in the southern province of Neuquen. A pilot spent fuel reprocessing plant was designed but its construction was not completed. At the same time, a pilot gaseous diffusion plant was constructed in order to produce enriched uranium for research reactors. The activities in the field of radioisotope and radiation applications were also intensive, mainly in nuclear medicine and food preservation. A facility to fabricate sealed sources was built to process the Co 60 produced by the Embalse power plant. Argentina was active in the export of nuclear facilities: CNEA built a complete nuclear research center in Peru, and the Argentine company INVAP built research reactors in Algeria and Egypt. The same company is now building a research reactor in Australia. (author)

  5. Demand of natural uranium to satisfy the requirements of nuclear fuel of new nuclear power plants in Mexico; Demanda de uranio natural para satisfacer los requerimientos de combustible nuclear de nuevas centrales nucleares en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Rios, M. del C.; Alonso, G.; Palacios H, J. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: jrrs@nuclear.inin.mx

    2008-07-01

    Due to the expectation of that in Mexico new plants of nuclear energy could be installed, turns out from the interest to evaluate the uranium requirements to operate those plants and to also evaluate if the existing reserves in the country could be sufficient to satisfy that demand. Three different scenes from nuclear power plant expansion for the country are postulated here that are desirable for the diversification of generation technologies. The first scene considers a growth in the generation by nuclear means of two reactors of type ABWR that could enter operation by years 2015 and 2020, in the second considers the installation of four reactors but as of 2015 and new every 5 years, in the scene of high growth considers the installation of 6 reactors of the same type that in the other scenes, settling one every three years as of 2015. The results indicate that the uranium reserves could be sufficient to only maintain in operation to one of the reactors proposed by the time of their useful life. (Author)

  6. Modernization of the turbo in the Laguna Verde Nuclear Power Plant; Modernizacion del turbogrupo en la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Liebana, B.; Merino, A.; Cobos, A.; Gonzalez, J. J.

    2010-07-01

    The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This paper describes the first phase of the project.

  7. Fukushima, two years later, modification requirements in nuclear power plants; Fukushima, dos anos despues, requerimientos de modificacion en centrales nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, J.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Salmeron V, J. A., E-mail: jerson.sanchez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    The occurred events in the nuclear power plant of Fukushima Daiichi as consequence of the strong earthquake of 9 grades in the Richter scale and the later tsunami with waves estimated in more than 14 meters high began a series of important questions about the safety of the nuclear power plants in operation and of the new designs. Firstly, have allowed to be questioned on the magnitudes and consequences of the extreme external natural events; that can put in risk the integrity of the safety barriers of a nuclear power plant when being presented in a multiple way. As consequence of the events of the Fukushima Daiichi NPP, the countries with NPPs in operation and /or construction carried out evaluations about their safety operation. They have also realized evaluations about accidents and their impact in the safety, analysis and studies too that have forced to the regulatory bodies to continue a systematic and methodical revision of their procedures and regulations, to identify the possible improvements to the safety in response to the events happened in Japan; everything has taken it to determine the necessity to incorporate additional requirements to the nuclear power plants to mitigate events Beyond the Design Base. Due to Mexico has the nuclear power plant of Laguna Verde, with two units of BWR-5 type with contention Mark III, some the modifications can be applicable to these units to administrate and/or to mitigate the consequences of the possible occurrence of an accident Beyond the Design Base and that could generate a severe accident. In this work an exposition is presented on the modification requirements to confront external natural events Beyond the Design Base, and its application in our country. (Author)

  8. Evolución de las aportaciones en embalses de cabecera del Guadalquivir: relación con las tendencias climáticas recientes y repercusión en la planificación hidrológica

    OpenAIRE

    Aguilar Alba, Mónica; Moral Ituarte, Leandro del

    2008-01-01

    Existen crecientes evidencias sobre la disminución de las aportaciones a embalses en diferentes cuencas de la Península Ibérica. Este hecho viene intensificando los indicios de sobrevaloración de las disponibilidades de agua estimadas por la planificación hidrológica. La actual Instrucción de la P.H., mejorada en su versión final (10 de septiembre de 2008) respecto de los borradores anteriores, establece la necesidad de tomar en consideración este riesgo, ordenando manejar las series de aport...

  9. Energy situation in Latin America and nuclear power

    International Nuclear Information System (INIS)

    Greenhouse Gas emission levels. As an example, C02 emission levels in South America were dominated by a 38% increase in Brazil in the period of 1990-2003. Regarding Nuclear Power generation, at present, only Mexico (1.300 MWe), Brazil (1.900 MWe) and Argentina (950 MWe) have NPP's in operation, representing 5%, 3% and 8% of total electricity generation share respectively. Argentina has 1 reactor (750 MWe) under construction, while Brazil has 1 (1.200 MWe) planned. In the near future Argentina is planning to finish its Third Nuclear Power Plant Atucha 2 for 2010, to extend the life of the CANDU type Embalse NPP for another 20 years and start studies for a future fourth plant in 2015

  10. Prevalence of congenital malformations in the vicinity of nuclear plants: data from the Central-East France registry

    International Nuclear Information System (INIS)

    To study the prevalence of malformations around the nuclear power plants in the Rhone-Alps region and compare it with their distribution in other parts of the region monitored by the registry. Methods: Municipalities with fewer than 50,000 inhabitants surrounding the 5 nuclear plants in operation from 1979 through 2002 were studied. Every municipality situated near a nuclear site (n=121) was assigned an exposure index, which we estimated from the distance between the municipality and the plant. A Poisson model and a reference population, defined as the 2154 municipalities in the region situated farther than 10 km from a nuclear plant were used to calculate relative risks for congenital malformations, after adjustment for year of birth, maternal age, district of birth, population density, average family income, and presence of chemical plants subject to E U Seveso regulations. Results: Significant differences were not observed for either gene/chromosome anomalies (p=0.50) or minor malformations (p=0.14). Risks for overall malformations and those defined as major non-syndromic appear to be reduced in areas less than 5 km from nuclear plants (RR=0.75 and RR=0.71, respectively). The only comparison showing a higher rate of malformations in populations living near nuclear sites involved rural communities situated 5 to 10 km from a plant (RR=1.41 for the major non-syndromic malformations and 1.31 for all malformations). Conclusion: These results may be random or may be explained by exposure to the plants, but a more likely explanation is the existence of confounding factors for which we could not adjust, such as road traffic for urban communities and pesticides in rural ones. (author)

  11. Development of database for spent fuel and special waste from the Spanish nuclear power plants; Desarrollo de la base de datos para el combustible gastado y residuos especiales de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Gandal, R.; Rodriguez Gomez, M. A.; Serrano, G.; Lopez Alvarez, G.

    2013-07-01

    GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

  12. Advances in seismic safety of operating nuclear power plants: IAEA Project Results Seismic-EBP; Avances en la seguridad sismica de centrales nucleares en operacion: Resultados del proyecto OIEA Seismic-EBP

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez juan, A.; Sanchez Cabanero, J. G.; Moreno gonzalez, A.

    2010-07-01

    Records of strong earthquakes occurred in the proximity of facilities in operation have shown that there may be greater than the expected acceleration, the seismic danger that the light of the actual experience can exceed the design basis, and that the aging installations and modifications over its operating life significantly influence seismic response capacity. All this confirms that the earthquake is the external event with the greatest impact on the safety of nuclear installations and the largest contributor (even more than 70%) to the core damage frequency of central probabilistic safety analyzes.

  13. Advance: research project on aging electrical wiring in nuclear power plants; Advance: proyecto de investigacion de envejecimiento en cableado electrico en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cano, J. C.; Ruiz, S.

    2013-07-01

    As Nuclear Power Plants get older it is more important to know the real condition of low voltage, instrumentation, power and control cables. Additionally, as new plants are being built, the election of cables and the use of in-situ monitoring techniques to get reliable aging indicators, can be very useful during the plant life. The goal of this Project is to adapt, optimize and asses Condition Monitoring techniques for Nuclear Power Plants cables. These techniques, together with the appropriate acceptance criteria, would allow specialists to know the state of the cable over its entire length and estimate its residual life. In the Project, accelerated ageing is used in cables installed in European NPPs in order to evaluate different techniques to detect local and global ageing. Results are compared with accepted tests to validate its use for the estimation of cables residual life. This paper describes the main stages of the Project and some results. (Author)

  14. Gestión y análisis de riesgos aplicados al proyecto : "Remodelización del vial existente que une el municipio de Cañaveruelas (Cuenca) con el embalse de Buendía, mediante una vía de doble sentido tipo C-60 que incluye un carril bici y otro peatonal. Ordenación terrritorial en las proximidades del embalse.

    OpenAIRE

    Rodríguez Vilar, Marta

    2015-01-01

    El objetivo de este PFG es aplicar las herramientas de planificación a un proyecto existente y hacer un estudio del análisis de riesgos. El PFC al que se va a aplicar la gestión de riesgos es: “ Remodelación del vial existente que une el municipio de Cañaveruelas (Cuenca) con el embalse de Buendía, mediante una vía de doble sentido tipo C-60 que incluye un carril bici y otro peatonal. Ordenación territorial en las proximidades al embalse”. Fue realizado por Laura Gallego Salagre y po...

  15. Implementation of the monitoring Plan of the State and behavior of the systems in the Central Nuclear Almaraz; Implantacion del Plan de Seguimiento del Estado y Comportamiento de Sistemas en la Central Nuclear Almaraz

    Energy Technology Data Exchange (ETDEWEB)

    Montero Puertas, I.; Gonzalez Redondo, R.; Lopez Pozo, A.

    2013-07-01

    This work aims to present the implementation process of the Monitoring of the State and behavior of the systems in the Nuclear plan Almaraz. Will define the scope, process, frequencies and criteria of evaluation of the State and behavior of the systems included in the Plan of reliability, as well as the documentary requirements of this evaluation. Cases will also be collected practical real phenomena detected during monitoring degradation made and will explain the actions taken prior to the failure.

  16. Establishment and evolution of Radiological Environmental Monitoring Programmes in nuclear power plants; Establecimiento y evolucion de los programas de vigilancia radiologica ambiental en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Marugan, I.; Luque, S.; Martin, J. L.; Rey, C.; Salas, R.; Sterling, A.; Ramos, L. M.

    2013-09-01

    This article presents a brief overview of how the Radiological Environmental Monitoring Programmes carried out around nuclear power plants have evolved associated to different reasons as the legal framework, operational phases of the facilities, development on the detection and measurement of low levels of radiation due to the state of art and best available technologies, changes within sites as well as in their surroundings and accident taken place inside and outside of our borders. (Author)

  17. Cleaning chemical and mechanical of heat exchangers in french nuclear plants; Limpieza mecanica y quimica de intercambiadores de calor en centrales nucleares francesas

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, J. t.; Guerra, P.; Carreres, C.

    2013-03-01

    This project was carried out under the frame of the approval of LAINSA as a supplier of EDF in France. The inspection performed on systems called the moisture separator reheaters (GSS) of CPO series reactor of EDF nuclear power plants has shown evidence of significant clogging due to deposits of magnetite inside the tubes of tube bundle. The pressure drop between inlet and outlet of the heating was close to maximum design criterion. This effect could result in equipment damage and loss of plant productivity. The aim of the work was the design, development, approval and implementation of a procedure for un blocking the tubes of the GSS respecting the integrity of materials and ensuring the harmlessness of cleaning procedures. The procedure used was to completely remove magnetite deposits in order to recover a passage diameter and a surface finish equivalent to the origin, thus avoiding the replacement of the GSS and obtaining a considerable reduction of costs. The achieve these objectives we have developed a procedure that is basically a mechanical pre-cleaning of all tubes of the GSS in order to unblock tem, followed by a chemical cleaning where magnetite is dissolved and crawled out of the tube bundle. The main results were: -Corrosion less than 10 microns. 100-110 Kg of magnetite removed by heat exchanger. -Final pressure drop similar to that of new equipment. -Waste water: 70 m{sup 3} per exchanger, which were managed by an authorized waste management company. This procedure has been applied successfully in 14 GSS type heat exchangers in Fessenheim and Bugey nuclear power plants in France between 2009 and 2011. This project demonstrates that the long experience of LAINSA in the Spanish nuclear industry along with the knowledge and experience in chemical cleaning of SOLARCA, have served to successfully work demanding and mature markets such as the French nuclear market, solving the problem of deposits of magnetite with an effective and safe method for the treated

  18. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

  19. Management of fatigue in the Central Nuclear of Cofrentes - implementation of program for calculation of fatigue based on stress

    International Nuclear Information System (INIS)

    This article describes the main features that should have monitoring systems of fatigue to give solid response to requirements associated with long-term operation. The specific examples given throughout the article are drawn from the lessons learned during the implementation of Fat one system Cofrentes Nuclear Power. (Author)

  20. Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

    International Nuclear Information System (INIS)

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  1. Temporary storage in dry of the spent nuclear fuel in the Nuclear Power Plant of Laguna Verde; Almacenamiento temporal en seco del combustible nuclear gastado en la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A., E-mail: natividad.hernandez@cfe.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Carretera Veracruz-Medellin Km. 7.5, 94270 Dos Bocas, Veracruz (Mexico)

    2013-10-15

    To guarantee the continuity in the operation of the two nuclear reactors of the nuclear power plant of Laguna Verde (NPP-L V) is an activity of high priority of the Comision Federal de Electricidad (CFE) in Mexico. At the present time, the CFE is working in the storage project in dry of the spent fuel with the purpose of to liberate space of the pools and to have the enlarged capacity of storage of the spent fuel that is discharged of the reactors. This work presents the storage option in dry of the spent fuel, considering that the original capacity of the spent fuel pools of the NPP-L V was of 1242 spaces each one and that in 1991, through a modification of the original design, the storage capacity was increased to 3177 spaces by pool. At present, the cells occupied by unit are of 2165 (68%) for the Unit-I and 1839 (58%) for the Unit-2, however, in 2017 and 2022 the capacity to discharge the complete core will be limited by what is required of a retirement option of spent fuel assemblies to liberate spaces. (author)

  2. Iodine prophylaxis following nuclear accidents - a concept how to distribute potassium-iodide tablets out of the central stocks in the event of an accident

    International Nuclear Information System (INIS)

    With its recommendation ''Iodine prophylaxis following nuclear accidents'' (1996) and its reports of 1997 and 2001 the German Commission on Radiological Protection (SSK) followed the recommendations of the WHO ''Guidelines for iodine prophylaxis following nuclear accidents'' of 1989. The intervention levels were lowered (50 mSv for children/adolescents (up to the age of 18 years) and pregnant women, 250 mSv for adults), the iodine prophylaxis was restricted to persons up to the age of 45 years and the recommended dosage of stable iodine was changed. Due to the lowered reference levels the radius of 25 km around a nuclear power plant that had been the planning radius for the distribution of iodine tablets so far was extended to 100 km. Based on these recommendations the German authorities began to set up new strategies for the provision and distribution of potassium-iodide tablets (iodine tablets). Since 2004, within the radius of 25 km the iodine tablets are pre-distributed to households and/or stored at several points in the municipality for persons up to the age of 45 years. For the new planning radius of 25-100 km iodine tablets are stored in 8 central stocks in Germany for children/adolescents (up to the age of 18 years) and pregnant women. A working group with representatives from federal and Laender authorities has developed a distribution strategy for the distribution out of these central stocks in the event of an accident. It describes a possibility of organising and implementing the distribution of the iodine tablets within the radius of 25-100 km in a nationwide standardised way. (orig.)

  3. ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

    International Nuclear Information System (INIS)

    The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

  4. Complementary assessment of the safety of French nuclear power plants; Evaluations complementaires de surete des centrales nucleaires francaises

    Energy Technology Data Exchange (ETDEWEB)

    Camarcat, N.; Pouget-Abadie, X. [EDF - (France)

    2011-07-15

    As an immediate consequence of the Fukushima accident the French nuclear safety Authority (ASN) asked EDF to perform a complementary safety assessment for each nuclear power plant dealing with 3 points: 1) the consequences of exceptional natural disasters, 2) the consequences of total loss of electrical power, and 3) the management of emergency situations. The safety margin has to be assessed considering 3 main points: first a review of the conformity to the initial safety requirements, secondly the resistance to events overdoing what the facility was designed to stand for, and the feasibility of any modification susceptible to improve the safety of the facility. This article details the specifications of such assessment, the methodology followed by EDF, the task organization and the time schedule. (A.C.)

  5. Modular plant of electro chlorination of seawater for nuclear power plants; Planta modular de electrocloracion de agua de mar para centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Dumas, H.; Sesma, J. L.

    2015-07-01

    Iberdola Engineering and Construction has supplied the seawater electro chlorination plant for the EPR of Flamanville 3. The plant produces sodium hypochlorite from the electrolysis of the seawater and injects it continuously to protect the cooling circuits against the marine flora and fauna. As a consequence of the problems faced during the erection of the plant, Iberdola Engineering and construction develops an innovation project to design a modular electro chlorination system for Nuclear Power Plants. The result is a competitive product that reduces significantly the installation costs and the delivery data. (Author)

  6. What they have in common the engineering from the Spanish nuclear power plants?; Que tienen en comun las ingenierias de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Mendez, M.

    2012-11-01

    In recent years, Spain Nuclear Power Plant Engineering have switched their project/task management method to Critical Chain multi-project management, developed by Dr. Goldratt, achieving outstanding results in improving quality and productivity. Multitasking reduction, task and resource synchronizing without the need of exact schedules, implementing a real-time priority information system, relying on the software Concerto, and daily decision making are the basis for the management change that has generated productivity increases of between 20% to 50%, opening new horizons for improvement in other scenarios such as optimizing refueling shutdowns. (Author)

  7. Modernization of electric power systems of the Laguna Verde Nuclear Power Plant; Modernizacion de los sistemas electricos de potencia de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Gabaldon, M. A.; Gonzalez, J. J.; Prieto, I.

    2011-07-01

    The Power Increase Project of Laguna Verde Nuclear Plant has entailed the replacement, in one unique outage, of the main power electrical systems of the Plant (Isolated Phase Bars, Generator Circuit Breaker and Main Transformer) as well as the replacement of the Turbo-group. The simultaneous substitution of these entire system has never been done by any other Plant in the world, representing an engineering challenge that embraced the design of the new equipment up to the planning, coordination and management of the construction and commissioning works, which were successfully carried out by Iberdrola within the established outage period /47 days) for both units. (Author)

  8. Self-Reliance and Sustainability of Nuclear Analytical Laboratories in Small States of Central Europe: The Slovenian Case

    International Nuclear Information System (INIS)

    The Jožef Stefan Institute is the largest research institution in Slovenia devoted to research in many fields of science and technology. Within the Institute several nuclear analytical laboratories operate, making it the largest nuclear research institution in Slovenia. The Laboratory for Radiation Measuring Systems and Radioactivity Measurements belongs to the Department for Medium and Low Energy Physics, which is engaged mainly in nuclear physics, interactions of radiation with matter and its applications, and in providing a service in radiation measurements and dosimetry. The laboratory was founded almost thirty years ago, when the three accelerators, which formed the basis of the research infrastructure of the department, came to the end of their working lives. The personnel took the opportunity to participate in the programme of radioactivity monitoring of the Krško Nuclear Power Plant, which at that time went into operation. The equipment, i.e., the detectors, electronics and computers, was available, but the expertise was limited to the techniques of measurement and analysis in gamma-ray spectrometry. The absence of the expertise in radiochemistry was a serious drawback, therefore new methods in detector calibration had to be developed. In the following years the laboratory participated not only in the monitoring programme of the nuclear power plant but also in other radioactivity monitoring programmes in Slovenia. Since its foundation the laboratory did not receive any financial support either from the state or from the department. Support in equipment and expertise was received from the International Atomic Energy Agency, the Government of the United States and the United Nations Development Programme. The laboratory is engaged mainly in gamma-ray spectrometric measurements of samples from the natural, living and working environments. The main customers are the Krško Nuclear Power Plant and governmental organizations and agencies. The work for these

  9. Regulatory challenges in the management of aging of structural materials in nuclear power plants; Retos reguladores en la gestion del envejecimiento de los materiales estructurales de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Castelo, C.; Mendoza, C.; Mas, E.; Conde, J. M.

    2013-07-01

    The article discusses two major pathways by which a regulatory body, and in particular the CSN, may participate in the acquisition of the necessary knowledge on mechanisms of aging of nuclear structural materials: to participate in forums to share operational experience and R and R project, both nationally and internationally. It notes the importance of this participation to carry out its regulatory function based on the knowledge acquired and the unique challenge of transferring that knowledge to rules and guidelines for their application. The article discusses various R and D projects in which the CSN participates directly. It calls for the presence of regulatory bodies in R and D project funded by the EU and the transfer of the results of such projects to codes, standards or guidelines for feasible implementation. (Author)

  10. Genetic structure based on nuclear and chloroplast microsatellite loci of Solanum lycocarpum A. St. Hil. (Solanaceae) in Central Brazil.

    Science.gov (United States)

    Martins, K; Chaves, L J; Vencovsky, R; Kageyama, P Y

    2011-01-01

    Solanum lycocarpum (Solanaceae) is a woody species found in the Brazilian Cerrado. The flowers are pollinated by Xylocopa spp bees, and seeds are dispersed by mammals with distinct home range sizes. As a consequence, relative contributions of pollen and seeds to overall gene flow can vary according to different spatial scales. We studied the genetic structure of four natural populations of S. lycocarpum separated by 19 to 128 km, including individuals located along dirt roads that interlink three of the populations. A total of 294 individuals were genotyped with five nuclear and six chloroplast microsatellite markers. Significant spatial genetic structure was found in the total set of individuals; the Sp statistic was 0.0086. Population differentiation based on the six chloroplast microsatellite markers (θ(pC) = 0.042) was small and similar to that based on the five nuclear microsatellite markers (θ(p) = 0.054). For this set of populations, pollen and seed flow did not differ significantly from one another (pollen-to-seed flow ratio = 1.22). Capability for long distance seed dispersion and colonization of anthropogenic sites contributes to the ability of S. lycocarpum to maintain genetic diversity. Seed dispersion along dirt roads may be critical in preserving S. lycocarpum genetic diversity in fragmented landscapes. PMID:21523656

  11. Spag16, an axonemal central apparatus gene, encodes a male germ cell nuclear speckle protein that regulates SPAG16 mRNA expression.

    Directory of Open Access Journals (Sweden)

    David R Nagarkatti-Gude

    Full Text Available Spag16 is the murine orthologue of Chlamydomonas reinhardtii PF20, a protein known to be essential to the structure and function of the "9+2" axoneme. In Chlamydomonas, the PF20 gene encodes a single protein present in the central pair of the axoneme. Loss of PF20 prevents central pair assembly/integrity and results in flagellar paralysis. Here we demonstrate that the murine Spag16 gene encodes two proteins: 71 kDa SPAG16L, which is found in all murine cells with motile cilia or flagella, and 35 kDa SPAG16S, representing the C terminus of SPAG16L, which is expressed only in male germ cells, and is predominantly found in specific regions within the nucleus that also contain SC35, a known marker of nuclear speckles enriched in pre-mRNA splicing factors. SPAG16S expression precedes expression of SPAG16L. Mice homozygous for a knockout of SPAG16L alone are infertile, but show no abnormalities in spermatogenesis. Mice chimeric for a mutation deleting the transcripts for both SPAG16L and SPAG16S have a profound defect in spermatogenesis. We show here that transduction of SPAG16S into cultured dispersed mouse male germ cells and BEAS-2B human bronchial epithelial cells increases SPAG16L expression, but has no effect on the expression of several other axoneme components. We also demonstrate that the Spag16L promoter shows increased activity in the presence of SPAG16S. The distinct nuclear localization of SPAG16S and its ability to modulate Spag16L mRNA expression suggest that SPAG16S plays an important role in the gene expression machinery of male germ cells. This is a unique example of a highly conserved axonemal protein gene that encodes two protein products with different functions.

  12. Microstructure of red clay from the central Pacific deep-sea basin: Significance to subseabed nuclear waste disposal

    International Nuclear Information System (INIS)

    The microstructure of deep-sea illitic red clay from the central Pacific Basin was investigated using transmission and scanning electron microscopy techniques. Gravity core samples (''undisturbed'') and sediments from dredge hauls (''disturbed'') were used in the investigations and analysis. Dredged samples were remolded and reconsolidated to equivalent in situ porosities by geotechnical engineers. To a first approximation, no significant difference in the fabric was observed between the undisturbed and remolded illitic sediment. Samples adjacent to the heater probe were subjected to temperatures slightly below 3000C. Slight preferential clay particle alignment probably resulting from shearing stresses developed in the sediment during probe insertion. Heating of the sediment did not appear to have a significant effect on the fabric, with the exception of localized ''quasi-expansion'' and flow features observed in the microfabric in the near field. 34 refs., 28 figs

  13. Communication dated 11 September 2006 from the Permanent Mission of the Republic of Kazakhstan regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006

    International Nuclear Information System (INIS)

    The Secretariat has received a Note Verbale, dated 11 September 2006, from the Permanent Mission of the Republic of Kazakhstan to the IAEA regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006 in Semipalatinsk by the leaders of Kazakhstan, Kyrgyzstan, Tajikistan, Turkmenistan and Uzbekistan. The Note Verbale and, as requested therein, the enclosed information regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia, is reproduced herewith for the information of Member States

  14. Central Indicent Reporting and Evaluation Office of VGB evaluation of special incidents in nuclear power plants; Auswertung besonderer Vorkommnisse in Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, J.; Grundhoefer, M.; Vallana, G. [VGB Technische Vereinigung der Grosskraftwerksbetreiber e.V., Essen (Germany)

    2000-07-01

    The Central Incident Reporting and Evaluation Office (ZMA) has been founded upon recommendation of the plant managers of German nuclear power plants in 1984 to serve as a central point of information flows at VGB. Since then all incidents have been reported to ZMA that are safety-relevant, have an important bearing on the availability or are of public interest. These incidents are stored in a data base and made available to all member companies for their exchange of experience. Measures taken lead to continual improvements of the plant safety and availability. (orig.) [German] Die 'Zentrale Melde- und Auswertestelle' (ZMA) wurde auf Empfehlung der Betriebsleiter der deutschen Kernrkaftwerke im Jahre 1984 als Drehscheibe der Informationsfluesse bei der VGB eingerichtet. Seitdem werden von den Mitgliedsunternehmen alle Vorkommnisse an die ZMA gemeldet, die sicherheitstechnisch relevant, fuer die Verfuegbarkeit wesentlich oder von oeffentlichem Interesse sind. Diese Vorkommnismeldungen werden in einer Datenbank gespeichert und allen Mitgliedsunternehmen zwecks Erfahrungsaustausch zur Verfuegung gestellt. Die durchgefuehrten Massnahmen fuehren zu kontinuierlichen Verbesserungen der Anlagensicherheit und Verfuegbarkeit. (orig.)

  15. Nuclear power plant of Fessenheim: evaluation of the seismic risk; Centrale Nucleaire de Fessenheim: appreciation du risque sismique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The seismic risk taken into account during the sizing of the nuclear power plant of Fessenheim seems to have been under evaluated at this time. The revaluation of the seismic risk, as proposed, until this day by EDF in order to the third ten-year visit of the power plant, planned for 2009, leads to a significant under evaluation of the risk and then is not acceptable. The present expertise details point by point the weaknesses of these revaluation. The power plant has been sized in an elastic manner that is generally strongly for the safety side. It is imperative to proceed the most quickly as possible to a deep control of the seismic resistance of the power plant of Fessenheim and then after having proceeded to a revision of the seismic risk in taking into account the actual knowledge in this field. (N.C.)

  16. Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central

    International Nuclear Information System (INIS)

    The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

  17. Direct observation of 134Cs and 137Cs in surface seawater in the western and central North Pacific after the Fukushima Dai-ichi nuclear power plant accident

    Directory of Open Access Journals (Sweden)

    H. Kaeriyama

    2013-06-01

    Full Text Available The horizontal distribution of radioactive cesium (Cs derived from the Fukushima Dai-ichi nuclear power plant (FNPP in the North Pacific is still unclear due to the limitation of direct measurement of the seawater in the open ocean. We present the result of direct observation of radioactive Cs in surface seawater collected from a broad area in the western and central North Pacific in July 2011, October 2011 and July 2012. We also conducted a simple particle tracking experiment to estimate the qualitative spatial distribution of radioactive Cs in the North Pacific. 134Cs was detected at 94 stations out of 123 stations, and 137Cs was detected at all stations. High 134Cs and 137Cs concentrations more than 10 m Bq kg−1 were observed in the area of the northern part of Kuroshio Extension at 144° E and 155° E in July 2011, in the area 147–175° E around 40° N in October 2011, and the northern part of Kuroshio Extension at 155° E and 175°30´ E in July 2012. Combining the result of direct observations and particle tracking experiment, the radioactive Cs derived from the FNPP had been dispersed eastward to the central North Pacific during 2011. It was considered from the horizontal distribution that radioactive Cs was dispersed not only eastward but also north- and southward in the central North Pacific. Pronounced dilution process of radioactive Cs from the FNPP during study period is suggested from temporal change in the activity ratio of 134Cs / 137Cs, which was decay-corrected on 6 April 2011, and relationships between radioactive Cs and temperature.

  18. Environmental Decrease of 137Cs-Activity Concentration in Milk in Central Europe After a Nuclear Fallout - A Comparison

    International Nuclear Information System (INIS)

    Full text: After a major contamination of a territory due to fallout from a reactor accident, a reprocessing plant accident or a weapon's detonation, one of the important questions to be addressed is the period required for the countermeasures to be applied. This is particularly important for countermeasures with high costs and consequences to the involved population such as relocation or a prohibition to consume local foodstuff. In that respect, the time required for a contamination with long-lived fission products to decrease below established intervention levels by natural processes of decay and removal from the soil layer is relevant. Therefore, the decrease in activity concentration in milk and other foodstuffs is investigated in several central-European countries and compared to each other. The decrease of activity concentration in the most important foodstuff is very similar in all these countries indicating that this decrease by natural effects is a universal effect typical for agricultural soils. Typically, in the first three years an effective half-life for 137Cs of 1 y, in the following years one of 5 y is observed. Including the first-to-second year decrease this results in a rapid decrease by about three orders of magnitude within a decade after fallout. Implications to long-term counter measures are discussed. (author)

  19. Confronting fluctuations of conserved charges in central nuclear collisions at the LHC with predictions from Lattice QCD

    CERN Document Server

    Braun-Munzinger, P; Redlich, K; Stachel, J

    2016-01-01

    We construct net baryon number and strangeness susceptibilities as well as correlations between electric charge, strangeness and baryon number from experimental data on the particle production yields at midrapidity of the ALICE Collaboration at CERN. The data were taken in central Pb-Pb collisions at $\\sqrt{s_{\\rm NN}}$~=~2.76~TeV and cover one unit of rapidity. We show that the resulting fluctuations and correlations are consistent with Lattice QCD results at the chiral crossover pseudocritical temperature $T_{c} \\simeq$ 155 MeV. This agreement lends strong support to the assumption that the fireball created in these collisions is of thermal origin and exhibits characteristic properties expected in QCD at the transition from the quark gluon plasma to the hadronic phase. Since Lattice QCD calculations are performed at a baryochemical potential of $\\mu_{B}$ = 0, the comparisons with LHC data are the most direct due to the vanishing baryon transport to midrapidity at these high energies.

  20. 30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

    Energy Technology Data Exchange (ETDEWEB)

    Guevara, S; Moreno Casasola, P; Castillo Campos, G; Dorantes, C; Gonzalez Garcia, F; Halffter, G; Isunza, E; Lot H, A; Mendoza, R; Paradowska, K; Priego, A; Sanchez Vigil, C; Vazquez, G [Comision Federal de Electricidad and Instituto Nacional de Ecologia A.C. (Mexico)

    2008-07-01

    results of the environmental measurements also demonstrate that the nuclear option of electrical energy generation, when it is operated with safety and efficiency, is one of the friendlier forms with the environment of power generation. [Spanish] Hace 36 anos nacio uno de los proyectos energeticos mas importantes de Mexico; el diseno y construccion de la Central Nuclear Laguna Verde. Este proyecto se volvio realidad gracias al compromiso de un grupo de profesionistas mexicanos que dieron lo mejor de ellos para su realizacion. En Mexico no existia en ese momento una legislacion que contemplara la proteccion del medio ambiente; sin embargo, la Constitucion preve que cuando en el pais no exista legislacion para el desarrollo de un proyecto. Este debe adoptar la legislacion del pais que lo esta vendiendo. En el caso especifico de Laguna Verde, se adopto la legislacion de los Estados Unidos de America y en la parte ambiental se tuvo que realizar el primer Manifiesto de Impacto Ambiental, que se titulo Informe ambiental para la construccion de la Central Nuclear Laguna Verde en el Estado de Veracruz. Este estudio lo realizaron varias instituciones tanto nacionales como extranjeras. Entre las mas sobresalientes se cuenta con: la Universidad Nacional autonoma de Mexico, el Instituto Politecnico Nacional, la Universidad Veracruzana, el Instituto Nacional para la Investigacion de los Recursos Biologicos, el Instituto de Ecologia, A.C. Con este informe, los ingenieros se dieron a la tarea de disenar y construir, los biologos y ecologos a realizar los estudios para mitigar los efectos causados al medio ambiente durante la construccion y, posteriormente, durante la operacion de la Central Nuclear. Despues de 18 anos de operacion comercial de la central se concluye el presente libro, en el cual se comparan los resultados obtenidos en 1972, cuando se iniciaron los estudios para el informe ambiental, contra los obtenidos a lo largo de este periodo. Es importante ver en los resultados de

  1. RÉGIMEN ALIMENTARIO DE SIETE ESPECIES ÍCTICAS EN EL EMBALSE DE LA HIDROELÉCTRICA URRÁ (CÓRDOBA, COLOMBIA

    Directory of Open Access Journals (Sweden)

    V.J. Atencio-García

    2005-12-01

    Full Text Available El objeto del estudio fue evaluar el régimen alimentario de siete especies de peces que se han establecidoen el embalse de la Hidroeléctrica Urrá (HU. Se analizaron 453 estómagos, distribuidos así: 115 deperico (Tracheolypterus badeli cf, 111 de cacucho (Panaque gibbosus, 108 de yalúa (Cyphocharaxmagdalenae, 89 de mojarra amarilla (Caquetaia kraussii , 11 de moncholo (Hoplias malabaricus, 10 debarbul ( Pimelodus clarias y 9 de doncella ( Ageneoisus pardales . Los contenidos estomacales se evaluaronmediante frecuencia de ocurrencia (FO, frecuencia numérica (FN y el método gravimétrico (G. Sedeterminó la importancia de cada presa mediante el índice de categorización de presa (ICP y lasuperposición de dietas se analizó mediante el Índice de Morosita (IM. La distribución porcentual de loscontenidos estomacales de la yalúa mostró que el 95.5% correspondió al ítem detritus y el restante 4.5%a microlagas (Clorofitas y Bacillariofitas y protozoarios/rotíferos. La dieta del cacucho la conformaron enun 70.9% microalgas (Cianofitas, Clorofitas y Bacilariofitas y protozoarios/rotíferos y el restante 29.1%correspondieron al ítem detritus. Barbul (FO = 50%, FN = 46.2% y perico se alimentaron principalmentede insectos (FO = 73.9%, FN = 86.4%. La mojarra amarilla (FO = 87.1%, FN = 83.3%, doncella(FO = 92.3%, FN = 92.0% y moncholo (FO = 90.9%, FN = 90.9% prefieren peces como cachanita(Roeboides dayi y sardinas ( Astianax sp. Los resultados sugieren que yalúa es detritívoro iliófago, cacuchoes detritívoro, perico y barbul son carnívoros insectívoros y doncella, moncholo y mojarra amarilla soncarnívoros piscívoros.

  2. Radiological impact of the management of radioactive waste arising from the Argentine Nuclear Programme

    International Nuclear Information System (INIS)

    The Argentine nuclear programme, as it stands at present, provides for the construction of four nuclear power plants in addition to those of Atucha I and Embalse and for the establishment of such fuel cycle facilities as are required to supply all of these plants. This paper evaluates the radiological impact (collective dose commitment) expected from the management of the radioactive wastes arising in the facilities mentioned above throughout the useful life of the reactors. The maximum individual doses to be expected as a result of the planned high-level-waste repository are also estimated. The evaluations presented are partly specific to the sites under consideration, but they also include estimates of the total collective dose commitments resulting from the management of radioactive waste under the Argentine nuclear programme. (author)

  3. CNE (Embalse nuclear power plant): Probabilistic safety study. Loss of steam generators as heat sink. Probabilistic evaluation and analysis through events sequence

    International Nuclear Information System (INIS)

    The aim of this paper is to analyze and evaluate from a probabilistic point of view the consequences of a set of failure modes that can produce the loss of steam generators as heat sink. This work is part of a probabilistic study about the incidence of the secondary system on the power plant safety. The failure modes or starting events that are of interest in this study were previously identified. When the reactor is operating at full power, they are: a) guillotine type rupture in drainage lines of steam generators; b) severe rupture in downstream supply lines of regulating stations; c) loss of main feeding flow associated with start up failure of auxiliary feeding system. The annual rate of occurrence of those failure modes is determined on the basis of the statistical values obtained from different sources of reliability data, using when necessary the failure-tree technique. The initial plant response, as well as the operator actions tending to create an alternative heat sink are analyzed through events sequence. It is concluded that the secondary system can seriously threaten the plant safety in two situations: loss of main feeding associated with failure of systems that reduce the reactor power and breakage of draining lines associated with omission failure of operator. (Author)

  4. Humid scraping method to obtain samples for the analysis of D2 incorporated in the pressure tubes of Embalse Nuclear Power Plant

    International Nuclear Information System (INIS)

    From ten fuel channels of the CNE reactor four samples of each channel were taken by means of the Humid Scraping method in order to evaluate the equivalent hydrogen content by incorporating deuterium in the pressure tubes. With these data, it is possible to make a list of priorities of channels for future replacement of spacer rings between pressure and calandria tubes, using Slarette equipment. (author)

  5. Changes of the more relevant PHTS parameters after the cleaning of the steam generators primary side at Embalse nuclear power plant

    International Nuclear Information System (INIS)

    During the operation of the plant magnetite deposition occurs at the inner walls of Primary Heat Transport System (PHTS). This deposition is particularly significant at the U-tubes of steam generators. The consequence of this is the deterioration of heat transfer to the Secondary System. In order to minimize this impact, during the annual outage of 2000, the steam generators primary side cleaning by the SIVABLAST technique was carried out. This technique consists in blasting the inner walls with tiny stainless steel balls propelled by air at high pressure. This paper presents the change of the more relevant parameters of PHTS after that cleaning. The parameters analyzed and the main results are the following: 1) Inlet header temperature dropped 4.7 C degrees at full power; 2) Exit quality at the outlet headers decreased from 3,5% to 1,5%; 3) Global PHTS flow in single phase evaluated from: a) In-site instrumentation increased 4,6%; b) Thermalhydraulic code NUCIRC 1.0 increased 3,2%; c) measured flows at the instrumented fuel channels increased 4.4%. (author)

  6. Multielemental analysis of soil samples from the Assin District of Central Region in Ghana using nuclear and related techniques

    International Nuclear Information System (INIS)

    Macronutrients, micronutrients, pH, salinity and moisture content were determined in soil samples from six farms in two farming towns in Assin North District in the Central Region of Ghana namely Assin Akonfudi and Assin Bereku. Soil samples were taken from cocoa farms, orange farms and palm oil plantations at three different depths. The nutrients determined were Primary macronutrients that was K, Secondary macronutrients that were Ca, Mg and Micronutrients that were, Cl, Co, Cu, Fe, Mn, Mo, Zn, Na and Se and Neutron Activation method and Atomic Absorption Spectrometry were used for the elemental analysis. The pHs were within the acidic range, ranging from 4.50-6.44. The top soil (0-5cm) had the higher pH followed by soil at the depth of 5-30cm and then soil at the depth of 30-40cm that is the pH decreased with depth. The salinity rather increased with depth ranging from 0.3l-2.98dS/m and the moisture content also ranged from 0.5-2.04%. For the soil samples taken from the cocoa farms, K recorded the highest concentration and Mo recorded the lowest concentration in the soil. For soil samples taken from orange farms, Ca recorded the highest concentration and Se recorded the lowest concentration in the soil and for soil samples taken from the palm oil plantations, Fe recorded the highest concentration and Mo recorded the lowest concentration in soil. The macronutrients ranged from 28591.19-6.49 mg/kg and the micronutrients ranged from <0.0004-20344.50 mg/kg. Soils in the cocoa farms were found to be more rich in nutrients and the soils in the palm oil plantations were found to be least rich in nutrients

  7. Improvements to the wastewater treatment from the beginning of the operation of Nuclear Asco; Mejoras en la depuracion de aguas residuales desde el inicio de la explotacion de la Central Nuclear de Asco

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin, J. L.; Boronat Medico, M.

    2014-07-01

    Sanitary sewage in the Central Nuclear de Asco (CNA), are subject to a series of physico-chemical and biological processes in the wastewater waste (WWTP) before being discharged to the River Ebro. Since the beginning of the exploitation of CNA, the number of workers and administrative restrictions have evolved so that they have forced the execution of modifications of lowest and highest wingspan to comply with applicable legal requirements in the field of discharges. The overall objective of this work is to present the different stages of evolution of the WWTP of CNA from the start of operation of the plant up to the present day. The specific objective is to show the latest enhancements implanted in the sewage treatment plant and the benefits obtained. With technical improvements carried out in the WWTP of CNA, fixed the problem of disposal coming from the central nitrogen, one of the key problems and reason of failure to comply with the parameters imposed by the administration. (Author)

  8. Assistance in chemistry and chemical processes related to primary, secondary and ancillary systems of nuclear power plants

    International Nuclear Information System (INIS)

    Argentina is currently running two nuclear power plants: Atucha I (CNA I) and Embalse (CNE) operated by Nucleoelectrica Argentina (NASA) whereas the National Atomic Energy Commission (CNEA), among other activities, is responsible for research and development in the nuclear field, operates research reactors and carries out projects related to them. In particular, the Reactor Chemistry Section personnel (currently part of the Chemistry Dept.) has been working on the field of reactor water chemistry for more than 25 years, on research and support to the NPPs chemistry department. Though the most relevant tasks have been connected to primary and secondary circuits chemistry, ancillary systems show along the time unexpected problems or feasible improvements originated in the undergoing operating time as well as in phenomena not foreseen by the constructors. In the present paper are presented the tasks performed in relation to the following systems of Embalse NPP: 1) Heavy water upgrade column preliminary water treatment; 2) Liquid waste system preliminary water treatment; and 3) Primary heat transport system coolant crud composition. (author)

  9. Communication dated 30 May 2014 received from the Permanent Mission of Uzbekistan to the Agency regarding the implementation of the initiative of the President of Uzbekistan on Establishing a Nuclear-Weapon-Free Zone in Central Asia

    International Nuclear Information System (INIS)

    The Director General has received a note verbale dated 30 May 2014 from the Permanent Mission of Uzbekistan to the Agency regarding the implementation of the initiative of the President of Uzbekistan, HE Mr Islam Karimov, on Establishing a Nuclear-Weapon-Free Zone in Central Asia. The note verbale and its attachment are circulated herewith for information, as requested by the Permanent Mission

  10. Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at root s(NN)=2.76 TeV

    Czech Academy of Sciences Publication Activity Database

    Adam, J.; Adamová, Dagmar; Bielčík, J.; Bielčíková, Jana; Brož, M.; Čepila, J.; Contreras, J. G.; Eyyubova, G.; Ferencei, Jozef; Křelina, M.; Křížek, Filip; Kučera, Vít; Kushpil, Svetlana; Mareš, Jiří A.; Petráček, V.; Pospíšil, Jan; Schulc, M.; Špaček, M.; Šumbera, Michal; Vajzer, Michal; Vaňát, Tomáš; Závada, Petr

    2016-01-01

    Roč. 93, č. 3 (2016), s. 034913. ISSN 0556-2813 R&D Projects: GA MŠk(CZ) LG13031 Institutional support: RVO:68378271 ; RVO:61389005 Keywords : ALICE collaboration * heavy ion collisions * centrality dependece Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders; BF - Elementary Particles and High Energy Physics (FZU-D) Impact factor: 3.733, year: 2014

  11. International Remote Monitoring Project Argentina nuclear power station remote monitoring system

    International Nuclear Information System (INIS)

    A remote monitoring system, designed to monitor spent fuel transfers from wet to dry storage, was installed at the Embalse Nuclear Power Station at Embalse, Argentina. The system consists of 6 gamma and one neutron radiation sensors. Five gamma sensors utilize RF transmission to communicate with Echelon nodes connected to a Local Operating Network (LON). One gamma and one neutron sensor are hardwired to the LON network. Each sensor Echelon node is bound to a single Datalogger that stores data until it receives an acquisition command to download to the Data Acquisition Software (DASW) database. The data from the Datalogger are transferred and stored in the Data Acquisition Software database, which resides on the IAEA MOS-MUX server. At a pre-determined interval, data from the DASW database are converted into Excel files and transferred to the IAEA database every 24 hours. At an predetermined interval all data are transferred to the distribution server located at the ARN laboratory at Ezeiza, Argentina. Remote access to data from the distribution server will be made from IAEA headquarters, Vienna, Austria, from ABACC in Rio de Janeiro, Brazil, from the IAEA field office in Buenos Aires, from ARN, and from Sandia National Laboratories, Albuquerque, New Mexico

  12. Variación espacio-temporal del nitrógeno y fósforo en el embalse del Neusa

    Directory of Open Access Journals (Sweden)

    Guillot Monroy Gabriel

    2003-06-01

    Full Text Available El Embalse del Neusa es un cuerpo de agua oligo-mesotrófico ubicado en la cordillera oriental de los Andes colombianos, utilizado en la regulación de caudales del río Neusa y en la distribución de agua para consumo. Allí se analizaron la variación espacial del nitrógeno y el fósforo y sus tasas de sedimentación, se indagó sobre su relación con la distribución de Egeria densa en el embalse. Para hacer una aproximación a la incidencia de las comunidades litorales sobre la variación del nitrógeno y fósforo se hicieron estimaciones de los porcentajes de nitrógeno y fósforo contenidos tanto en la biomasa como en la necromasa macrofíticas y se estudió su variación en el tiempo durante los procesos de descomposición in situ. En este trabajo se encontró que las diferencias temporales y espaciales en los contenidos de nitrógeno y fósforo en la columna de agua

  13. Contaminación por metales pesados en el embalse del Muña y su relación con los niveles en sangre de plomo, mercurio y cadmio y alteraciones de salud en los habitantes del municipio de Sibaté (Cundinamarca) 2007 / Heavy metals pollution of Muña Reservoir and its relation between blood levels of cadmium, lead and mercury, and health effects of Sibaté town (Cundinamarca) 2007

    OpenAIRE

    Combariza Bayona, David Andrés

    2009-01-01

    La cercanía del embalse del Muña con el municipio de Sibaté ha generado en sus habitantes diversas inquietudes sobre el impacto que puede estar originando sobre su salud, la exposición indirecta a los diferentes agentes contaminantes contenidos en el cuerpo de agua, el contacto con los plaguicidas utilizados para el control de los zancudos y del Jacinto de agua (buchón) y las emanaciones provenientes del embalse. Para tener un panorama más claro acerca de esta situación, en el año 2007 el Min...

  14. Caracterización citomorfomérica de Anabaena circinalis (Cyanophyta en una proliferación masiva en el embalse Paso de Las Piedras (Provincia de Buenos Aires, Argentina Cytomorphometric characterization of Anabaena circinalis (Cyanophyta from a bloom in the lake Embalse Paso de las Piedras (Buenos Aires Province, Argentina

    Directory of Open Access Journals (Sweden)

    Gimena Argañaraz Bonini

    2005-07-01

    Full Text Available El objetivo principal de este trabajo fue realizar un tratamiento estadístico de los caracteres morfológicos de los individuos de Anabaena circinalis presentes en una proliferación masiva del Embalse Paso de las Piedras (Buenos Aires, Argentina cuya identidad se determinó mediante técnicas moleculares. Se plantearon como objetivos específicos de este trabajo: 1 analizar las dimensiones celulares y parámetros estadísticos de centralización y dispersión; 2 analizar la posición relativa de los heterocistos y las acinetas en el tricoma; 3 analizar la composición porcentual de los distintos tipos de células del tricoma; 4 analizar relación entre valores promedio del ancho y largo celular; y 5 analizar la variación del largo celular en células vegetativas de diferentes tricomas. Los resultados obtenidos sugieren que en condiciones eutróficas: 1 es posible caracterizar a los individuos de Anabaena circinalis mediante parámetros estadísticos referidos a las medidas de las células vegetativas de los tricomas, 2 el criterio basado en los caracteres morfológicos de las acinetas inmaduras no debe ser utilizado para ese fin, dadas la no-maduración de las acinetas en condiciones eutróficas y la tendencia a la uniformidad morfométrica entre las células vegetativas y las acinetas inmaduras, y 3 los heterocistos y las células vegetativas, uniformemente esféricos, sólo pueden diferenciarse entre sí por su tamaño y no por su forma, mientras que ambos a su vez pueden diferenciarse de las acinetas ovoidales por su forma. En cuanto al análisis de la varianza del largo de las células vegetativas, los resultados obtenidos confirman que todos los tricomas pertenecen a una misma especie.The principal goal of the work was to make a statistical analysis of the morphology of individuals of Anabaena circinalis growing in a bloom in Embalse Paso de las Piedras (Provincia de Buenos Aires, Argentina, identified by a gene probe for this species

  15. Fitoplancton del embalse Yacyretá (Argentina-Paraguay a una década de su llenado Phytoplankton of the Yacyretá Reservoir (Argentina-Paraguay after a decade from its filling

    Directory of Open Access Journals (Sweden)

    Norma Meichtry de Zaburlín

    2013-03-01

    Full Text Available Se estudió la estructura y dinámica del fitoplancton del embalse Yacyretá en relación con las principales variables limnológicas durante el periodo diciembre de 2004 a noviembre de 2005, a 10 años del llenado del embalse. Las muestras cualitativas y cuantitativas fueron recolectadas en 6 estaciones, previamente seleccionadas siguiendo un criterio de zonación longitudinal. Se analizó la densidad, composición, riqueza, diversidad específica, equitatividad y grupos taxonómicos dominantes. Durante el período de estudio, el embalse Yacyretá no presentó estratificación térmica y la concentración de oxígeno disuelto fue alta en toda la columna de agua. Se registraron 200 especies distribuidas en 9 clases. El número de especies por muestra osciló entre 14 y 45 taxa y la diversidad específica entre 1.55 y 4.61 bits. La densidad varió entre 66 y 10 060 ind/ml, con dominancia de Cryptophyceae y Bacillariophyceae en las distintas regiones del embalse. Al inicio del otoño y final de la primavera, se registró un aumento en la densidad de Cyanobacteria en las estaciones con mayor tiempo de residencia del agua. La composición y densidad del fitoplancton presentó una marcada variación espacial y temporal determinada principalmente, por las variaciones del régimen hidrosedimentológico del río Paraná.In this study, we analyzed the structure and dynamics of the phytoplankton of the Yacyretá Reservoir and its relationship with the main limnological variables between December 2004 and November 2005, 10 years after the filling of the reservoir. Qualitative and quantitative samples were collected at 6 sampling stations, following a longitudinal zonation criterion. Density, composition, specific richness, diversity, equitability and dominance were analyzed. During the studied period, the Yacyretá Reservoir did not present thermal stratification, and the dissolved oxygen concentration in the water column was high. Two hundred species in 9

  16. Especies leñosas nativas claves para la restauración ecológica del Embalse de Chisacá, Colombia, con base en rasgos importantes de su historia de vida

    OpenAIRE

    Rodríguez Ramírez Natalia; Vargas Orlando

    2006-01-01

    Se determinaron cinco especies nativas leñosas, como claves para la restauración de plantaciones de Pinus patula
    y Corredor ripario potrerizado del embalse de Chisacá (localidad de Usme, Bogotá, Colombia 3.000-3.250
    msnm; 4°08’59’’ N; 74°17’62’’ W), con base en Rasgos de de Historia de Vida (RHV) y otras características de
    especies presentes en estas áreas. Teniendo en cuenta el objetivo del estudio y las características de las áreas
    degradadas se s...

  17. Water dynamics on ice and hydrate lattices studied by second-order central-line stimulated-echo oxygen-17 nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Oxygen-17 stimulated-echo spectroscopy is a novel nuclear magnetic resonance (NMR) technique that allows one to investigate the time scale and geometry of ultraslow molecular motions in materials containing oxygen. The method is based on detecting orientationally encoded frequency changes within oxygen’s central-transition NMR line that are caused by second-order quadrupolar interactions. In addition to the latter, the present theoretical analysis of various two-pulse echo and stimulated-echo pulse sequences takes also heteronuclear dipolar interactions into account. As an experimental example, the ultraslow water motion in polycrystals of tetrahydrofuran clathrate hydrate is studied via two-time oxygen-17 stimulated-echo correlation functions. The resulting correlation times and those of hexagonal ice are similar to those from previous deuteron NMR measurements. Calculations of the echo functions’ final-state correlations for various motional models are compared with the experimental data of the clathrate hydrate. It is found that a six-site model including the oxygen-proton dipolar interaction describes the present results

  18. Water dynamics on ice and hydrate lattices studied by second-order central-line stimulated-echo oxygen-17 nuclear magnetic resonance

    Science.gov (United States)

    Adjei-Acheamfour, Mischa; Tilly, Julius F.; Beerwerth, Joachim; Böhmer, Roland

    2015-12-01

    Oxygen-17 stimulated-echo spectroscopy is a novel nuclear magnetic resonance (NMR) technique that allows one to investigate the time scale and geometry of ultraslow molecular motions in materials containing oxygen. The method is based on detecting orientationally encoded frequency changes within oxygen's central-transition NMR line that are caused by second-order quadrupolar interactions. In addition to the latter, the present theoretical analysis of various two-pulse echo and stimulated-echo pulse sequences takes also heteronuclear dipolar interactions into account. As an experimental example, the ultraslow water motion in polycrystals of tetrahydrofuran clathrate hydrate is studied via two-time oxygen-17 stimulated-echo correlation functions. The resulting correlation times and those of hexagonal ice are similar to those from previous deuteron NMR measurements. Calculations of the echo functions' final-state correlations for various motional models are compared with the experimental data of the clathrate hydrate. It is found that a six-site model including the oxygen-proton dipolar interaction describes the present results.

  19. Water dynamics on ice and hydrate lattices studied by second-order central-line stimulated-echo oxygen-17 nuclear magnetic resonance

    Energy Technology Data Exchange (ETDEWEB)

    Adjei-Acheamfour, Mischa; Tilly, Julius F.; Beerwerth, Joachim; Böhmer, Roland [Fakultät Physik, Technische Universität Dortmund, 44221 Dortmund (Germany)

    2015-12-07

    Oxygen-17 stimulated-echo spectroscopy is a novel nuclear magnetic resonance (NMR) technique that allows one to investigate the time scale and geometry of ultraslow molecular motions in materials containing oxygen. The method is based on detecting orientationally encoded frequency changes within oxygen’s central-transition NMR line that are caused by second-order quadrupolar interactions. In addition to the latter, the present theoretical analysis of various two-pulse echo and stimulated-echo pulse sequences takes also heteronuclear dipolar interactions into account. As an experimental example, the ultraslow water motion in polycrystals of tetrahydrofuran clathrate hydrate is studied via two-time oxygen-17 stimulated-echo correlation functions. The resulting correlation times and those of hexagonal ice are similar to those from previous deuteron NMR measurements. Calculations of the echo functions’ final-state correlations for various motional models are compared with the experimental data of the clathrate hydrate. It is found that a six-site model including the oxygen-proton dipolar interaction describes the present results.

  20. Possibilities and limitations of analogue methods for studying the dynamics of nuclear power stations; Possibilites et limitations du calcul analogique pour les etudes dynamiques de centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Caillet, C.; Deat, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1. Introduction: the present paper is devoted to analog simulation of problems related to nuclear reactors other than the simulation of the kinetic equations which is well known. 2. Thermodynamic problems: various problems relative to temperature evolution in a reactor, in a pipe, in an exchanger, in a turbine, are studied, and simulation techniques used by earlier authors are critically reviewed. 3. Pipe simulators: it is shown that this problem can be solved by the use of specialized simulators which will be described and analysed. 4. Rotating machine simulators: the particular aspect of rotating machine calculations introducing frequent use of diagrams is emphasized. A simulator requiring both digital and analogue methods is described. 5. The study of a nuclear power station: as an example it is proposed to discuss problems a rising in connection with the preceding elements (a, b, c, d) when simulating the behaviour of large nuclear plants. The part played by ordinary computing elements for the simulation of the different servomechanism transfer functions is considered and process of regulation is outlined. 6. Conclusion: the necessity of the use of high quality simulators and computers is underlined and the accuracy of the solutions is discussed. (author)Fren. [French] 1. Cinetique des reacteurs: la simulation des equations cinetiques d'un reacteur nucleaire ne pose desormais plus de probleme. II est donc possible de faire le point des differentes applications de la technique analogique dans ce domaine. 2. Les problemes thermodynamiques: on discute les differents problemes poses par l'evolution des temperatures dans un reacteur, dans une tuyauterie, dans un echangeur, dans une turbine, et on passe en revue les techniques de simulation proposees jusqu'a ce jour. 3s simulateurs de tuyauteries: on montre comment les differents problemes poses ci-dessus peuvent etre resolus, pour une classe tres vaste de reacteurs par l'emploi de simulateurs

  1. Variaciones temporales del fitoplancton de los ríos tributarios y emisario del embalse C. Gelsi (Tucumán, Argentina

    Directory of Open Access Journals (Sweden)

    Silvia N Martinez de Marco

    2012-12-01

    Full Text Available En este trabajo se estudiaron las variaciones temporales del fitoplancton de los tributarios (ríos Salí, Tapia y Vipos y del emisario (río Salí del embalse C. Gelsi. La abundancia algal mínima se obtuvo en verano con una biomasa de 0,19-0,58 µg Cl-a L-1 y la máxima en invierno o primavera con una biomasa de 5,43-6,79 µg Cl-a L-1. En los tributarios se destacaron las diatomeas pennadas sobresaliendo Diatoma vulgare y Cymbella affinis y en el río Salí (emisario dominaron las céntricas especialmente Aulacoseira granulata y Cyclotella meneghiniana. Las Chlorophyta se ubicaron en segundo término en el río Salí, las Cyanobacteria codominaron en los ríos Vipos y Tapia en marzo de 1998 y las Dinophyta sólo fueron observadas en el Salí (emisario. El índice de diversidad específica osciló entre 0,2 y 4,2 y el sapróbico caracterizó las aguas como "no poluídas" o "ligeramente poluídas" en invierno y como "moderadamente poluídas" en verano. El NMDS ordenó temporalmente las muestras según la abundancia de las especies algales consideradas. Los dos primeros ejes del RDA separaron los sitios según gradientes de temperatura, pH, conductividad, DBO5 y nitrato, además de la abundancia de Aulacoseira granulata, Cyclotella meneghiniana, Ulnaria ulna, Cymbella affinis y Leptolyngbya foveolarum.Temporal variations of the phytoplankton of the tributaries and effluent from the C. Gelsi reservoir (Tucumán, Argentina. In this paper we analyzed the phytoplankton variation in the tributaries (Salí, Tapia, and Vipos rivers and effluent (Salí River from the C. Gelsi reservoir according to a seasonal gradient. The minimum algal abundance took place in summer with a biomass of 0.19-0.58 µg Cl-a L-1, while the maximum occurred in winter or in spring, with a biomass of 5.43-6.79 µg Cl-a L-1. In the tributaries pennate diatoms prevailed, Diatoma vulgare and Cymbella affinis were most abundant, while in the Salí river (Gelsi effluent centric

  2. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states

    International Nuclear Information System (INIS)

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  3. Methodology for risk-based configuration control of nuclear power plant operation

    International Nuclear Information System (INIS)

    The hazardous configurations control in Nuclear Power Plants is an application of a previous Probabilistic Safety Analysis (PSA). A more complete option would be the risk monitoring for the online detection of these configurations but expert personnel would be required to deal with the complexities of PSA and risk monitor. The paper presents a simpler but effective approach: a method of configuration control, based on dependencies matrixes. The algorithm is included in a computer code called SECURE A-Z. The configuration control is carried out in a qualitative way, without previous PSA results and not using a Risk Monitor. The simplicity of the method warrants its application to facilities where these tools have not been developed, allowing the detection of hazardous configurations during operation and increasing plant safety. This configuration control system was implemented in the Embalse Nuclear Power Plant in Argentina. The paper shows the application of the algorithm to the analysis of a simplified safety system. (author)

  4. Steam generator materials and secondary side water chemistry in nuclear power stations

    International Nuclear Information System (INIS)

    The main purpose of this work is to summarize the European and North American experiences regarding the materials used for the construction of the steam generators and their relative corrosion resistance considering the water chemestry control method. Reasons underlying decision for the adoption of Incoloy 800 as the material for the secondary steam generator system for Atucha I Nuclear Power Plant (Atucha Reactor) and Embalse de Rio III Nuclear Power Plant (Cordoba Reactor) are pointed out. Backup information taken into consideration for the decision of utilizing the All Volatil Treatment for the water chemistry control of the Cordoba Reactor is detailed. Also all the reasonswhich justify to continue with the congruent fosfatic method for the Atucha Reactor are analyzed. Some investigation objectives which would eventually permit the revision of the decisions taken on these subjects are proposed. (E.A.C.)

  5. Past, present and future of nuclear energy and the nuclear fuel cycle in Argentina

    International Nuclear Information System (INIS)

    Full text: Argentina started its nuclear activities early in the fifties with Uranium Exploration, Research Reactors design and construction and Research Reactors Fuel development and manufacturing. At the end of the sixties and after the construction of three research reactors, a decision was made on the construction of a series of NPP of D2O-Natural Uranium type. Two of them, Atucha I and Embalse are in operation and the third is under construction waiting for the decision of its completion. Three stages can be shown as an evolution of the Nuclear Fuel Technology in Argentina. The first one was the acquisition of basic knowledge in material properties, metallurgical processes and research reactor fuel manufacturing. This stage was developed late in the fifties and during the sixties. The second covers the Fuel Engineering and Power Reactor Prototype fuel manufacturing capability. This step was carried out from late 60's to the end of the seventies. The third was the establishment of a Nuclear Fuel Cycle Industry that was developed during the eighties and beginning of the nineties. CNEA developed a group of Companies that operate installations and are responsible for the supply and goods of the Nuclear Fuel Cycle. CNEA remains as the technological support for this industry and participates as technological partner in the shear of the stock. We face now a new challenging step characterised by the needs of a very high-density research reactor fuel and highly reliable and low cost fuel for power reactor. (author)

  6. Nuclear Factor kappa B is central to Marek’s Disease herpesvirus induced neoplastic transformation of CD30 expressing lymphocytes in-vivo

    Directory of Open Access Journals (Sweden)

    Kumar Shyamesh

    2012-09-01

    Full Text Available Abstract Background Marek’s Disease (MD is a hyperproliferative, lymphomatous, neoplastic disease of chickens caused by the oncogenic Gallid herpesvirus type 2 (GaHV-2; MDV. Like several human lymphomas the neoplastic MD lymphoma cells overexpress the CD30 antigen (CD30hi and are in minority, while the non-neoplastic cells (CD30lo form the majority of population. MD is a unique natural in-vivo model of human CD30hi lymphomas with both natural CD30hi lymphomagenesis and spontaneous regression. The exact mechanism of neoplastic transformation from CD30lo expressing phenotype to CD30hi expressing neoplastic phenotype is unknown. Here, using microarray, proteomics and Systems Biology modeling; we compare the global gene expression of CD30lo and CD30hi cells to identify key pathways of neoplastic transformation. We propose and test a specific mechanism of neoplastic transformation, and genetic resistance, involving the MDV oncogene Meq, host gene products of the Nuclear Factor Kappa B (NF-κB family and CD30; we also identify a novel Meq protein interactome. Results Our results show that a CD30lo lymphocytes are pre-neoplastic precursors and not merely reactive lymphocytes; b multiple transformation mechanisms exist and are potentially controlled by Meq; c Meq can drive a feed-forward cycle that induces CD30 transcription, increases CD30 signaling which activates NF-κB, and, in turn, increases Meq transcription; d Meq transcriptional repression or activation of the CD30 promoter generally correlates with polymorphisms in the CD30 promoter distinguishing MD-lymphoma resistant and susceptible chicken genotypes e MDV oncoprotein Meq interacts with proteins involved in physiological processes central to lymphomagenesis. Conclusions In the context of the MD lymphoma microenvironment (and potentially in other CD30hi lymphomas as well, our results show that the neoplastic transformation is a continuum and the non-neoplastic cells are actually pre

  7. Negative sequence relay applied to generator 1 of the Laguna Verde nuclear power plant; Aplicacion de un relevador de secuencia negativa en el generador 1 de la central de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Diaz de la Serna P, Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1988-12-31

    The rotor of a synchronous generator can be dangerously heated in a short time by stator current unbalance, therefore it must be protected with a specific relay. This article discusses the protection and the adjustments selected for Unit 1 of the Comision Federal de Electricidad Laguna Verde Nuclear Nuclear Power Station. [Espanol] El rotor de un generador sincrono puede calentarse peligrosamente en un tiempo corto debido a desbalance de corrientes en el estator, por lo que debe protegerse con un relevador especifico. En este articulo se describen la proteccion y los ajustes seleccionados para la unidad 1, de la central nucleoelectrica Laguna Verde de la Comision Federal de Electricidad.

  8. Estudios de apoyo a la preparación de procedimientos de ejecución de cálculos de seguridad y operación de una central nuclear con modelos integrales de planta

    OpenAIRE

    Rodríguez Moya, Rafael

    2007-01-01

    La Sección de Ingeniería Nuclear de la Universidad Politécnica de Cataluña, ha colaborado desde 1991 con las plantas nucleares de Ascó y Vandellós con el objetivo, entre otros, de conseguir un modelo validado y documentado de estas centrales. Es por ello que se tiene como objetivo continuo y principal, la mejora y validación de estos modelos, aumentando así la calidad de los datos obtenidos. Siendo la finalidad de esta mejora obtener una óptima y más segura explotación de las p...

  9. Cesium-134 and 137 activities in the central North Pacific Ocean after the Fukushima Dai-ichi nuclear power plant accident

    Directory of Open Access Journals (Sweden)

    J. Kameník

    2013-03-01

    Full Text Available Surface seawater 134Cs and 137Cs samples were collected in the central and western North Pacific Ocean during the 1.5 yr after the Fukushima Dai-ichi nuclear power plant accident to monitor dispersion patterns of these radioisotopes towards the Hawaiian Islands. In the absence of other recent sources and due to its short half-life only those parts of the Pacific Ocean would have detectable 134Cs that were impacted by Fukushima releases. Between March and May 2011, 134Cs was not detected around the Hawaiian Islands and Guam. Here, most 137Cs activities (1.2–1.5 Bq m−3 were in the range of expected preexisting levels. Some samples north of the Hawaiian Islands (1.6–1.8 Bq m−3 were elevated above the 18-month baseline established in surface seawater in Hawaii indicating that those might carry atmospheric fallout. The 18-month time-series analysis of surface seawater from Hawaii did not reveal any seasonal variability or trends, with an average activity of 1.46 ± 0.06 Bq m−3 (Station Aloha, 17 values. In contrast, samples collected between Japan and Hawaii contained 134Cs activities in the range of 1–4 Bq m−3 and 137Cs levels were about 2–3 times above the preexisting activities. We found that the southern boundary of the Kuroshio and Kuroshio extension currents represented a boundary for radiation dispersion with higher activities detected within and north of the major currents. The radiation plume has not been detected over the past 1.5 yr at the main Hawaiian Islands due to the transport patterns across the Kuroshio and Kuroshio extension currents.

  10. Cesium-134 and 137 activities in the central North Pacific Ocean after the Fukushima Dai-ichi Nuclear Power Plant accident

    Directory of Open Access Journals (Sweden)

    J. Kameník

    2013-09-01

    Full Text Available Surface seawater 134Cs and 137Cs samples were collected in the central and western North Pacific Ocean during the 2 yr after the Fukushima Dai-ichi Nuclear Power Plant accident to monitor dispersion patterns of these radioisotopes towards the Hawaiian Islands. In the absence of other recent sources and due to its short half-life, only those parts of the Pacific Ocean would have detectable 134Cs values that were impacted by Fukushima releases. Between March and May 2011, 134Cs was not detected around the Hawaiian Islands and Guam. Here, most 137Cs activities (1.2–1.5 Bq m–3 were in the range of expected preexisting levels. Some samples north of the Hawaiian Islands (1.6–1.8 Bq m–3 were elevated above the 23-month baseline established in surface seawater in Hawaii indicating that those might carry atmospheric fallout. The 23-month time-series analysis of surface seawater from Hawaii did not reveal any seasonal variability or trends, with an average activity of 1.46 ± 0.06 Bq m–3 (Station Aloha, 18 values. In contrast, samples collected between Japan and Hawaii contained 134Cs activities in the range of 1–4 Bq m–3, and 137Cs levels were about 2–3 times above the preexisting activities. We found that the southern boundary of the Kuroshio and Kuroshio extension currents represented a boundary for radiation dispersion with higher activities detected within and north of the major currents. The radiation plume has not been detected over the past 2 yr at the main Hawaiian Islands due to the transport patterns across the Kuroshio and Kuroshio extension currents.

  11. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  12. Modifications in the design of the fuel assemblies to improve the competitiveness of the nuclear energy in the electricity market

    International Nuclear Information System (INIS)

    Full text: Several changes in the electricity market of Argentina produced in the last years have stressed the necessity of reducing the cost of the nuclear generation to improve its competitiveness and to remain as an alternative in the market. To achieve this objective several modifications of the fuel assemblies used in the Embalse nuclear power plant were considered. In this paper the increase of the mass of uranium in the fuel elements and its impact in reducing the annual fuel consumption and therefore the cost of generation is analyzed. To improve the fuel design the effort was focused in those modifications with and easy implementation and immediate application in order to assist to the necessary reduction of costs without affecting other aspects of the operation. At the same time this modifications should not require significant changes in the fuel manufacturing plant or in the nuclear station. Changes in fuel pellet and fuel rod designs were previously verified using the ELESIM code that allows to simulate the behavior of fuel rods during the nuclear service. Fuel assemblies with this modifications have been introduced in Embalse reactor since the middle of 1997 with a satisfactory behavior in their nuclear service. As a result of this design improvements the mass of uranium of the fuel assemblies increased in about 1%. At the end of the program the increment will reach approximately 2%. A similar study for the Atucha 1 fuel is close to completion. In this case the increase of mass of Uranium could overcome the 3%. At the same time a program to increase the number of fuel rods to 37 is being performed. Considering both programs the total increment of mass would be approximately 6%. This paper also briefly describes additional fuel design modifications which implementation is not so immediate and requires detailed thermalhydraulic and neutronic analysis

  13. The integripennis species group of Geocharidius Jeannel, 1963 (Carabidae, Bembidiini, Anillina from Nuclear Central America: a taxonomic review with notes about biogeography and speciation

    Directory of Open Access Journals (Sweden)

    Igor Sokolov

    2014-09-01

    Full Text Available Our review recognizes 15 species of the integripennis species group of Geocharidius from Nuclear Central America, include three species previously described (G. gimlii Erwin, G. integripennis (Bates and G. zullinii Vigna Taglianti and 12 described here as new. They are: G. andersoni sp. n. (type locality: Chiapas, Chiapas Highlands, Cerro Huitepec and G. vignatagliantii sp. n. (type locality: Chiapas, Motozintla, Sierra Madre de Chiapas, Benito Juárez from Mexico; G. antigua sp. n. (type locality: Sacatepéquez, 5 km SE of Antigua, G. balini sp. n. (type locality: Suchitepéquez, 4 km S of Volcan Atitlán, G. erwini sp. n. (type locality: Quiché Department, 7 km NE of Los Encuentros, G. jalapensis sp. n. (type locality: Jalapa Department, 4 km E of Mataquescuintla, G. longinoi, sp. n. (type locality: El Progreso Department, Cerro Pinalón, and G. minimus sp. n. (type locality: Sacatepéquez Department, 5 km SE of Antigua from Guatemala; and G. celaquensis sp. n. (type locality: Lempira Department, Celaque National Park, G. comayaguanus sp. n. (type locality: Comayagua Department, 18 km ENE of Comayagua, G. disjunctus sp. n. (type locality: Francisco Morazán, La Tigra National Park, and G. lencanus sp. n. (type locality: Lempira Department, Celaque National Park from Honduras. For all members of the group, adult structural characters, including male and female genitalia, are described, and a taxonomic key for all members of the integripennis species group is presented based on these characters. Behavioral and biogeographical aspects of speciation in the group are discussed, based on the morphological analysis. In all cases of sympatry, pairs of closely related species show greater differences in sizes than pairs of more remotely related species. Integripennis group species occupy six different montane areas at elevations above 1300m, with no species shared among them. Major faunal barriers in the region limiting present species distributions

  14. The integripennis species group of Geocharidius Jeannel, 1963 (Carabidae, Bembidiini, Anillina) from Nuclear Central America: a taxonomic review with notes about biogeography and speciation.

    Science.gov (United States)

    Sokolov, Igor M; Kavanaugh, David H

    2014-01-01

    Our review recognizes 15 species of the integripennis species group of Geocharidius from Nuclear Central America, include three species previously described (Geocharidiusgimlii Erwin, Geocharidiusintegripennis (Bates) and Geocharidiuszullinii Vigna Taglianti) and 12 described here as new. They are: Geocharidiusandersoni sp. n. (type locality: Chiapas, Chiapas Highlands, Cerro Huitepec) and Geocharidiusvignatagliantii sp. n. (type locality: Chiapas, Motozintla, Sierra Madre de Chiapas, Benito Juárez) from Mexico; Geocharidiusantigua sp. n. (type locality: Sacatepéquez, 5 km SE of Antigua), Geocharidiusbalini sp. n. (type locality: Suchitepéquez, 4 km S of Volcan Atitlán), Geocharidiuserwini sp. n. (type locality: Quiché Department, 7 km NE of Los Encuentros), Geocharidiusjalapensis sp. n. (type locality: Jalapa Department, 4 km E of Mataquescuintla), Geocharidiuslonginoi, sp. n. (type locality: El Progreso Department, Cerro Pinalón), and Geocharidiusminimus sp. n. (type locality: Sacatepéquez Department, 5 km SE of Antigua) from Guatemala; and Geocharidiuscelaquensis sp. n. (type locality: Lempira Department, Celaque National Park), Geocharidiuscomayaguanus sp. n. (type locality: Comayagua Department, 18 km ENE of Comayagua), Geocharidiusdisjunctus sp. n. (type locality: Francisco Morazán, La Tigra National Park), and Geocharidiuslencanus sp. n. (type locality: Lempira Department, Celaque National Park) from Honduras. For all members of the group, adult structural characters, including male and female genitalia, are described, and a taxonomic key for all members of the integripennis species group is presented based on these characters. Behavioral and biogeographical aspects of speciation in the group are discussed, based on the morphological analysis. In all cases of sympatry, pairs of closely related species show greater differences in sizes than pairs of more remotely related species. Integripennis group species occupy six different montane areas at

  15. Riesgo de contaminación con cianobacterias en tres embalses de agua de Santiago de Cuba Risk of pollution with cyanobacteria in three water reservoirs of Santiago de Cuba

    Directory of Open Access Journals (Sweden)

    Liliana M Gómez Luna

    Full Text Available La gestión del riesgo de contaminación con cianobacterias es sin dudas un tema relevante, de gran impacto social. Es bien conocida la relación que existe entre las floraciones de estos microorganismos y serias afectaciones a la salud humana. Con el objetivo de proponer un modelo de gestión del riesgo por contaminación con cianobacterias en embalses de agua para consumo humano, se estudió la presencia de estos microorganismos en tres embalses que servician agua a más del 80% de la población de Santiago de Cuba (Chalóns, Paradas y Charco Mono durante los meses de noviembre de 2008 y marzo de 2009. Se realizaron muestreos cualitativos y cuantitativos para la caracterización del fitoplancton y determinaciones de la densidad fitoplanctónica. Se identifican 73 especies fitoplanctónicas y 9 especies de cianobacterias potencialmente tóxicas. La densidad del fitoplancton osciló entre 5 y 25 x10(4 cél/mL-1. Este estudio contribuye al diseño de una metodología para enfrentar el riesgo de la contaminación por cianobacterias, por lo que tiene impacto social y económico a nivel local.The risk of pollution with cyanobacteria is undoubtedly an important topic of great social impact. It is very well-known the relation between the flowering of these microorganisms and the serious involvement to the human health. With the purpose of proposing an administration model of the risk of pollution with cyanobacteria in water reservoirs for the human consumption, the presence of these bacteria was studied in 3 reservoirs (Chalóns, Paradas and Charco Mono, which supply more than 80 % of Santiago population, from November, 2008 to March, 2009. Qualitative and quantitative samplings were made to characterize the phytoplankton and determine its density, which ranged between 5 and 25x104 cel/mL-1. Seventy three species of phytoplankton and nine cyanobacteria potentially toxic were identified. This study contributes to the design of a methodology to face

  16. Annual report from the realization of the Central Program of the Fundamental Studies no 01.09. ''Studies of elementary particles and nuclear processes'' in 1987

    International Nuclear Information System (INIS)

    Report on the realization of research program in the domain of high and medium energy physics, structural studies by means of nuclear physics methods, nuclear chemistry and high-energy instrumentation in 1987 is presented. Program is coordinated by Institute of Nuclear Physics in Cracow, Institute of Physics of Jagiellonian University in Cracow and Institute of Nuclear Studies in Swierk. The information on international cooperation and costs of the realization of the program are given. Lists of the 487 most important publications are presented. (M.F.W.)

  17. Environmental monitoring in the surroundings of nuclear power plants of Argentina during 1996 and 1997

    International Nuclear Information System (INIS)

    During 1996 and 1997, the environmental monitoring program in the surroundings of nuclear power plants Atucha 1 (CNA-1) and Embalse (CNE) was performed. For the selection of the sample points, sample type and frequency, recommendations were taken into account, as well as the major pathways of exposure to man. The results of the measurements were, in general, below the lower limit of detection and the doses for each critical group were, in the case of CNA I, below 4.9 E-3 mSv during 1996 and below 4.5 E-3 mSv during 1997, and for CNE, below 7.7 E-3 mSv during 1996 and below 9.4 mSv during 1997. All of these values are well below the dose limits established by todays norms (1mSv/year). (author)

  18. Environmental aspects of tritium release in the Argentinas nuclear power station

    International Nuclear Information System (INIS)

    The Argentine nuclear power facilities of Atucha (CNA) and Embalse (CNE) use natural uranium as fuel and heavy water as coolant. During the normal operation a fraction of generated tritium by neutron activation of the deuterium of heavy water, is released into the atmosphere by means of liquid and gaseous discharged. From the radiological protection point of view, it is one of the main effluents. Therefore, from the start in operation of the CNA (1974) and the CNE (1984), continuous determinations of the gaseous and liquid discharged are made, as well as the environmental monitoring in the surroundings of the facilities is realized. In this work, the values of release and the concentration integrated along the time, obtained from the environmental monitoring in both power facilities are correlated. The results obtained with the model of transference used in the preoperational studies, are compared considering the parameters of atmospheric dispersion corresponding to the meteorological conditions of the own site. (author)

  19. Evaluación de cinco métodos de muestreo para abejas en dos estados sucesionales del área de influencia del embalse Porce II (Antioquia.

    Directory of Open Access Journals (Sweden)

    Smith Pardo Allan Henry

    1999-06-01

    Full Text Available Se evalúo la eficacia de cinco métodos para la captura de abejas en algunos bosques y rastrojos bajos de la que será la zona de influencia del embalse Porce II ( Antioquia, Colombia S.A.; los métodos utilizados, consistieron en : jameo a través de dos transectos de 100 m de largo por 2m de ancho, la utilización de trampas Van Somer con pescado descompuesto como cebo, trampas Malaise de 2 m de ancho por 2 m de largo, platos amarillos sobre un pedestal de 1.5 m de altura y finalmente tarros portadores de esencias; todas las trampas estuvieron separadas 12 m entre si y fueron ubicadas al azar por sorteo. En cuanto a la abundancia, riqueza y a los índices de diversidad para las abejas capturadas se destacaron como métodos de evaluación las trampas Van Somer con pescado descompuesto como cebo y el jameo ( más comúnmente utilizado , adicionalmente, el análisis del índice de similitud de Jaccard y de las morfoespecies capturadas por cada método mostraron que cada uno de estos capturó cierta cantidad de morfoespecies exclusivamente.

  20. Evaluación Preliminar de Recursos Culturales Arqueológicos del Embalse de Río Tercero, Provincia de Córdoba, Argentina. Una Contribución a la Gestión Participativa del Patrimonio Cultural

    Directory of Open Access Journals (Sweden)

    Jerónimo Angueyra

    2007-01-01

    Full Text Available Gran cantidad de asentamientos arqueológicos fueron afectados por la construcción del embalse de Río Tercero desde la década de 1930. Un vasto número de ellos han ya desaparecido pero una porción aún no determinada sobrevive y desaparece progresivamente cada año por diversos procesos asociados con factores naturales y actividades humanas en la región. Esta iniciativa pretende determinar de forma preliminar la cantidad, composición, ubicación y estado de conservación de los recursos arqueológicos existentes, por medio de la investigación compartida con miembros de la comunidad local, a partir de la exploración de las relaciones entre la población actual y esta parte del medio ambiente a lo largo del tiempo, focalizando los mecanismos socioculturales y naturales de la degradación ambiental y la desaparición del patrimonio arqueológico.

  1. Outlook to nonproliferation activities in the world and cooperation in peaceful uses of nuclear energy among Turkey, Caucasus and Central Asia

    International Nuclear Information System (INIS)

    Full text: Following the First Geneva Conference in 1955 for expanding peaceful uses of nuclear energy, Turkey was one of the first countries to start activities in the nuclear field. Turkish Atomic Energy Authority (TAEK) was established in 1956 and Turkey became a member of the International Atomic Energy Agency established in 1957. TAEK was established to support, co-ordinate and perform the activities in peaceful uses of nuclear energy and act as a regulatory body and establish cooperation with countries and international organizations. In the late nineteen-ninetieth, TAEK, besides the cooperation with various countries, has involved in cooperating with nuclear institutes of Azerbaijan, Kazakhstan, Kyrgyzstan, Uzbekistan and Turkmenistan for establishment of bilateral and multilateral scientific and technical cooperation in peaceful uses of nuclear energy and signed protocols with Scientific Organisations of Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan. These protocols enable parties to organize joint projects, conferences, seminars, training programs, establish laboratories for the joint studies and make joint efforts to seek support from their governments and international organizations for these activities. Also, an executive committee has been set up with delegates from each organization under TAEK that also provides the secretarial service for organizing the joint activities. Turkey supports the non-proliferation activities that do not prevent the peaceful uses of nuclear energy and in this respect as signed Non-Proliferation Treaty (NPT) and Comprehensive Nuclear Test Ban Treaty (CTBT). Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan have also signed these Treaties following their independence and, except Kyrgyzstan, have become members to IAEA

  2. Reflections on the development of local suppliers for the Argentine nuclear industry

    International Nuclear Information System (INIS)

    Argentina has given recently a new start to its nuclear power activities. Looking for background and experiences that can be useful under the new reality, the paper is a survey of the past development of local suppliers for the national nuclear industry. Based on the intention to answer the questions: Why so early it was decided to build a nuclear power plant? Why it was decided to buy it under a turnkey basis rather than developing an indigenous design? and what was the meaning of the 'opening of the technology package' at that time?, the paper describes the actions that led to the purchase of the Atucha I, Embalse and Atucha II nuclear power plants and how these decisions were implemented in order to maximize local participation and the technology transfer. It also analyzes the influence of the Argentine Nuclear Plan of the late seventies on the development of endogenous technology and describes the facts that helped to preserve until now the technological nuclear capabilities of the country in spite of the stopping of the Atucha II construction, and to create positive expectations regarding the revival of the local industry as a supplier of nuclear goods and services. (author)

  3. The continuous improvement system of nuclear power plant of Laguna Verde; El sistema de mejora continua de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rivera C, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 42.5 Cardel-Nautla, Veracruz (Mexico)], e-mail: arr99999@cfe.gob.mx

    2009-10-15

    This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

  4. Optimal nuclear magnetic resonance excitation schemes for the central transition of a spin 3/2 in the presence of residual quadrupolar coupling.

    Science.gov (United States)

    Lee, Jae-Seung; Regatte, Ravinder R; Jerschow, Alexej

    2008-12-14

    Optimal control theory is applied for enhancing the intensity of the central peak of a spin 3/2 signal in the presence of a residual quadrupolar coupling. While a maximum enhancement is always possible in the regime omega(rf) control and test these with (23)Na NMR in this regime. In addition to enhancing the intensity of the central transition signal, the satellite peaks can be effectively suppressed, which is a useful feature for the implementation in (23)Na imaging sequences. PMID:19071931

  5. Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde; Metodologia de la gestion del envejecimiento en estructuras, sistemas y componentes de una central nuclear y su aplicacion a un programa piloto en Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Fernandez S, G. [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Dos Bocas, 54270 Veracruz (Mexico)], e-mail: gfdezs@cfe.gob.mx

    2009-10-15

    From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

  6. Initial Basis for Agronomic Countermeasure Selection Following a Nuclear Accident

    International Nuclear Information System (INIS)

    During the recovery stage, following a nuclear accident, application of agricultural countermeasures will be relevant to the minimization of the radiation induced detriment due to ingestion of locally produced contaminated foodstuff, as long as the magnitude of the averted dose is sufficient to justify their implementation. Nuclear emergency planning in Argentina currently holds food ban as the accepted countermeasure, at least until other measures are taken. Though it may ensure no residual collective dose, food ban may also imply very high costs, compared to other alternatives, specially due to the need of disposing off perishable food such as milk. Therefore, an exhaustive evaluation of all the alternatives, considering both quantitative and qualitative factors is still needed to identify optimal countermeasure strategies, bearing in mind also that decisions made during the early phase of an emergency will affect the fate of the measures to be taken later. As a first step in this direction, a basic quantitative decis sion-aiding technique, the cost-benefit analysis, is carried out for comparison of countermeasures related to Cesium contaminated cow-milk which are considered feasible for implementation in Argentina. Countermeasures total costs are estimated from various local sources, while their effectiveness are adopted from international bibliography. At this stage, a simple theoretical example considering milk contamination in the surroundings of the Embalse Nuclear Power Plant is used for a generic analysis, since actual collective doses and costs can only be calculated for a specific modelled scenario. (authors)

  7. Analysis of occupational doses in radioactive and nuclear facilities

    International Nuclear Information System (INIS)

    Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

  8. Procedures and techniques for monitoring the radiation detection, signalization and alarm systems in the centralized ambience monitoring systems of the basic nuclear facilities of the CEN Saclay

    International Nuclear Information System (INIS)

    After referring to the regulations governing the 'systematic ambience monitoring' in the basic nuclear facilities, the main radiation detection, signalization and alarm devices existing at present in these facilities of the Saclay Nuclear Study Centre are described. The analysis of the operating defects of the measuring channels and detection possibilities leads to the anomalies being classified in two separate groups: the anomalies of the logical 'all or nothing' type of which all the possible origins are integrated into a so-called 'continuity' line and the evolutive anomalies of various origins corresponding to poor functioning extending possibly to a complete absence of signal. The techniques for testing the detection devices of the radiation monitoring board set up in the 'Departement de Rayonnements' at the Saclay Nuclear Study Centre are also described

  9. Practical training in the operation of nuclear power plants with Interactive Graphic Simulator of Zorita; Formacion practica en la operacion de centrales nucleares con el Simulador Grafico Interactivo de Zorita

    Energy Technology Data Exchange (ETDEWEB)

    Cuervo, D.; Garcia-Herranz, N.; Garcia, S.; Davila, R.; Ahnert, C.; Aragones, J. M.; Cabellos, O.; Gallego, E.; Lorente, A.; Minguez, E.; Rebollo, L.; Blanco, J.

    2010-07-01

    In April 2008 a collaboration agreement was signed between Gas Natural Union Fenosa and the Universad Politecnica de Madrid for the creation of the Aula Jose Cabrera dedicated to train professionals in the field of nuclear technology. The Classroom located in the Department of Nuclear Engineering, has been equipped with the Interactive Graphic Simulator of Zorita (SGIZ). The use of the simulator intended to improve the quality of teaching in the area of Nuclear Engineering. It integrates in the teachings of Industrial Engineering degree and the Master of Nuclear Science and Technology. Different manuals are under preparation to make it a suitable tool for teaching purpose. These manuals will guide the student so that learning takes place both through the guidance of the teacher as independently. (Author) 3 refs.

  10. Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at $\\sqrt{s_{NN}}$ = 2.76 TeV

    CERN Document Server

    Adam, Jaroslav; Aggarwal, Madan Mohan; Aglieri Rinella, Gianluca; Agnello, Michelangelo; Agrawal, Neelima; Ahammed, Zubayer; Ahn, Sang Un; Aimo, Ilaria; Aiola, Salvatore; Ajaz, Muhammad; Akindinov, Alexander; Alam, Sk Noor; Aleksandrov, Dmitry; Alessandro, Bruno; Alexandre, Didier; Alfaro Molina, Jose Ruben; Alici, Andrea; Alkin, Anton; Millan Almaraz, Jesus Roberto; Alme, Johan; Alt, Torsten; Altinpinar, Sedat; Altsybeev, Igor; Alves Garcia Prado, Caio; Andrei, Cristian; Andronic, Anton; Anguelov, Venelin; Anielski, Jonas; Anticic, Tome; Antinori, Federico; Antonioli, Pietro; Aphecetche, Laurent Bernard; Appelshaeuser, Harald; Arcelli, Silvia; Armesto Perez, Nestor; Arnaldi, Roberta; Arsene, Ionut Cristian; Arslandok, Mesut; Audurier, Benjamin; Augustinus, Andre; Averbeck, Ralf Peter; Azmi, Mohd Danish; Bach, Matthias Jakob; Badala, Angela; Baek, Yong Wook; Bagnasco, Stefano; Bailhache, Raphaelle Marie; Bala, Renu; Baldisseri, Alberto; Baltasar Dos Santos Pedrosa, Fernando; Baral, Rama Chandra; Barbano, Anastasia Maria; Barbera, Roberto; Barile, Francesco; Barnafoldi, Gergely Gabor; Barnby, Lee Stuart; Ramillien Barret, Valerie; Bartalini, Paolo; Barth, Klaus; Bartke, Jerzy Gustaw; Bartsch, Esther; Basile, Maurizio; Bastid, Nicole; Basu, Sumit; Bathen, Bastian; Batigne, Guillaume; Batista Camejo, Arianna; Batyunya, Boris; Batzing, Paul Christoph; Bearden, Ian Gardner; Beck, Hans; Bedda, Cristina; Behera, Nirbhay Kumar; Belikov, Iouri; Bellini, Francesca; Bello Martinez, Hector; Bellwied, Rene; Belmont Iii, Ronald John; Belmont Moreno, Ernesto; Belyaev, Vladimir; Bencedi, Gyula; Beole, Stefania; Berceanu, Ionela; Bercuci, Alexandru; Berdnikov, Yaroslav; Berenyi, Daniel; Bertens, Redmer Alexander; Berzano, Dario; Betev, Latchezar; Bhasin, Anju; Bhat, Inayat Rasool; Bhati, Ashok Kumar; Bhattacharjee, Buddhadeb; Bhom, Jihyun; Bianchi, Livio; Bianchi, Nicola; Bianchin, Chiara; Bielcik, Jaroslav; Bielcikova, Jana; Bilandzic, Ante; Biswas, Rathijit; Biswas, Saikat; Bjelogrlic, Sandro; Blair, Justin Thomas; Blanco, Fernando; Blau, Dmitry; Blume, Christoph; Bock, Friederike; Bogdanov, Alexey; Boggild, Hans; Boldizsar, Laszlo; Bombara, Marek; Book, Julian Heinz; Borel, Herve; Borissov, Alexander; Borri, Marcello; Bossu, Francesco; Botta, Elena; Boettger, Stefan; Braun-Munzinger, Peter; Bregant, Marco; Breitner, Timo Gunther; Broker, Theo Alexander; Browning, Tyler Allen; Broz, Michal; Brucken, Erik Jens; Bruna, Elena; Bruno, Giuseppe Eugenio; Budnikov, Dmitry; Buesching, Henner; Bufalino, Stefania; Buncic, Predrag; Busch, Oliver; Buthelezi, Edith Zinhle; Bashir Butt, Jamila; Buxton, Jesse Thomas; Caffarri, Davide; Cai, Xu; Caines, Helen Louise; Calero Diaz, Liliet; Caliva, Alberto; Calvo Villar, Ernesto; Camerini, Paolo; Carena, Francesco; Carena, Wisla; Carnesecchi, Francesca; Castillo Castellanos, Javier Ernesto; Castro, Andrew John; Casula, Ester Anna Rita; Cavicchioli, Costanza; Ceballos Sanchez, Cesar; Cepila, Jan; Cerello, Piergiorgio; Cerkala, Jakub; Chang, Beomsu; Chapeland, Sylvain; Chartier, Marielle; Charvet, Jean-Luc Fernand; Chattopadhyay, Subhasis; Chattopadhyay, Sukalyan; Chelnokov, Volodymyr; Cherney, Michael Gerard; Cheshkov, Cvetan Valeriev; Cheynis, Brigitte; Chibante Barroso, Vasco Miguel; Dobrigkeit Chinellato, David; Chochula, Peter; Choi, Kyungeon; Chojnacki, Marek; Choudhury, Subikash; Christakoglou, Panagiotis; Christensen, Christian Holm; Christiansen, Peter; Chujo, Tatsuya; Chung, Suh-Urk; Zhang, Chunhui; Cicalo, Corrado; Cifarelli, Luisa; Cindolo, Federico; Cleymans, Jean Willy Andre; Colamaria, Fabio Filippo; Colella, Domenico; Collu, Alberto; Colocci, Manuel; Conesa Balbastre, Gustavo; Conesa Del Valle, Zaida; Connors, Megan Elizabeth; Contreras Nuno, Jesus Guillermo; Cormier, Thomas Michael; Corrales Morales, Yasser; Cortes Maldonado, Ismael; Cortese, Pietro; Cosentino, Mauro Rogerio; Costa, Filippo; Crochet, Philippe; Cruz Albino, Rigoberto; Cuautle Flores, Eleazar; Cunqueiro Mendez, Leticia; Dahms, Torsten; Dainese, Andrea; Danu, Andrea; Das, Debasish; Das, Indranil; Das, Supriya; Dash, Ajay Kumar; Dash, Sadhana; De, Sudipan; De Caro, Annalisa; De Cataldo, Giacinto; De Cuveland, Jan; De Falco, Alessandro; De Gruttola, Daniele; De Marco, Nora; De Pasquale, Salvatore; Deisting, Alexander; Deloff, Andrzej; Denes, Ervin Sandor; D'Erasmo, Ginevra; Di Bari, Domenico; Di Mauro, Antonio; Di Nezza, Pasquale; Diaz Corchero, Miguel Angel; Dietel, Thomas; Dillenseger, Pascal; Divia, Roberto; Djuvsland, Oeystein; Dobrin, Alexandru Florin; Dobrowolski, Tadeusz Antoni; Domenicis Gimenez, Diogenes; Donigus, Benjamin; Dordic, Olja; Drozhzhova, Tatiana; Dubey, Anand Kumar; Dubla, Andrea; Ducroux, Laurent; Dupieux, Pascal; Ehlers Iii, Raymond James; Elia, Domenico; Engel, Heiko; Erazmus, Barbara Ewa; Erdemir, Irem; Erhardt, Filip; Eschweiler, Dominic; Espagnon, Bruno; Estienne, Magali Danielle; Esumi, Shinichi; Eum, Jongsik; Evans, David; Evdokimov, Sergey; Eyyubova, Gyulnara; Fabbietti, Laura; Fabris, Daniela; Faivre, Julien; Fantoni, Alessandra; Fasel, Markus; Feldkamp, Linus; Felea, Daniel; Feliciello, Alessandro; Feofilov, Grigorii; Ferencei, Jozef; Fernandez Tellez, Arturo; Gonzalez Ferreiro, Elena; Ferretti, Alessandro; Festanti, Andrea; Feuillard, Victor Jose Gaston; Figiel, Jan; Araujo Silva Figueredo, Marcel; Filchagin, Sergey; Finogeev, Dmitry; Fiore, Enrichetta Maria; Fleck, Martin Gabriel; Floris, Michele; Foertsch, Siegfried Valentin; Foka, Panagiota; Fokin, Sergey; Fragiacomo, Enrico; Francescon, Andrea; Frankenfeld, Ulrich Michael; Fuchs, Ulrich; Furget, Christophe; Furs, Artur; Fusco Girard, Mario; Gaardhoeje, Jens Joergen; Gagliardi, Martino; Gago Medina, Alberto Martin; Gallio, Mauro; Gangadharan, Dhevan Raja; Ganoti, Paraskevi; Gao, Chaosong; Garabatos Cuadrado, Jose; Garcia-Solis, Edmundo Javier; Gargiulo, Corrado; Gasik, Piotr Jan; Germain, Marie; Gheata, Andrei George; Gheata, Mihaela; Ghosh, Premomoy; Ghosh, Sanjay Kumar; Gianotti, Paola; Giubellino, Paolo; Giubilato, Piero; Gladysz-Dziadus, Ewa; Glassel, Peter; Gomez Coral, Diego Mauricio; Gomez Ramirez, Andres; Gonzalez Zamora, Pedro; Gorbunov, Sergey; Gorlich, Lidia Maria; Gotovac, Sven; Grabski, Varlen; Graczykowski, Lukasz Kamil; Graham, Katie Leanne; Grelli, Alessandro; Grigoras, Alina Gabriela; Grigoras, Costin; Grigoryev, Vladislav; Grigoryan, Ara; Grigoryan, Smbat; Grynyov, Borys; Grion, Nevio; Grosse-Oetringhaus, Jan Fiete; Grossiord, Jean-Yves; Grosso, Raffaele; Guber, Fedor; Guernane, Rachid; Guerzoni, Barbara; Gulbrandsen, Kristjan Herlache; Gulkanyan, Hrant; Gunji, Taku; Gupta, Anik; Gupta, Ramni; Haake, Rudiger; Haaland, Oystein Senneset; Hadjidakis, Cynthia Marie; Haiduc, Maria; Hamagaki, Hideki; Hamar, Gergoe; Hansen, Alexander; Harris, John William; Hartmann, Helvi; Harton, Austin Vincent; Hatzifotiadou, Despina; Hayashi, Shinichi; Heckel, Stefan Thomas; Heide, Markus Ansgar; Helstrup, Haavard; Herghelegiu, Andrei Ionut; Herrera Corral, Gerardo Antonio; Hess, Benjamin Andreas; Hetland, Kristin Fanebust; Hilden, Timo Eero; Hillemanns, Hartmut; Hippolyte, Boris; Hosokawa, Ritsuya; Hristov, Peter Zahariev; Huang, Meidana; Humanic, Thomas; Hussain, Nur; Hussain, Tahir; Hutter, Dirk; Hwang, Dae Sung; Ilkaev, Radiy; Ilkiv, Iryna; Inaba, Motoi; Ippolitov, Mikhail; Irfan, Muhammad; Ivanov, Marian; Ivanov, Vladimir; Izucheev, Vladimir; Jacobs, Peter Martin; Jadlovska, Slavka; Jahnke, Cristiane; Jang, Haeng Jin; Janik, Malgorzata Anna; Pahula Hewage, Sandun; Jena, Chitrasen; Jena, Satyajit; Jimenez Bustamante, Raul Tonatiuh; Jones, Peter Graham; Jung, Hyungtaik; Jusko, Anton; Kalinak, Peter; Kalweit, Alexander Philipp; Kamin, Jason Adrian; Kang, Ju Hwan; Kaplin, Vladimir; Kar, Somnath; Karasu Uysal, Ayben; Karavichev, Oleg; Karavicheva, Tatiana; Karayan, Lilit; Karpechev, Evgeny; Kebschull, Udo Wolfgang; Keidel, Ralf; Keijdener, Darius Laurens; Keil, Markus; Khan, Kamal; Khan, Mohammed Mohisin; Khan, Palash; Khan, Shuaib Ahmad; Khanzadeev, Alexei; Kharlov, Yury; Kileng, Bjarte; Kim, Beomkyu; Kim, Do Won; Kim, Dong Jo; Kim, Hyeonjoong; Kim, Jinsook; Kim, Mimae; Kim, Minwoo; Kim, Se Yong; Kim, Taesoo; Kirsch, Stefan; Kisel, Ivan; Kiselev, Sergey; Kisiel, Adam Ryszard; Kiss, Gabor; Klay, Jennifer Lynn; Klein, Carsten; Klein, Jochen; Klein-Boesing, Christian; Kluge, Alexander; Knichel, Michael Linus; Knospe, Anders Garritt; Kobayashi, Taiyo; Kobdaj, Chinorat; Kofarago, Monika; Kollegger, Thorsten; Kolozhvari, Anatoly; Kondratev, Valerii; Kondratyeva, Natalia; Kondratyuk, Evgeny; Konevskikh, Artem; Kopcik, Michal; Kour, Mandeep; Kouzinopoulos, Charalampos; Kovalenko, Oleksandr; Kovalenko, Vladimir; Kowalski, Marek; Koyithatta Meethaleveedu, Greeshma; Kral, Jiri; Kralik, Ivan; Kravcakova, Adela; Krelina, Michal; Kretz, Matthias; Krivda, Marian; Krizek, Filip; Kryshen, Evgeny; Krzewicki, Mikolaj; Kubera, Andrew Michael; Kucera, Vit; Kugathasan, Thanushan; Kuhn, Christian Claude; Kuijer, Paulus Gerardus; Kulakov, Igor; Kumar, Ajay; Kumar, Jitendra; Lokesh, Kumar; Kurashvili, Podist; Kurepin, Alexander; Kurepin, Alexey; Kuryakin, Alexey; Kushpil, Svetlana; Kweon, Min Jung; Kwon, Youngil; La Pointe, Sarah Louise; La Rocca, Paola; Lagana Fernandes, Caio; Lakomov, Igor; Langoy, Rune; Lara Martinez, Camilo Ernesto; Lardeux, Antoine Xavier; Lattuca, Alessandra; Laudi, Elisa; Lea, Ramona; Leardini, Lucia; Lee, Graham Richard; Lee, Seongjoo; Legrand, Iosif; Lehas, Fatiha; Lemmon, Roy Crawford; Lenti, Vito; Leogrande, Emilia; Leon Monzon, Ildefonso; Leoncino, Marco; Levai, Peter; Li, Shuang; Li, Xiaomei; Lien, Jorgen Andre; Lietava, Roman; Lindal, Svein; Lindenstruth, Volker; Lippmann, Christian; Lisa, Michael Annan; Ljunggren, Hans Martin; Lodato, Davide Francesco; Lonne, Per-Ivar; Loginov, Vitaly; Loizides, Constantinos; Lopez, Xavier Bernard; Lopez Torres, Ernesto; Lowe, Andrew John; Luettig, Philipp Johannes; Lunardon, Marcello; Luparello, Grazia; Ferreira Natal Da Luz, Pedro Hugo; Maevskaya, Alla; Mager, Magnus; Mahajan, Sanjay; Mahmood, Sohail Musa; Maire, Antonin; Majka, Richard Daniel; Malaev, Mikhail; Maldonado Cervantes, Ivonne Alicia; Malinina, Liudmila; Mal'Kevich, Dmitry; Malzacher, Peter; Mamonov, Alexander; Manko, Vladislav; Manso, Franck; Manzari, Vito; Marchisone, Massimiliano; Mares, Jiri; Margagliotti, Giacomo Vito; Margotti, Anselmo; Margutti, Jacopo; Marin, Ana Maria; Markert, Christina; Marquard, Marco; Martin, Nicole Alice; Martin Blanco, Javier; Martinengo, Paolo; Martinez Hernandez, Mario Ivan; Martinez-Garcia, Gines; Martinez Pedreira, Miguel; Martynov, Yevgen; Mas, Alexis Jean-Michel; Masciocchi, Silvia; Masera, Massimo; Masoni, Alberto; Massacrier, Laure Marie; Mastroserio, Annalisa; Masui, Hiroshi; Matyja, Adam Tomasz; Mayer, Christoph; Mazer, Joel Anthony; Mazzoni, Alessandra Maria; Mcdonald, Daniel; Meddi, Franco; Melikyan, Yuri; Menchaca-Rocha, Arturo Alejandro; Meninno, Elisa; Mercado-Perez, Jorge; Meres, Michal; Miake, Yasuo; Mieskolainen, Matti Mikael; Mikhaylov, Konstantin; Milano, Leonardo; Milosevic, Jovan; Minervini, Lazzaro Manlio; Mischke, Andre; Mishra, Aditya Nath; Miskowiec, Dariusz Czeslaw; Mitra, Jubin; Mitu, Ciprian Mihai; Mohammadi, Naghmeh; Mohanty, Bedangadas; Molnar, Levente; Montano Zetina, Luis Manuel; Montes Prado, Esther; Morando, Maurizio; Moreira De Godoy, Denise Aparecida; Moretto, Sandra; Morreale, Astrid; Morsch, Andreas; Muccifora, Valeria; Mudnic, Eugen; Muhlheim, Daniel Michael; Muhuri, Sanjib; Mukherjee, Maitreyee; Mulligan, James Declan; Gameiro Munhoz, Marcelo; Murray, Sean; Musa, Luciano; Musinsky, Jan; Nandi, Basanta Kumar; Nania, Rosario; Nappi, Eugenio; Naru, Muhammad Umair; Nattrass, Christine; Nayak, Kishora; Nayak, Tapan Kumar; Nazarenko, Sergey; Nedosekin, Alexander; Nellen, Lukas; Ng, Fabian; Nicassio, Maria; Niculescu, Mihai; Niedziela, Jeremi; Nielsen, Borge Svane; Nikolaev, Sergey; Nikulin, Sergey; Nikulin, Vladimir; Noferini, Francesco; Nomokonov, Petr; Nooren, Gerardus; Cabanillas Noris, Juan Carlos; Norman, Jaime; Nyanin, Alexander; Nystrand, Joakim Ingemar; Oeschler, Helmut Oskar; Oh, Saehanseul; Oh, Sun Kun; Ohlson, Alice Elisabeth; Okatan, Ali; Okubo, Tsubasa; Olah, Laszlo; Oleniacz, Janusz; Oliveira Da Silva, Antonio Carlos; Oliver, Michael Henry; Onderwaater, Jacobus; Oppedisano, Chiara; Orava, Risto; Ortiz Velasquez, Antonio; Oskarsson, Anders Nils Erik; Otwinowski, Jacek Tomasz; Oyama, Ken; Ozdemir, Mahmut; Pachmayer, Yvonne Chiara; Pagano, Paola; Paic, Guy; Pajares Vales, Carlos; Pal, Susanta Kumar; Pan, Jinjin; Pandey, Ashutosh Kumar; Pant, Divyash; Papcun, Peter; Papikyan, Vardanush; Pappalardo, Giuseppe; Pareek, Pooja; Park, Woojin; Parmar, Sonia; Passfeld, Annika; Paticchio, Vincenzo; Patra, Rajendra Nath; Paul, Biswarup; Peitzmann, Thomas; Pereira Da Costa, Hugo Denis Antonio; Pereira De Oliveira Filho, Elienos; Peresunko, Dmitry Yurevich; Perez Lara, Carlos Eugenio; Perez Lezama, Edgar; Peskov, Vladimir; Pestov, Yury; Petracek, Vojtech; Petrov, Viacheslav; Petrovici, Mihai; Petta, Catia; Piano, Stefano; Pikna, Miroslav; Pillot, Philippe; Pinazza, Ombretta; Pinsky, Lawrence; Piyarathna, Danthasinghe; Ploskon, Mateusz Andrzej; Planinic, Mirko; Pluta, Jan Marian; Pochybova, Sona; Podesta Lerma, Pedro Luis Manuel; Poghosyan, Martin; Polishchuk, Boris; Poljak, Nikola; Poonsawat, Wanchaloem; Pop, Amalia; Porteboeuf, Sarah Julie; Porter, R Jefferson; Pospisil, Jan; Prasad, Sidharth Kumar; Preghenella, Roberto; Prino, Francesco; Pruneau, Claude Andre; Pshenichnov, Igor; Puccio, Maximiliano; Puddu, Giovanna; Pujahari, Prabhat Ranjan; Punin, Valery; Putschke, Jorn Henning; Qvigstad, Henrik; Rachevski, Alexandre; Raha, Sibaji; Rajput, Sonia; Rak, Jan; Rakotozafindrabe, Andry Malala; Ramello, Luciano; Raniwala, Rashmi; Raniwala, Sudhir; Rasanen, Sami Sakari; Rascanu, Bogdan Theodor; Rathee, Deepika; Read, Kenneth Francis; Real, Jean-Sebastien; Redlich, Krzysztof; Reed, Rosi Jan; Rehman, Attiq Ur; Reichelt, Patrick Simon; Reidt, Felix; Ren, Xiaowen; Renfordt, Rainer Arno Ernst; Reolon, Anna Rita; Reshetin, Andrey; Rettig, Felix Vincenz; Revol, Jean-Pierre; Reygers, Klaus Johannes; Riabov, Viktor; Ricci, Renato Angelo; Richert, Tuva Ora Herenui; Richter, Matthias Rudolph; Riedler, Petra; Riegler, Werner; Riggi, Francesco; Ristea, Catalin-Lucian; Rivetti, Angelo; Rocco, Elena; Rodriguez Cahuantzi, Mario; Rodriguez Manso, Alis; Roeed, Ketil; Rogochaya, Elena; Rohr, David Michael; Roehrich, Dieter; Romita, Rosa; Ronchetti, Federico; Ronflette, Lucile; Rosnet, Philippe; Rossi, Andrea; Roukoutakis, Filimon; Roy, Ankhi; Roy, Christelle Sophie; Roy, Pradip Kumar; Rubio Montero, Antonio Juan; Rui, Rinaldo; Russo, Riccardo; Ryabinkin, Evgeny; Ryabov, Yury; Rybicki, Andrzej; Sadovskiy, Sergey; Safarik, Karel; Sahlmuller, Baldo; Sahoo, Pragati; Sahoo, Raghunath; Sahoo, Sarita; Sahu, Pradip Kumar; Saini, Jogender; Sakai, Shingo; Saleh, Mohammad Ahmad; Salgado Lopez, Carlos Alberto; Salzwedel, Jai Samuel Nielsen; Sambyal, Sanjeev Singh; Samsonov, Vladimir; Sanchez Castro, Xitzel; Sandor, Ladislav; Sandoval, Andres; Sano, Masato; Sarkar, Debojit; Scapparone, Eugenio; Scarlassara, Fernando; Scharenberg, Rolf Paul; Schiaua, Claudiu Cornel; Schicker, Rainer Martin; Schmidt, Christian Joachim; Schmidt, Hans Rudolf; Schuchmann, Simone; Schukraft, Jurgen; Schulc, Martin; Schuster, Tim Robin; Schutz, Yves Roland; Schwarz, Kilian Eberhard; Schweda, Kai Oliver; Scioli, Gilda; Scomparin, Enrico; Scott, Rebecca Michelle; Seger, Janet Elizabeth; Sekiguchi, Yuko; Sekihata, Daiki; Selyuzhenkov, Ilya; Senosi, Kgotlaesele; Seo, Jeewon; Serradilla Rodriguez, Eulogio; Sevcenco, Adrian; Shabanov, Arseniy; Shabetai, Alexandre; Shadura, Oksana; Shahoyan, Ruben; Shangaraev, Artem; Sharma, Ankita; Sharma, Mona; Sharma, Monika; Sharma, Natasha; Shigaki, Kenta; Shtejer Diaz, Katherin; Sibiryak, Yury; Siddhanta, Sabyasachi; Sielewicz, Krzysztof Marek; Siemiarczuk, Teodor; Silvermyr, David Olle Rickard; Silvestre, Catherine Micaela; Simatovic, Goran; Simonetti, Giuseppe; Singaraju, Rama Narayana; Singh, Ranbir; Singha, Subhash; Singhal, Vikas; Sinha, Bikash; Sarkar - Sinha, Tinku; Sitar, Branislav; Sitta, Mario; Skaali, Bernhard; Slupecki, Maciej; Smirnov, Nikolai; Snellings, Raimond; Snellman, Tomas Wilhelm; Soegaard, Carsten; Soltz, Ron Ariel; Song, Jihye; Song, Myunggeun; Song, Zixuan; Soramel, Francesca; Sorensen, Soren Pontoppidan; Spacek, Michal; Spiriti, Eleuterio; Sputowska, Iwona Anna; Spyropoulou-Stassinaki, Martha; Srivastava, Brijesh Kumar; Stachel, Johanna; Stan, Ionel; Stefanek, Grzegorz; Steinpreis, Matthew Donald; Stenlund, Evert Anders; Steyn, Gideon Francois; Stiller, Johannes Hendrik; Stocco, Diego; Strmen, Peter; Alarcon Do Passo Suaide, Alexandre; Sugitate, Toru; Suire, Christophe Pierre; Suleymanov, Mais Kazim Oglu; Sultanov, Rishat; Sumbera, Michal; Symons, Timothy; Szabo, Alexander; Szanto De Toledo, Alejandro; Szarka, Imrich; Szczepankiewicz, Adam; Szymanski, Maciej Pawel; Takahashi, Jun; Tambave, Ganesh Jagannath; Tanaka, Naoto; Tangaro, Marco-Antonio; Tapia Takaki, Daniel Jesus; Tarantola Peloni, Attilio; Tarhini, Mohamad; Tariq, Mohammad; Tarzila, Madalina-Gabriela; Tauro, Arturo; Tejeda Munoz, Guillermo; Telesca, Adriana; Terasaki, Kohei; Terrevoli, Cristina; Teyssier, Boris; Thaeder, Jochen Mathias; Thomas, Deepa; Tieulent, Raphael Noel; Timmins, Anthony Robert; Toia, Alberica; Trogolo, Stefano; Trubnikov, Victor; Trzaska, Wladyslaw Henryk; Tsuji, Tomoya; Tumkin, Alexandr; Turrisi, Rosario; Tveter, Trine Spedstad; Ullaland, Kjetil; Uras, Antonio; Usai, Gianluca; Utrobicic, Antonija; Vajzer, Michal; Vala, Martin; Valencia Palomo, Lizardo; Vallero, Sara; Van Der Maarel, Jasper; Van Hoorne, Jacobus Willem; Van Leeuwen, Marco; Vanat, Tomas; Vande Vyvre, Pierre; Varga, Dezso; Vargas Trevino, Aurora Diozcora; Vargyas, Marton; Varma, Raghava; Vasileiou, Maria; Vasiliev, Andrey; Vauthier, Astrid; Vechernin, Vladimir; Veen, Annelies Marianne; Veldhoen, Misha; Velure, Arild; Venaruzzo, Massimo; Vercellin, Ermanno; Vergara Limon, Sergio; Vernet, Renaud; Verweij, Marta; Vickovic, Linda; Viesti, Giuseppe; Viinikainen, Jussi Samuli; Vilakazi, Zabulon; Villalobos Baillie, Orlando; Vinogradov, Alexander; Vinogradov, Leonid; Vinogradov, Yury; Virgili, Tiziano; Vislavicius, Vytautas; Viyogi, Yogendra; Vodopyanov, Alexander; Volkl, Martin Andreas; Voloshin, Kirill; Voloshin, Sergey; Volpe, Giacomo; Von Haller, Barthelemy; Vorobyev, Ivan; Vranic, Danilo; Vrlakova, Janka; Vulpescu, Bogdan; Vyushin, Alexey; Wagner, Boris; Wagner, Jan; Wang, Hongkai; Wang, Mengliang; Wang, Yifei; Watanabe, Daisuke; Watanabe, Yosuke; Weber, Michael; Weber, Steffen Georg; Wessels, Johannes Peter; Westerhoff, Uwe; Wiechula, Jens; Wikne, Jon; Wilde, Martin Rudolf; Wilk, Grzegorz Andrzej; Wilkinson, Jeremy John; Williams, Crispin; Windelband, Bernd Stefan; Winn, Michael Andreas; Yaldo, Chris G; Yang, Hongyan; Yang, Ping; Yano, Satoshi; Yin, Zhongbao; Yokoyama, Hiroki; Yoo, In-Kwon; Yurchenko, Volodymyr; Yushmanov, Igor; Zaborowska, Anna; Zaccolo, Valentina; Zaman, Ali; Zampolli, Chiara; Correia Zanoli, Henrique Jose; Zaporozhets, Sergey; Zardoshti, Nima; Zarochentsev, Andrey; Zavada, Petr; Zavyalov, Nikolay; Zbroszczyk, Hanna Paulina; Zgura, Sorin Ion; Zhalov, Mikhail; Zhang, Haitao; Zhang, Xiaoming; Zhang, Yonghong; Zhao, Chengxin; Zhigareva, Natalia; Zhou, Daicui; Zhou, You; Zhou, Zhuo; Zhu, Hongsheng; Zhu, Jianhui; Zhu, Xiangrong; Zichichi, Antonino; Zimmermann, Alice; Zimmermann, Markus Bernhard; Zinovjev, Gennady; Zyzak, Maksym

    2016-01-01

    Transverse momentum ($p_{\\rm{T}}$) spectra of pions, kaons, and protons up to $p_{\\rm{T}} = 20$ GeV/$c$ have been measured in Pb-Pb collisions at $\\sqrt{s_{\\rm NN}} = 2.76$ TeV using the ALICE detector for six different centrality classes covering 0-80%. The proton-to-pion and the kaon-to-pion ratios both show a distinct peak at $p_{\\rm{T}} \\approx 3$ GeV/$c$ in central Pb-Pb collisions that decreases towards more peripheral collisions. For $p_{\\rm{T}} > 10$ GeV/$c$, the nuclear modification factor is found to be the same for all three particle species in each centrality interval within systematic uncertainties of 10-20%. This suggests there is no direct interplay between the energy loss in the medium and the particle species composition in the hard core of the quenched jet. For $p_{\\rm{T}} < 10$ GeV/$c$, the data provide important constraints for models aimed at describing the transition from soft to hard physics.

  11. Especies leñosas nativas claves para la restauración ecológica del Embalse de Chisacá, Colombia, con base en rasgos importantes de su historia de vida

    Directory of Open Access Journals (Sweden)

    Rodríguez Ramírez Natalia

    2006-12-01

    Full Text Available Se determinaron cinco especies nativas leñosas, como claves para la restauración de plantaciones de Pinus patula
    y Corredor ripario potrerizado del embalse de Chisacá (localidad de Usme, Bogotá, Colombia 3.000-3.250
    msnm; 4°08’59’’ N; 74°17’62’’ W, con base en Rasgos de de Historia de Vida (RHV y otras características de
    especies presentes en estas áreas. Teniendo en cuenta el objetivo del estudio y las características de las áreas
    degradadas se seleccionaron y analizaron 23 rasgos a cada una de las especies evaluadas en los distintos ambientes. En la zona de pinos se estudiaron 23 especies, 21 en el corredor ripario potrerizado y 20 en el Matorral Bajo. Se estableció un sistema de calificación para las posibles respuestas de cada uno de los rasgos según su incidencia en la restauración ecológica de las áreas a restaurar. Posteriormente, se calificaron los resultados de los rasgos de cada una de las especies y se calculó una calificación final de éstas. Se recomiendan como especies claves para la restauración las cinco especies que obtuvieron mayor calificación final. Teniendo en cuenta lo anterior se recomiendan como especies claves para la restauración de la zona de pinos las especies Hesperomeles goudotiana (72,41%, Vallea stipularis (67,82%, Symplocos s theiformis (67,82%, Holodiscus argenteus (65,52%, y Myrcianthes leucoxyla (65,52% y para el corredor ripario potrerizado las especies Hesperomeles goudotiana (75,86%, Brugmansia sanguinea (74,71%, Myrcianthes leucoxyla (68,97%, Berberis goudotii (65,48% y Vallea stipularis (64,37%. La selección de especies claves para la restauración con base en RHV parece ser una metodología adecuada, siempre y cuando la selección de rasgos se haga cuidadosamente, teniendo en cuenta
    los objetivos del estudio y que las especies consideradas se estudien en cada ambiente donde se desarrollen. En
    efecto, se observó que los rasgos responden de

  12. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

  13. Life time of nuclear power plants and new types of reactors; La duree de vie des centrales nucleaires et les nouveaux types de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

  14. Desarrollo de una metodología de simulación de secuencias en accidente en centrales nucleares de agua ligera considerando actuaciones del operador

    OpenAIRE

    Expósito Lorenzo, Antonio

    2006-01-01

    This thesis presents the work carried out to develop a simulation system for nuclear power plants, denominated TRETA / COPMA-III integrated simulator, which allows the simulation of the thermalhydraulic processes that take place in this type of facilities, in normal operation and emergency operation, as well as the control room crew actions related with the management of the emergency situations. The simulation of the thermalhydraulic processes is carried out by means of the TR...

  15. Preparation of the Improved Technical Specifications of Nuclear Almaraz, Asco and Vandellos; Procedimiento de elaboracion de las Especificaciones Tecnicas Mejoradas de las Centrales de Almaraz Asco y Vandellos

    Energy Technology Data Exchange (ETDEWEB)

    Fuente, I.; Mirallas, F.; Garcia, M. D.

    2012-07-01

    In 2010 the Nuclear Almaraz, Asco and Vandellos agreed with the CSN start the transition project to the Improved Plant Technical Specifications (IPTSs), with reference the Rev. 3.1 of NUREG-1431. In April 2012 has been published the Rev. 4.0 of NUREG and have decided to adapt the IPTSs to the content of this new revision. The project for the three plants is developed in parallel, which allows to optimize the process.

  16. Environmental radiological surveillance around nuclear power plants in Argentina

    International Nuclear Information System (INIS)

    During the last five years of operation of Atucha I nuclear power plant (CNA I) and Embalse nuclear power plant (CNE), a field team from the Environmental Radioactivity Division of Nuclear Regulatory Authority (ARN) of Argentina has carried out surveillance programs in the surroundings of these facilities, in order to estimate the radiological impact. The Argentine nuclear power plants use natural uranium as fuel and heavy water as refrigerant and moderator. During normal operation, radionuclides are released to the environment through liquid and gaseous discharges; mainly tritium which is generated from the neutron activation of heavy water deuterium. One of the environmental radioprotection requirements for a nuclear facility licensing is the compliance of the dose limit (1 mSv/year) to the most exposure members of the public (critic group). The authorised annual dose limits established for ARN, to control the release of radioactive effluents are 50 and 100 μSv/year for CNA I and CNE respectively. The surveillance programs carried out around the mentioned nuclear facilities included the radionuclide analysis of H-3, Cs-137, Co-60. I-131 and Sr-90. The matrixes analysed were milk, grass, diet, fish and groundwater, surface and tap water. The results, including the dose assessment, are presented. The measured results of the radionuclides mentioned above were, in general, below the detection limit (except for tritium). The doses estimated for both, liquid and gaseous discharges, varied from 4 to 5 μSv/year for each nuclear power plant, since 1998 to 2002. This implies that the population living in the vicinity of these areas receives no significant exposure. (author)

  17. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production; UPVAPOR: Aplicacion informatica para el analisis de resultados de produccion en Central Nuclear Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-07-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  18. Evolution of Technology Laser Scanner. Implications for use in Nuclear Power and Radioactive Facilities; Evolucion de la Tecnologia Laser Escaner. Implicaciones en uso en Centrales Nucleares e Instalaciones Radioactivas

    Energy Technology Data Exchange (ETDEWEB)

    Sarti Fernandez, F.; Bonet, J.

    2012-07-01

    The main technical factors affecting these teams their actual implementation in nuclear power plants will be analyzed: data acquisition speed, sensitivity, laser power, autonomy, contamination of equipment, radiation effect, etc. In conclusion, the real difference is displayed in the data collection in function of various technologies, embodied in field time, and costs.

  19. Follow-up of the results of the nuclear power plant stress tests and action plan.; Seguimiento de los resultados de las pruebas de resistencia de las centrales nucleares y plan de accion

    Energy Technology Data Exchange (ETDEWEB)

    Mellado Jimenez, I.

    2012-07-01

    The results of the stress tests carried out by the European nuclear power plants in the wake of the Fukushima Daiichi accident, subsequently subjected to peer reviews, have made it possible to identify the measures to be applied to improve safety. Action plans have been put in place to implement these measures within appropriate time frames. (Author)

  20. Domestic nuclear fuels supply: possibility of an independent technology

    International Nuclear Information System (INIS)

    After considering the different energy sources, their consumption and their respective periods of exploitation, technological considerations in the nuclear fuel field are made. The main subject is the Domestic Supply Project of Embalse Fuel (CANDU type). The different aspects which had to be developed during the realization of this project still under progress, and which are fundamental for the command of the technology, are described: 1) Qualification of the produced fuel elements: fuel elements' characteristics; the reactors' operating parameters, and the prototype fuel elements' characteristics; 2) Development of materials and/or suppliers: the obtainment of UO2 and its physical properties are considered, as well as those of Zircaloy-4, the development of suppliers and the respective developments for the obtainment of materials such as beryllium, helium and colloidal graphite; 3) Processes development; the following processes are studied and defined: UO2 pellets fabrication with UO2 granulated powder; beryllium coating under vaccum; and induction brazing of bearing pads and spacers, end cap and end plate resistance welding and stamping of Zircaloy components, graphite-coating of cladding's internal face; 4) Development of special production equipments; automatic equipment for end cap-to-cladding resistance welding among others. The need for a specific program of quality assurance for nuclear fuels supply is emphasized and the basic criteria are established. The IAEA's quality asssurance requirements are also analyzed. (M.E.L.)

  1. Nuclear fragmentation in central collisions: Ni + Au from 32 to 90 A*MeV; Fragmentation dans les collisions centrales du systeme Ni + Au de 32 a 90 A MeV

    Energy Technology Data Exchange (ETDEWEB)

    Bellaize, N

    2000-11-03

    Heavy ion collisions are one of tools for studying nuclear system far away from its equilibrium state. This work concerns the most violent collisions in the Ni + Au system for incident energies ranging from 32 up to 90 AMeV. These events were detected with the multidetector INDRA and selected by the Principal Component Analysis (multidimensional analysis). This method classifies the events according their detection features and their degree of dissipation. We observed two deexcitation mechanisms: a fusion/fission - evaporation process and a multifragmentation process. Those two coexist from 32 to 52 AMeV whereas only one subsists at 90 AMeV. For those two mechanisms, an component was observed which seems to be linked to the initial phase of the reaction. The energy fluctuations of this component leads to variations in the energy deposit which determines the deexcitation of the system. The experimental multifragmentation data of the Ni + Au system (52 and 90 AMeV) were compared to the predictions of a statistical model and to the experimental data of the system Xe + Sn at 50 AMeV (also detected with INDRA). These comparisons show the lack of collective radial energy for fragments (Z{>=}10) in the Ni + Au system, and show that the degree of multifragmentation depends of the thermal excitation energy. Mean kinetic energies of particles and lights fragments (Z{>=}10) are larger in the Ni + Au system than the Xe + Sn system. This observation shows that these particles are more sensitive to the entrance channel for an asymmetric system than for a symmetric system (for the same number of nucleons). (author)

  2. Study of shear wave attenuation field variations in Central Asia region using records of nuclear and chemical explosions at the Semipalatinsk Test Site

    International Nuclear Information System (INIS)

    The temporal variations of amplitude ratio of Lg and Pg, Lg and P waves were studied using the 1964-2000 records of more than 200 underground nuclear and chemical calibration explosions obtained at the Northern Tien Shan TLG station, KURK station (Eastern Kazakhstan), BRVK (Kokchetav Massif), GRM (Southern Tien Shan) located at epicentral distances of 77-1400 km. Variations in this parameter with time are shown to be significantly different for different paths. The spatial-temporal variations of the seismic wave attenuation field are presumably associated with the ascent of juvenile fluids through large deep faults. (author)

  3. Determination of the changes of water storage in an aridisol at the central Bolivian highlands with the help of nuclear techniques

    International Nuclear Information System (INIS)

    The results of this kind of research, the first one conducted in Bolivia with the help of nuclear techniques for three years, allow to demonstrate that the soil classified as ''typical paleargid'' or ''aridisol'' with loam-clay sandy texture, has a very varied water storage until reaching a depth of 76 cm. This strictly depends on the variable rain fall in different seasons and the strong evaporation rate during the cloudless winter at 4000 m of altitude. The growing period of the Andean cultivated plants coincides with the increasing soil water content from September to January and the harvest period with the decrease of water storage from March to May

  4. The deconstruction of EDF nuclear power plants - Information note September 2011; La deconstruction des centrales nucleaires EDF - Note d'information Septembre 2011

    Energy Technology Data Exchange (ETDEWEB)

    Tran, Lionel

    2012-01-10

    As nine nuclear reactors are being deconstructed, this document outlines EDF commitment in this deconstruction, and the fact that this deconstruction is a long process which comprises several phases (stopping the reactor, partial and total dismantling). It presents the CIDEN (Deconstruction and Environment Engineering Centre), an expertise centre specialised in plant deconstruction. It briefly addresses the issue of deconstruction wastes: there are different types of wastes (conventional wastes and wastes with different levels of radioactivity), and different associated storage sites. The document highlights the importance of public, personnel and environment protection for these operations, and evokes the financial issue. Finally, the industrial project ICEDA (packaging and warehousing installation for activated wastes) is presented

  5. Update of foundation design modifications of data cables and piping in nuclear power plants in operation; Actualizacion de modificaciones de sieno de bases de datos de cables y conducciones en centrales nucleares en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Perez Pereira, J.

    2013-07-01

    The scope of this application is the manage the life cycle of cables electrical and pipes of cables in Trillo NPP. The application is integrated in a configuration Control system, so both cables and conduits become elements of configuration and management of life and history associated with the of the relevant modifying documents. The guarantees criteria of physical separation of wires for jobs and for independent networks designed according to the redundancy of the Central System.

  6. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  7. Revision of by-laws about effluents of EdF's nuclear power plants; Revision des arretes de rejets des centrales nucleaires d'EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, {sup 14}C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  8. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs

  9. Analysis of the financial task generated by the construction of a nuclear power plant in Mexico; Analisis de la carga financiera generada por la construccion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, G.; Ramirez, R.; Palacios, J.; Delfin, A., E-mail: gustavo.alonso@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-11-15

    The construction of new nuclear reactors requires of a high investment making them intensive projects in capital and that require as minimum of 5 years for its construction. The financial task that represents for the electric company is of vital importance, since in the case of privates in other countries prevents them of entering in this type of projects if they do not have its Government support. In the case of Mexico, being an electric company integrated vertically can have financing to carry out this investment type. In this study is analyzed the construction viability of new nuclear reactors in Mexico based on the financial task that represents for the Electric Company its construction. (Author)

  10. New technologies of information treatment in the ERP of the Almaraz and Trillo nuclear power plants; Nuevas tecnologias de tratamiento de la informacion en el ERP de las centrales nucleares de Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Lopez-Suevos, C.; Gonzalez Crego, E.

    2013-03-01

    The Almaraz and Trillo Nuclear Power Plants are equipped with an Integrated Operation Management System (SIGE), which covers practically all of their transactional and management needs in all areas, with the exception of some specific engineering and simulation tools. In recent years, applications based on new computer technologies have been developed and integrated into the SIGE, including a Maintenance Dashboard, an Admissions Office ant the use of bar code readers, all of which are described in this article. (Author)

  11. CAGE: A standard design application to nuclear power plants of Cofrentes, Almaraz and Trillo; CAGE: Un diseno estandar de aplicacion a las centrales nucleares de Cofrentes, Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Cubian Martinez, B.; Gomez Gomez, M.; Zornoza Garcia-Andrade, J.; Turrion Lopez, F.; Barrio, M. A. del; Cobos Perabad, A.; Garcia-Serrano, J. L.

    2016-08-01

    Design, engineering, supply, construction, assembly, supervision and quality control, construction management and commissioning of Alternative Emergency Management Centres (CAGES) of nuclear power plants Cofrentes (CNC), Almaraz (CNA) and Trillo (CNT) were awarded in the first half of 2014 to Iberdrola Engineering and Construction (IIC). After obtaining the required building permits issued by municipalities, following the delivery of the corresponding, basic project and execution, in January 2015, began civil works at CNA, CNT and in February of this year in CNC. (Author)

  12. Instruction by virtual reality to operation and security of a nuclear power plant of IV generation; Instruccion por realidad virtual a la operacion y seguridad de una central nuclear de generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Neri O, J. C.; Baltasar M, J.; Valle H, J. [Facultad de Ingenieria, Division de Estudios de Posgrado, Campus Morelos, UNAM, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)], e-mail: neriunam@ieee.org

    2009-10-15

    The purpose of LaNuVi project which is developing in the Engineering Faculty of National Autonomous University of Mexico, to have a virtual laboratory of nuclear reactors as tool of multidisciplinary education at basic and advanced levels in nuclear engineering area, involves training resources in audio visual and interactive form that allow to form a comprehension more realistic of operation of different systems and components. In this work is proposed to use educational resources, as the employees in the U.S. Army and in some centers of advanced education of medicine, where have been come proving concepts like projected reality, increased reality, tele transparency and others that present big benefits to learning-education process. The proposal here is to include the resource knew as serious game based learning. The focal point of stage that is presented is of a nuclear reactor PBMR like desalination and generator of controlled alternating energy and efficient that should put on in operation to allow the subsistence of a community in a desolated region of beginning second quarter of X XI century. For this purpose the designs are initiated and programmed several subsystems that allow the three-dimensional modeling of main components of a PBMR as well as of surrounding facilities. The obtained results and reaches of this design are presented. The product is in tests for a first version and it is hope to achieve a free and integral resource of national distribution for different cultural groups, interested in this type of advanced technology. (Author)

  13. The central repeat domain 1 of Kaposi's sarcoma-associated herpesvirus (KSHV) latency associated-nuclear antigen 1 (LANA1) prevents cis MHC class I peptide presentation

    International Nuclear Information System (INIS)

    KSHV LANA1, a latent protein expressed during chronic infection to maintain a viral genome, inhibits major histocompatibility complex class I (MHC I) peptide presentation in cis as a means of immune evasion. Through deletional cloning, we localized this function to the LANA1 central repeat 1 (CR1) subregion. Other CR subregions retard LANA1 translation and proteasomal processing but do not markedly inhibit LANA1 peptide processing by MHC I. Inhibition of proteasomal processing ablates LANA1 peptide presentation. Direct expression of LANA1 within the endoplasmic reticulum (ER) overcomes CR1 inhibition suggesting that CR1 acts prior to translocation of cytoplasmic peptides into the ER. By physically separating CR1 from other subdomains, we show that LANA1 evades MHC I peptide processing by a mechanism distinct from other herpesviruses including Epstein-Barr virus (EBV). Although LANA1 and EBV EBNA1 are functionally similar, they appear to use different mechanisms to evade host cytotoxic T lymphocyte surveillance.

  14. Monitoring systems online of oil for transformers of nuclear power plants; Sistemas de monitorizacion online del aceite para transformadores de potencia de Centrales

    Energy Technology Data Exchange (ETDEWEB)

    Sarandeses, S.

    2014-07-01

    The nuclear power plants are showing their concern due to the existence of recent failures related to the bulky transformers of power. These transformers are not security, but are important for the production of power as its failure can cause transient on the floor, reactor scram or shooting, that can cause interruptions in the production of energy or might force us to reduce the power of production The analysis of gases dissolved in transformer oil is recognized as a trial key to identify a submerged transformer failure in oil. With this analysis it is not possible to ensure that there is no damage in the transformer, but the probability of risk of this type of failure can be reduced. The industry recommended to equip the new large power transformers with oil online monitoring systems and in some cases also be It recommended its use in existing transformers. (Author)

  15. The sanitary officer: first aid coordinator on EDF nuclear power plant; Le delegue sanitaire: coordonnateur des secouristes en centrale nucleaire a E.D.F

    Energy Technology Data Exchange (ETDEWEB)

    Masson, A

    2000-07-01

    The internal organisation for first aid to the injured in case of an accident on E.D.F. nuclear power plant calls for the immediate assistance of a first aid team, consisting of five workers, under the direction of a principal first aid officer; one of the first aid workers, the sanitary officer who instructs the first aid workers intervention awaiting the arrival of an external medical. When the 'Sanitary on-site Emergency Plan' was up' dated, twenty medical doctors and seventy members of staff from five different sites were questioned as to the function of the sanitary officer. The conclusions revealed a notable difference of training amongst the different sites, and concerning first aid organisation, difference of priority of actions, extent of their participation once the medical team arrives and their participation in case of decontamination treatment. The medical doctors and staff lay a particular stress on importance of defining on a national scale the limits of role and responsibilities of the sanitary officer and establish a more specific training in this field, consequently motivating commitment and professionalism involvement. There is a great difference between the training and coaching of the first aid assistance and fire protection teams. To conclude, we propose that the first aid officer be known as first aid coordinator and the qualification of 'Certificat de Formation aux Premiers Secours en Equipe' in compliance with the current legislation together with a specific nuclear module and they should undergo regular on-site drills. (author)

  16. Sensing remote nuclear spins

    OpenAIRE

    Zhao, Nan; Honert, Jan; Schmid, Berhard; Isoya, Junichi; Markham, Mathew; Twitchen, Daniel; Jelezko, Fedor; Liu, Ren-Bao; Fedder, Helmut; Wrachtrup, Jörg

    2012-01-01

    Sensing single nuclear spins is a central challenge in magnetic resonance based imaging techniques. Although different methods and especially diamond defect based sensing and imaging techniques in principle have shown sufficient sensitivity, signals from single nuclear spins are usually too weak to be distinguished from background noise. Here, we present the detection and identification of remote single C-13 nuclear spins embedded in nuclear spin baths surrounding a single electron spins of a...

  17. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico. Parte 2

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. de L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

  18. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

  19. Regulator process for the authorization of an amendment to the operation license of a nuclear power plant in Mexico; Proceso regulador para la autorizacion de una enmienda a la licencia de operacion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Perez, R.; Espinosa V, J.M.; Salgado, J.R.; Mamani, Y.R. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2005-07-01

    The regulator process by which an authorization is granted from an amendment to the License of Operation of a nuclear power station in Mexico is described. It makes an appointment the effective legal mark, the technical characteristics of the modification, the evaluation process and deposition upon oath of tests and finally the elaboration of the Safety report and the Technical Verdict that is a correspondent for the regulator organism to the Secretary of Energy, the one that in turn is the responsible of granting the amendment the License just as it establishes it the Law. (Author)

  20. Modification and updating of documentation in equipment of panels of control room in nuclear power plant operation; Modificacion y actualizacion de documentacion en aparatos de paneles de sala de control en una central nuclear en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Agudo Montero, L.

    2013-07-01

    The present paper describes a case very unique specific design of interactive 2D-CAD application, that has been developed by Empresarios Agrupados as engineering support to the nuclear power plants, aware of the problem that exists with the documentation of the instruments and devices that are on the panels of Control room, and that only have the documentation generated in its day by the manufacturers of these panels. To this end, an application (application DOPAB) has been developed to help solve the problem of management, design and modification of wiring and wiring devices existing in the Control room control panels.

  1. Fenología reproductiva y dispersión de semillas del arbusto altoandino Monnina salicifolia R&P (Polygalaceae en el embalse San Rafael, La Calera, Cundinamarca, Colombia

    Directory of Open Access Journals (Sweden)

    Vargas Ríos Orlando

    2004-12-01

    Full Text Available Monnina salicifolia R&P (Polygalaceae se reporta como una de las tres especies más abundantes y representativas en la dispersión de semillas por aves en la zona del Embalse San Rafael La Calera. Es una especie que presenta fenofases reproductivas de forma simultánea y siendo ampliamente consumida por aves, por lo que se le podría atribuir como especie clave en la regeneración de áreas alteradas, y considerada como pionera en los procesos de sucesión. Entre septiembre de 2001 y agosto de 2002, se determinó la estacionalidad de las fases reproductivas, la producción de flores y frutos; y la disponibilidad de frutos maduros de 20 individuos entre 1,5 y 2 m de altura, mediante conteos directos de las estructuras presentes en cada individuo, quincenalmente. Así mismo, se evaluó la dispersión regional de semillas mediante la utilización de perchas artificiales, como última etapa en el ciclo de vida de Monnina salicifolia. Monnina salicifolia presentó floración y fructificación durante todo el año de muestreo y de forma continua. Sin embargo, la mayor producción floral coincidió con la estación seca, mientras que la fructificación aumentó su producción durante la estación de lluvias. Patrón observado generalmente en zonas tropicales y característico de algunas especies pioneras. Aparentemente los factores climáticos que se tuvieron en cuenta en este estudio no actuaron como señales disparadoras en la producción de flores y frutos, quizás debido a la variación poco significativa de estos durante el período de muestreo. Con respecto a la dispersión regional de semillas de Monnina salicifolia, fue constante durante los 12 meses de muestreo, lo cual pudo favorecerse por la fructificación constante de la planta. El mayor número de semillas encontradas bajo las perchas, coincidió con la época seca, época de menor disponibilidad de frutos maduros a escala local, lo cual puede deberse a que la dispersión ocurre a escala

  2. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde; Cuestionamientos al aumento de potencia de los reactores de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B., E-mail: salasmarb@yahoo.com.mx [UNAM, Facultad de Ciencias, Departamento de Fisica, Circuito exterior s/n, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2014-08-15

    The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

  3. Economic analysis of extended cycles in the Laguna Verde nuclear power plant; Analisis economico de ciclos de extendidos en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: hermilo@correo.unam.mx

    2004-07-01

    The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

  4. Sampling and description of the resins stockpiles in the Kozloduy Nuclear Power Plant large tanks; Muestreo y caracterizacion de resinas almacenadas en tanques de grandes dimensiones de la Central Nuclear de Kozloduy (Bulgaria)

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Fernandez, L.; Gonzalez Gandal, R.; Herrera, J. A.

    2012-11-01

    The consortium ENSA-Gas Natural Fenosa Engineering has a contract with Kozloduy Nuclear Power Plant (KNPP) for the retrieval and conditioning of the resins, which were generated during the operation of the plant. The project deals with resins characterization for which its necessary to define a proper methodology that fulfills the Bulgarian authorities requirements. Also, it will be included the design, fabrication, supply and installation of the required equipment to carry out the sampling and measurements of the resins, updating the facilities and the specific training of the personnel in order to perform by themselves every activities. This article reflects how the consortium will deal with the management of this damaging project, which involves a wide range of activities, including the management of each implicated are of both KNPP and external organizations. (Author)

  5. Project development: testing of heat exchange of cooling system and cleaning fuel pool of NPP Cofrentes; Desarrollo del proyecto Prueba de Intercambio Termico del Sistema de Enfriamiento y Limpieza de la Piscina de combustible (G41) de Central Nuclear de Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, B.; Vaquer, J. I.; Mota, M.; Reyes, S.; Palomo, M.; Ruiz, G.; Rebollo, C.

    2012-07-01

    Heat exchanger tests were carried out and data in the thermodynamic models developed, turned and can verify that the efficiency of heat exchange met the requirements. The work concluded complying at all times with the technical specifications and quality proposals by the Department of engineering at the Central Nuclear de Cofrentes.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

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

  12. Chinese nuclear insurance and Chinese nuclear insurance pool

    International Nuclear Information System (INIS)

    Chinese Nuclear Insurance Started with Daya Bay Nuclear Power Station, PICC issued the insurance policy. Nuclear insurance cooperation between Chinese and international pool's organizations was set up in 1989. In 1996, the Chinese Nuclear Insurance Pool was prepared. The Chinese Nuclear Insurance Pool was approved by The Chinese Insurance Regulatory Committee in May of 1999. The principal aim is to centralize maximum the insurance capacity for nuclear insurance from local individual insurers and to strengthen the reinsurance relations with international insurance pools so as to provide the high quality insurance service for Chinese nuclear industry. The Member Company of Chinese Nuclear Pool and its roles are introduced in this article

  13. Europa central

    Directory of Open Access Journals (Sweden)

    Karel BARTOSEK

    2010-02-01

    Full Text Available La investigación francesa continúa interesándose por Europa Central. Desde luego, hay límites a este interés en el ambiente general de mi nueva patria: en la ignorancia, producto del largo desinterés de Francia por este espacio después de la Segunda Guerra Mundial, y en el comportamiento y la reflexión de la clase política y de los medios de comunicación (una anécdota para ilustrar este ambiente: durante la preparación de nuestro coloquio «Refugiados e inmigrantes de Europa Central en el movimiento antifascista y la Resistencia en Francia, 1933-1945», celebrado en París en octubre de 1986, el problema de la definición fue planteado concreta y «prácticamente». ¡Y hubo entonces un historiador eminente, para quién Alemania no formaría parte de Europa Central!.

  14. Use of nuclear and related techniques in studies of agroecological effects resulting from the use of persistent pesticides in Central America. Report of a final research co-ordination meeting

    International Nuclear Information System (INIS)

    The use of pesticides for the control of pests of agriculture and vectors of human and animal diseases in the countries of Central America is the highest per capita and one of the most intense in the world. There are reports of acute toxicity and chronic effects among farm workers. There are also reports that pesticide residues in food frequently exceed the Codex Alimentarius Commission's maximum residue levels (MRLs) and shipments of foodstuffs have been rejected by importing countries due to the presence of excessive residues of pesticides. Pesticides are also implicated in the contamination of continental and coastal waters. The indiscriminate use of pesticides would be expected to also aggravate pest problems by adversely affecting populations of beneficial arthropods and causing the development of resistance in pest populations. The Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture initiated a co-ordinated research project in 1992 to generate information on residues of pesticides in the environment, their persistence under local conditions and effect on local species of beneficial arthropods in agricultural and adjacent areas in the countries of Central America. Such information could be used in the implementation of legislation to control the distribution and use of pesticides and the development and application of integrated pest management programmes. Scientists from Costa Rica, Guatemala, Honduras, Nicaragua, Panama and the United States of America participated in this project. This TECDOC reports on the accomplishments of the project and includes the papers presented at the final Research Co-ordination Meeting held in Panama City, Panama, 20-24 April 1998

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

  16. Corrosion in nuclear power plants and it implication in the leak before break criteria; Corrosion en centrales nucleares y su implicacion en el criterio de fuga antes de ruptura

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

    The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)

  17. INTERNET and information about nuclear sciences. The world wide web virtual library: nuclear sciences

    International Nuclear Information System (INIS)

    In this work author proposes to constitute new virtual library which should centralize the information from nuclear disciplines on the INTERNET, in order to them to give first and foremost the connection on the most important links in set nuclear sciences. The author has entitled this new virtual library The World Wide Web Library: Nuclear Sciences. By constitution of this virtual library next basic principles were chosen: home pages of international organizations important from point of view of nuclear disciplines; home pages of the National Nuclear Commissions and governments; home pages of nuclear scientific societies; web-pages specialized on nuclear problematic, in general; periodical tables of elements and isotopes; web-pages aimed on Chernobyl crash and consequences; web-pages with antinuclear aim. Now continue the links grouped on web-pages according to single nuclear areas: nuclear arsenals; nuclear astrophysics; nuclear aspects of biology (radiobiology); nuclear chemistry; nuclear company; nuclear data centres; nuclear energy; nuclear energy, environmental aspects of (radioecology); nuclear energy info centres; nuclear engineering; nuclear industries; nuclear magnetic resonance; nuclear material monitoring; nuclear medicine and radiology; nuclear physics; nuclear power (plants); nuclear reactors; nuclear risk; nuclear technologies and defence; nuclear testing; nuclear tourism; nuclear wastes; nuclear wastes. In these single groups web-links will be concentrated into following groups: virtual libraries and specialized servers; science; nuclear societies; nuclear departments of the academic institutes; nuclear research institutes and laboratories; centres, info links

  18. Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde; Estudio de ruido ambiental en una planta BWR como la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Cruz G, M.; Amador C, C., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2013-10-15

    In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

  19. Evaluación del estado de micorrización de Vallea stipularis y Hesperomeles goudotiana (Embalse de Chisaca-Usme y efecto de la aplicación de endomicorrizas en Vallea stipularis

    Directory of Open Access Journals (Sweden)

    Vargas Jesús Orlando

    2006-12-01

    Full Text Available Se evaluó el estado de micorrización de dos especies de importancia para la restauración ecológica del bosque
    alto andino: Vallea stipularis y Hesperomeles goudotiana, presentes en zonas de matorral así como el estado de las
    micorrizas en la zona de potrero, dentro de los predios del embalse de Chisacá. Se procedió a multiplicar los
    hongos encontrados en suelo rizosférico de V. stipularis y de la vegetación de potrero en plantas trampa de
    Brachiaria decumbens, para la obtención de inóculos, con el fin de realizar un ensayo para evaluar el efecto de
    la inoculación de hongos micorrícicos arbusculares comerciales y nativos en plantas propagadas de forma
    sexual de V. stipularis. Se encontró que ambas especies presentan altos niveles de micorrización, posiblemente
    H. goudotiana sea más dependiente de las micorrizas que V. stipularis, ya que éste presentó los mayores porcentajes
    de micorrización y escasa presencia de pelos radiculares. La zona de potrero presentó un bajo número
    de esporas y bajos porcentajes de micorrización radicular, con respecto a lo encontrado en el suelo rizosférico
    de ambas especies presentes en el matorral, esto posiblemente como resultado de todo el proceso de disturbio al que ha estado sometida la zona, esta situación, puede estar representando una barrera en el establecimiento de especies nativas con alta dependencia micorrícica en la zona de potrero. En el ensayo de aplicación de endomicorrizas en V. Stipularis, se encontró un mejor desarrollo y menor ataque por ácaros y fitopatógenos en las plantas inoculadas con respecto al control, aunque la incidencia de mosca blanca fue menor en las plantas no inoculadas. El tratamiento en el que se empleo el inoculo comercial resulto ser el mejor ya que en
    éste se obtuvo mayor índice de respuesta micorrícica, así mismo se pudo establecer la existencia de una correlación
    positiva entre el

  20. Nuclear shell theory

    CERN Document Server

    de-Shalit, Amos; Massey, H S W

    1963-01-01

    Nuclear Shell Theory is a comprehensive textbook dealing with modern methods of the nuclear shell model. This book deals with the mathematical theory of a system of Fermions in a central field. It is divided into three parts. Part I discusses the single particle shell model. The second part focuses on the tensor algebra, two-particle systems. The last part covers three or more particle systems. Chapters on wave functions in a central field, tensor fields, and the m-Scheme are also presented. Physicists, graduate students, and teachers of nuclear physics will find the book invaluable.

  1. The nuclear power decisions

    International Nuclear Information System (INIS)

    Nuclear power has now become highly controversial and there is violent disagreement about how far this technology can and should contribute to the Western energy economy. More so than any other energy resource, nuclear power has the capacity to provide much of our energy needs but the risk is now seen to be very large indeed. This book discusses the major British decisions in the civil nuclear field, and the way they were made, between 1953 and 1978. That is, it spans the period between the decision to construct Calder Hall - claimed as the world's first nuclear power station - and the Windscale Inquiry - claimed as the world's most thorough study of a nuclear project. For the period up to 1974 this involves a study of the internal processes of British central government - what the author terms 'private' politics to distinguish them from the very 'public' or open politics which have characterised the period since 1974. The private issues include the technical selection of nuclear reactors, the economic arguments about nuclear power and the political clashes between institutions and individuals. The public issues concern nuclear safety and the environment and the rights and opportunities for individuals and groups to protest about nuclear development. The book demonstrates that British civil nuclear power decision making has had many shortcomings and concludes that it was hampered by outdated political and administrative attitudes and machinery and that some of the central issues in the nuclear debate were misunderstood by the decision makers themselves. (author)

  2. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

    Energy Technology Data Exchange (ETDEWEB)

    Andriot, J.; Gaussens, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l

  3. Emission of {sup 14}C by the Almirante Alvaro Alberto Nuclear Power Plant 1 and 2 and their local effects on the environmental levels; Emissao de {sup 14}C pelas unidades 1 e 2 da Central Nuclear Almirante Alvaro Alberto (CNAAA) e seu efeito local nos niveis ambientais

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Cintia Melazo

    2006-07-01

    {sup 14}C is a is a long-lived beta-emitting nuclide (T{sub 1/2} = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable {sup 14}N({sup 14}N(n,p){sup 14}C). Although in a lesser extent, nuclear power plants produce {sup 14}C as well during their routine operation. Since it is converted in {sup 14}CO{sub 2} and mixed throughout the atmosphere, it is incorporated into plant tissues, via photosynthesis process, and hence in food chain. Because of the biological importance of {sup 14}C and long half-life, it is of interest to quantify the amounts released by nuclear industry. The Brazilian nuclear central named Nuclear Central Admiral Alvaro Alberto (CNAAA) has two nuclear reactors of PWR type in operation, Angra I (657 MWe) and Angra II (1350 MWe), and one under construction, Angra III (1309 MWe PWR). The aim of this study was to determine the strength of the sources and the {sup 14}C content in the environment through analyses of air, vegetation and soils taken within 5 km (the influenced area) of CNAAA. The thesis consists of an extensive review about the subject (part one) and of four papers (part two). The first paper is about the determination of {sup 14}C concentrations released by reactors (source strength). For Angra I, a device was developed in order to sample the gaseous effluents and for Angra II, a commercial monitoring system had already been implemented since its initial operation (2001). The {sup 14}C can be emitted as hydrocarbons, CO or CO{sub 2}, depending on the type of reactor. For PWRs, the main chemical form released is hydrocarbons (80 %). The monitoring system of Angra I was planned to determine both CO{sub 2} and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO{sub 2} by using a Pd/Al{sub 2}O{sub 3} catalyst at 450 deg C. The liquid scintillation was the method employed to measure the samples. The second one concerns the atmospheric dispersion of the released

  4. Replacement of flux detectors at Embalse NPP

    International Nuclear Information System (INIS)

    Full text: The work began replacing, in first place, the units with flux mapping detectors only, taking care not to replace detectors of the reactor regulation system and safety systems in order do not have an impairment on the safety systems in case of replacement program's interruption during the first steps of replacements. During the phase of connectors installing in the seventh vertical flux unit (7th VFD) the original Twinax cable was found with a lack of its original properties. The internal conductor insulation was stiffened. For that reason, the internal conductor insulation became very difficult to handle without possible cable damage. Immediately, it was decided to stop the detectors replacement because the general schedule of the outage must delayed by the additional unexpected task of cable replacement. Besides, properly replacement cable was not available at de plant. A series of insulation measurements were made on the detectors cables, including those which were not replaced. A periodical control of insulation resistance measures of detectors and cables was arranged to be carried out during normal operation, until the next outage. In the next Annual Outage the detectors replacement was completed and the PVC cables was replaced by KKK cables with EQ requirements At the present a decision making process must be realized taking into account the Long Term Operation of Plant. (author)

  5. Feedwater heaters functional analysis at Embalse NGS

    International Nuclear Information System (INIS)

    This study is concerned with the analysis or feedwater heaters, to detect actual failure or a bad trend beyond acceptable operating limits. When these situations are identified, preventive or corrective maintenance must be done. 2 tabs., 14 figs

  6. Control rod cluster drop time anomaly Guandong nuclear power station (Daya bay) and Electricite de France nuclear power stations (1450 MWe N4 Series); Anomalie de temps de chute des grappes de controle centrale de guang dong (daya bay) et centrales d`electricite de France (Palier N4-1450 MWE)

    Energy Technology Data Exchange (ETDEWEB)

    Olivera, J.J.; Naury, S.; Tricot, N.; Tran Dai, P.; Gama, J.M.

    1996-12-31

    The anomaly of control rod cluster drop time revealed at Guandong Nuclear Power Station in Daya Bay and in the Chooz B1 pilot unit for the N4 series, led to the replacement of the M1 type control rod cluster guide tubes with 1300 MWe PWR type guide tubes, adapted to the geometry of the Guandong reactors and the 1450 MWe reactors of the N4 series. The comparison of the drop times obtained with the 1300 MWe type control rod cluster guide 1300 MWe type control rod cluster guide tubes gave satisfactory results. These met the safety criterion for N4 series control rod cluster drop times (2.15 under hot shutdown conditions). The drop time tests which will be carried out in middle of and at the end of cycle 1 of Chooz B1 should make it possible to finally validate the solution already successfully implemented at Guandong. However, this anomaly has revealed the limits of representativeness of the experimental test loops with regard to the real reactor configuration. In view of this, it has been deemed necessary to ask Electricite de France to pursue its analysis both on the understanding of the phenomena which led to this anomaly and on the limits of the representativeness of the experimental test loops. (authors).

  7. Nuclear Physics of Neutron Stars

    OpenAIRE

    Piekarewicz, J.

    2009-01-01

    Understanding the equation of state (EOS) of cold nuclear matter, namely, the relation between the pressure and energy density, is a central goal of nuclear physics that cuts across a variety of disciplines. Indeed, the limits of nuclear existence, the collision of heavy ions, the structure of neutron stars, and the dynamics of core-collapse supernova, all depend critically on the equation of state of hadronic matter. In this contribution I will concentrate on the special role that nuclear ph...

  8. CENTRAL EUROPE: Role models

    International Nuclear Information System (INIS)

    Hungary is one of the newcomers to the CERN fold, having joined in 1992. The country's contributions are naturally in line with its slender resources and are not as immediately visible as those of the major Western European Member States. However the approach used and its consequent successes provide a good role model for a smaller nation in an international research environment. This was reflected on 24 September at a meeting of the European Committee for Future Accelerators (ECFA) convened in Budapest, continuing an ECFA tradition of holding meetings in national centres to learn more about the physics programmes of different countries. This tradition started with visits to major West European Centres, but last year ECFA held a meeting in Warsaw, its first in a central European country. By far the largest Hungarian population centre, Budapest is also a hub for national research in this sector, with university centres and the KFKI Research Institute for Particle and Nuclear Physics of the National Academy of Sciences. However important research work is also carried out in the eastern city of Debrecen. Hungarians look back to the classic investigations of Eotvos early this century as the starting point of their national tradition in fundamental physics. (In the mid-80s, these experiments briefly came back into vogue when there was a suggestion of an additional 'fifth force' contribution to nuclear masses.)

  9. Experience gained in enhancing operational safety at ComEd's nuclear power plants

    International Nuclear Information System (INIS)

    The following aspects of experience gained in enhancing operational safety at Comed's nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight

  10. Nuclear Medicine

    Science.gov (United States)

    ... Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive tracers? ... funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that uses ...

  11. Nuclear regulation in transition

    International Nuclear Information System (INIS)

    The current state of nuclear regulations in the USA is examined. Since Three Mile Island the regulation of the nuclear power industry has been undergoing a noticeable transition. It will be argued here that the transition is characterized by two indicia. First, the primary focus of state and federal regulators has been on the financial aspects of the industry: this is best seen in the context of decisions allocating the costs of nuclear plant cancellations. Second, decisionmaking power has been decentralized: although the regulatory history of nuclear power demonstrates the tradition of centralized decisionmaking power (i.e., formerly the primary decisionmaking body was the Atomic Energy Commission), now States share decisionmaking power with the Nuclear Regulatory Commission. In Section 1 a brief legislative history of nuclear regulation is presented to establish the assertion that nuclear regulation, both de jure and de facto, was centralized. Next, Section 2 canvasses recent United States Supreme Court opinions regarding nuclear regulation. The Court frequently acts as policymaker through the consequences of its opinions, if not by its intent. In the area of nuclear policymaking, the Court has paid allegiance recently both to the tradition of centralization and to the movement toward decentralization. This dualism is reflected in other federal court decisions as well which will be briefly mentioned. Continuing the analysis of Federal regulation, Section 3 examines the current reform efforts of the NRC. Section 4 presents an examination of State responses to nuclear plant cancellations. In this section, State administrative agency and court decisions will be examined and recent State legislation will be discussed. (author)

  12. Case study - Argentina

    International Nuclear Information System (INIS)

    Antecedents and experience of nuclear activities in Argentina; the Atomic Energy Commission (CNEA). First development and research activities. Research reactors and radioisotopes plants. Health physics and safety regulations. - Feasibility studies for the first nuclear power plant. Awarding the first plant CNA I (Atucha I). Relevant data related to the different project stages. Plant performance. - Feasibility study for the second nuclear power plant. Awarding the second plant CNE (Central Nuclear Embalse). Relevant data related to established targets. Differences compared with the first station targets. Local participation. Plant performance. (orig./GL)

  13. Invisible nuclear; converting nuclear

    International Nuclear Information System (INIS)

    This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

  14. Central Pain Syndrome

    Science.gov (United States)

    ... Enhancing Diversity Find People About NINDS NINDS Central Pain Syndrome Information Page Table of Contents (click to ... being done? Clinical Trials Organizations What is Central Pain Syndrome? Central pain syndrome is a neurological condition ...

  15. Artificial intelligence application to diagnosis and supervision of nuclear power plants

    International Nuclear Information System (INIS)

    A diagnostic expert system was developed, in the Process Control Division at the Centro Atomico Bariloche, for the Embalse nuclear power plant simulator. The diagnostic system task is to interpret and show the probable cause of an abnormal transitory behaviour in the simulated process. The system was developed using artificial intelligence techniques such as: knowledge representation using rules, heuristic programming, inference under uncertainty and fuzzy sets. The diagnostic technique used consists of finding the possible cause of failure using the fault hypothesis confirmation. The faults hypothesis are organized in hierarchical form into a tree structure. The Best First search strategy is used to direct the search to those hypothesis which are confirmed with a higher degree of certainty. The diagnostic is finished when a specific hypothesis is confirmed with a high certainty factor. The diagnostic result obtained by different process fault simulation is shown. An alternative diagnostic technique is presented where the knowlegde of process structure and behaviour are represented in the form of mathematical constraints. This diagnostic method detects a suspicious component through constraints satisfaction and localizes it through constraints suspension. The validity of the method is shown by an easy example. (Author)

  16. Super compacting of drums with dry solid radioactive waste in the nuclear power plant of Laguna Verde;Super compactacion de bidones con desecho radiactivo solido seco en la central nucleo electrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, R.; Lara H, M. A.; Cabrera Ll, M.; Verdalet de la Torre, O., E-mail: marco.lara@cfe.gob.m [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2009-10-15

    The nuclear power plant of Laguna Verde located in the Gulf of Mexico, completes in this 2009, nineteen years to produce by nuclear means 4.78% of the electric power that Mexico requires daily. During this time, the Unit 1 has generated more of 88.85 million mega watt-hour and the Unit 2 more of 69.48 million mega watt-hour with an availability average of 83.55%. Derived of their operation cycles, the nuclear power plant has generated (as any other installation of its type) radioactive wastes of low activity that at the moment are temporarily stored in the site. Due to the life cycle of the nuclear power plant, actually has become necessary to begin a project series focused to continue guaranteeing the storage of these wastes, guarantee that is a license requirement for the operation of this nuclear installation before the National Commission of Nuclear Security and Safeguards. The Federal Commission of Electricity beginning a project that allows continue guaranteeing space of sufficient storage for the wastes that the nuclear power plant of Laguna Verde could generate for the rest of its useful life, this project consisted on a process of physical volume reduction of dry solid radioactive wastes denominated super compacting, it has made possible to reduce the volume that these wastes occupy in the temporary storage noted Dry Solid Radioactive Wastes Deposit located inside the site that occupies the nuclear power plant of Laguna Verde. This work presents the super compacting results, as well as a description of the realization of this task until concluding with the super compacting of 5,854 drums with dry solid radioactive waste of low activity. We will enunciate which were the radiological controls that the Department of Radiological Protection of the nuclear power plant of Laguna Verde applied to this work that was realized for first time in Mexico and the nuclear power plant. (Author)

  17. A Study on the Nuclear Foreign Policy

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S

    2007-12-15

    This study approaches the international trends related to nuclear non-proliferation in four aspects. First, this study analyzes the trend of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime and proposals for assurance of nuclear fuel supply. Second, this study analyzes the trend of international nuclear organizations, which includes the International Atomic Energy Agency (IAEA), a central body of development of nuclear technology and international nuclear diplomacy, and the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a intergovernmental organization to consist of a group of nuclear advanced countries. Third, this study analyzes the trends of the U.S.'s nuclear foreign policies, particularly nuclear non-proliferation. Fourth, this study analyzes the nuclear issues of North Korea and Iran as they cause serious concerns to a international society.

  18. INFLUENCIA DE LAS CONDICIONES FISICOQUÍMICAS DEL SEDIMENTO Y LA INTERFASE AGUA-SEDIMENTO EN LA TRANSFERENCIA EXPERIMENTAL DEL O,O-DIETIL O?- 3,5,6 TRICLORO-2-PIRIDINIL FOSFOROTIATO (CLORPIRIFOS Y EL 3,5,6 TRICLORO-2-PIRIDINOL (TCP, EN EL EMBALSE RIOGRANDE II

    Directory of Open Access Journals (Sweden)

    Diana María Agudelo

    2013-12-01

    Full Text Available En esta investigación experimental se evaluó la influencia de algunas variables fisicoquímicas de sedimentos procedentes del embalse Riogrande II y de la interfase agua-sedimento en la transferencia de Clorpirifos y TCP. El análisis de clorpirifos y TCP en sedimentos y agua se realizó por extracción en fase sólida. Las muestras fueron detectadas por cromatografía de gases acoplada a espectrometría de masas (Trace GC Ultra MS 2030-Thermo Scientific. Se evidenció una fuerte adsorción de ambos compuestos en los sedimentos, dado el alto contenido de arcillas y de carbono orgánico, lo cual limitó su movilidad hacia la interfase. La interfase agua-sedimento se caracterizó por una condición de hipoxia durante toda la fase experimental, mientras que la conductividad eléctrica aumento en el tiempo. Se determinó que un pH neutro o ligeramente alcalino favoreció el aumento de la concentración de clorpirifos en la interfase agua-sedimento, lo cual sugiere un incremento de su transferencia desde el sedimento a la interfase, mientras que un pH ligeramente ácido favorece la transformación del compuesto parental en el sedimento.

  19. The nuclear case book

    International Nuclear Information System (INIS)

    The subject is covered in sections, entitled: the truth about nukes; disarmament, arms control and arms limitation; directory of nuclear weapons; tables of principal nuclear weapons; points of view 1 (Anglican); proliferation of nuclear technology; the just war; preventing proliferation; the numbers business; war scenario 1 (the Gulf); points of view 2 (Roman Catholic); deterrence; European Nuclear Balance; war scenario 2 (Germany); arguing about war and peace; points of view 3 (Jewish); is there a Soviet military threat; the view from Omsk; points of view 4 (Pugwash); the British deterrent; points of view 5 (generals for peace and disarmament); 'broken arrows'; costs of nuclear weapons; war scenario 3 (Pakistan); nuclear weapons - what is the moral response; non-use of nuclear weapons; points of view 6 (women and families for defence); dear Mr. Heseltine; why acquire nuclear weapons; the effects of nuclear weapons; war scenario 4 (Central America and the Middle East); civil defence; alternatives to nuclear defence; points of view 7 (Quaker). (U.K.)

  20. CINDU - Catalogue of numerical nuclear data available from the IAEA Nuclear Data Section

    International Nuclear Information System (INIS)

    This catalogue lists the nuclear data libraries presently held at the IAEA Nuclear Data Section. A number of evaluated neutron nuclear data files has recently been received at the IAEA Nuclear Data Section, and also libraries for charged particle nuclear data, photoneutron data, nuclear structure and decay data are now available. The primary purpose of the present issue is to publicize the various nuclear data libraries now available. CINDU is mainly addressed to nuclear and reactor physicists and other data users in the service area of the IAEA Nuclear Data Section, which includes countries in Eastern Europe and Asia (except USSR and Japan), Africa, Central and South America, Australia and New Zealand

  1. Nuclear cardiology

    International Nuclear Information System (INIS)

    Today, nuclear medicine techniques are routinely used in cardiological practice. They include procedures for the atraumatic investigation of different physiological processes in the various structures included in the central circulation: pericardium, myocardium, myocardial adrenergic innervation, cardiac chambers and valves, coronary microcirculation, and great vessels. Beside these in-Vivo procedures, they also comprise of in-Vitro methods for the detection and measurement in blood of various biological molecules of significance in the management of cardiac diseases. A common feature in this collection of in-Vivo and in-Vitro techniques is their ability to provide helpful clinical information for the diagnosis, prognosis and management of cardiac diseases. Their simplicity and safety for the patient allow their repeated use in the follow up of the progress of disease and in the assessment of the efficacy of the therapeutic measures

  2. To centralize or not to centralize?

    OpenAIRE

    Campbell, Andrew; Kunisch, Sven; Müller-Stewens, Günter

    2011-01-01

    The CEO's dilemma-were the gains of centralization worth the pain it could cause?-is a perennial one. Business leaders dating back at least to Alfred Sloan, who laid out GM's influential philosophy of decentralization in a series of memos during the 1920s, have recognized that badly judged centralization can stifle initiative, constrain the ability to tailor products and services locally, and burden business divisions with high costs and poor service.1 Insufficient centralization can deny bus...

  3. Panorama of the nuclear physics

    International Nuclear Information System (INIS)

    A summary of the topics covered by the nuclear physics, as disciplinary basis of the nuclear engineering, is presented, including from the fundamentals of modern physics used in nuclear physics, to the methods and more important applications, with the nucleus structure as central topic of the nuclear physics. In addition to a survey of the essential historical development in the different areas, this survey summarizes the basic concepts, postulates, laws and processes, which are the starting points, as in every scientific discipline for the understanding, interpretation and prediction of the variety of nuclear phenomena observed by methods increasingly improved and more complex, although such experimental methods are not discussed. (author)

  4. Laboratory Mesurements in Nuclear Astrophysics

    OpenAIRE

    Gai, Moshe

    1994-01-01

    After reviewing some of the basic concepts, nomenclatures and parametrizations of Astronomy, Astrophysics and Cosmology, we introduce a few central problems in Nuclear Astrophysics, including the hot-CNO cycle, helium burning in massive stars, and solar neutrino's. We demonstarte that SECONDARY (RADIOACTIVE) NUCLEAR BEAMS allow for considerable progress on these problems.

  5. Nuclear safety organisation in France

    International Nuclear Information System (INIS)

    This report outlines the public authorities responsible for the safety of nuclear installations in France. The composition and responsibilities of the Central Safety Service of Nuclear Installations within the Ministry of Industry, the Institute of Nuclear Protection and Safety within the CEA, the Central Service of Protection Against Ionising Radiation and the Interministerial Committee of Nuclear Safety are given. Other areas covered include the technical safety examination of large nuclear installations, the occurrence of accidents, treatment and control of release of radioactive wastes and decommissioning. The section on regulations covers the authorisation procedure, plant commissioning, release of radioactive effluents, surveillance and protection of workers exposed to ionising radiation. The situation is compared with the USA and the Federal Republic of Germany. A list of commercial nuclear installations in France is given

  6. Introduction - Latin America and nuclear energy

    International Nuclear Information System (INIS)

    For the second time in its history, the International Atomic Energy Agency is holding its General Conference in Latin America. The first was in Mexico City in September 1972; this September the Conference meets in Rio de Janeiro (in each case, the arrangement has been possible because of the very generous hospitality of the Host Government). Therefore, it is an appropriate occasion to devote a section of the IAEA Bulletin to nuclear energy in Latin America. The vast Latin American region presents many special opportunities for the introduction of nuclear science and technology. The first mission that the IAEA sent out, as far back as 1957, was to Latin America to promote co-operation in using radioisotope techniques. Today, these techniques are widely used by hospitals and medical research institutions throughout the region. Besides their medical applications, isotope techniques are also proving to be very useful in studying soils and irrigation, improving crops and livestock, and controlling insect pests. They also help make prudent use of the underground water resources in the region which, despite its bountiful rivers and tropical forests, includes many large arid areas. The major applications of nuclear technology have come only recently to Latin America, firstly in Argentina, where a 319 MW(e) nuclear power plant began operating at Atucha in 1974. It will soon be followed by the first Brazilian nuclear power plant - a 600 MW(e) light water plant at Angra dos Reis nearing completion. Argentina is building a second power plant at Embalse, and Brazil is planning two 1200 MW(e) plants at Angra and six more 1200 MW(e) units by 1990. Mexico is building its first nuclear plant at Laguna Verde, while other countries such as Chile and Colombia are planning the introduction of nuclear power. After a relatively slow start it, therefore, seems that nuclear power will go ahead fast in the Latin American region in the 1980's and 1990's. This is not surprising. Despite

  7. Panel Discussion - Eastern and Central Europe decommissioning

    International Nuclear Information System (INIS)

    In conjunction with technical session 'Experience with Present Decommissioning Projects' the Panel Discussion is organized in the frame of ECED 2013 Conference. The main purposes of the panel was to analyse more in details the information given in the previous session and mainly to answer the questions from the audience. The panel was focused on the on-going decommissioning projects and on the projects in the final phase of preparation in the region of Eastern and Central Europe as follows: - Ignalina Nuclear Power Plant in Lithuania - RBMK-1500 reactors; - Chernobyl Nuclear Power Plant in Ukraine - RBMK-1000 reactors; - Kozloduy Nuclear Power Plant in Bulgaria - VVER-440 reactors; - Metsamor Armenian Nuclear Power Plant - VVER-440 reactors; - Greifswald Nuclear Power Plant in Germany (former East Germany) - VVER-440 reactors; - V1 Nuclear Power Plant in Slovakia - VVER-440 reactors; - A1 Nuclear Power Plant in Slovakia - Heavy Water Gas Cooled Reactor; shutdown after accident. The panel speakers listed the skilled and experienced representatives from all above mentioned countries and from Russian Federation where many decommissioning projects are ongoing or under preparation. The region of Eastern and Central Europe has actually become very important in the field of decommissioning and the lessons learned from the performed projects could make a significant base for decommissioning projects worldwide.

  8. Seismotectonic model of Central Europe

    International Nuclear Information System (INIS)

    Earthquakes belong to natural disasters which are associated with tectonic processes in the interior of the Earth. They are extremely devastating in populated areas; they cause human losses and damage personal estates and the environment. To mitigate the potential effects of earthquakes it is necessary that relief and mitigation structures operate following an earthquake, but it is also essential to stimulate and enhance preparedness and prevention. Prevention includes the development of scenarios of potential earthquakes, hazard mapping, formulation of regulations, etc. Preparedness includes the installation and operation of warning systems, establishing communication networks to operate before, during, and after earthquakes. As nuclear technology belongs to high-risk technologies with regard to human health and the environment and its hazard substantially increases in consequence of earthquakes, in the siting of a nuclear plant engineering solutions are generally available to mitigate the potential vibratory effects through design. For the choice of a suitable engineering solution, reliable data must be processed by reliable techniques. The IAEA safety guide of the safety series No. 50-SG-S1(Rev. 1) specifies the demands on data and on their processing and also on the regional seismotectonic model. With a view of this the regional seismotectonic model of Central Europe was created. The paper presents regional geological characteristics of Central Europe and a chronological model of neotectonic movements in Central Europe with specification of neotectonic regional units and their present movements. Moreover, it contains earthquake characteristics for Central Europe and the specification of seismogenic movements. It was found that the genesis of local regions with occurrence of the strongest earthquakes is connected with several movement trends in the last 5 Ma. Six more or less tectonically separate regional units were revealed. The earthquake epicenters often

  9. Nuclear scientists, merchants and persons

    International Nuclear Information System (INIS)

    This article on the investigations made in the field of nuclear fission in the Netherlands during the past decades was included as a central chapter in the book 'Nuclear Energy in Motion, a Handbook on Issues of Nuclear Energy' which shall be published shortly by Keesing Boeken, Amsterdam. The book containing contributions of about 30 authors, was edited by C.D. Andriesse and A. Heertje. (orig./HP)

  10. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident provides valuable lessons for China national nuclear Corp.as it continues to expand its operations AS Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp. (CNNC),the country’s largest nuclear plant operator, comes under the spotlight.

  11. A central spent fuel storage in Sweden

    International Nuclear Information System (INIS)

    A planned central spent fuel storage facility in Sweden is described. The nuclear power program and quantities of spent fuel generated in Sweden is discussed. A general description of the facility is given with emphasis on the lay-out of the buildings, transport casks and fuel handling. Finally a possible design of a Swedish transportation system is discussed. (author)

  12. Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

    International Nuclear Information System (INIS)

    Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

  13. Nuclear undertakers

    International Nuclear Information System (INIS)

    The Shippingport Atomic Power Station, the first commercial nuclear central electric-generating station in the US, will soon be taken apart and buried in a process known as decommissioning. Beginning in the spring of 1985, and expected to last four years, the process will be closely watched by both the nuclear industry and its critics. A small crew has just finished removing the last fuel assemblies from the reactor's nuclear core; however, the pressure-vessel walls remain intensely radioactive. The author outlines the radiation protective measures that will be used as the workers cut and saw to disassemble the 21 miles of piping inside the plant - e.g., building plastic enclosures around certain work areas to trap radioactive dust and working behind shielding as positioned saws do the cutting. Also, any radioactive concrete in the plant will be removed, again using the best radiation-protective measures. Once the decommissioning team works its way in the heart of the reactor, the pressure vessel - a steel cylinder 35 ft high and 10 ft across with walls 8 inches thick - plans call for erecting a tower above and pouring concrete into the cavity around the vessel. The 770-ton steel and concrete package will then be hoisted in one piece, placed on a heavy-duty transporter and hauled to a barge on the Ohio River, eventually following a water route to the Hanford, Washington energy reservation; there it will join some other 120 truckloads of other radioactive wastes from its plant for burial. Even if this is successfully accomplished as planned and at the $80 million estimate, critics point out that decommissioning the much larger plants will be much more complex and costly - that Shippingport is far from an analogous situation

  14. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

  15. Centrality, Rapidity And Transverse-Momentum Dependence of Cold Nuclear Matter Effects on J/Psi Production in D Au, Cu Cu And Au Au Collisions at S(NN)**(1/2)

    Energy Technology Data Exchange (ETDEWEB)

    Ferreiro, E.G.; /Santiago de Compostela U.; Fleuret, F.; /Ecole Polytechnique; Lansberg, J.P.; /Ecole Polytechnique /SLAC; Rakotozafindrabe, A.; /SPhN, DAPNIA, Saclay

    2011-11-11

    We have carried out a wide study of Cold Nuclear Matter (CNM) effects on J/{Psi} = production in dAu, CuCu and AuAu collisions at {radical}s{sub NN} = 200 GeV. We have studied the effects of three different gluon-shadowing parameterizations, using the usual simplified kinematics for which the momentum of the gluon recoiling against the J/{Psi} is neglected as well as an exact kinematics for a 2 {yields} 2 process, namely g + g {yields} J/{psi} + g as expected from LO pQCD. We have shown that the rapidity distribution of the nuclear modification factor R{sub dAu}, and particularly its anti-shadowing peak, is systematically shifted toward larger rapidities in the 2 {yields} 2 kinematics, irrespective of which shadowing parameterization is used. In turn, we have noted differences in the effective final-state nuclear absorption needed to fit the PHENIX dAu data. Taking advantage of our implementation of a 2 {yields} 2 kinematics, we have also computed the transverse momentum dependence of the nuclear modification factor, which cannot be predicted with the usual simplified kinematics. All the corresponding observables have been computed for CuCu and AuAu collisions and compared to the PHENIX and STAR data. Finally, we have extracted the effective nuclear absorption from the recent measurements of RCP in dAu collisions by the PHENIX collaboration.

  16. Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model; Analisis de viabilidad en la propuesta de expansion de la central nucleoelectrica Laguna Verde: aplicacion de opciones reales, modelo binomial

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez I, S.; Ortiz C, E.; Chavez M, C., E-mail: lunitza@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2011-11-15

    At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

  17. Development of a severe accident module of a nuclear power plant based in the MELCOR nuclear code and its incorporation to the room simulator; Desarrollo del modulo de accidentes severos de una central nucleoelectrica basado en el codigo nuclear MELCOR y su incorporacion al simulador de aula

    Energy Technology Data Exchange (ETDEWEB)

    Cortes M, F.S.; Ramos P, J.C.; Nelson E, P.; Chavez M, C. [Facultad de Ingenieria, Division de Ingenieria Electrica, Grupo de Ingenieria Nuclear, UNAM, Ciudad Universitaria, Distrito Federal (Mexico)]. E-mail: samuelcortes@correo.unam.mx

    2004-07-01

    This work describes the development of the Severe Accidents Module (MAS) based on the Code MELCOR and its incorporation to the Simulator of Classroom of the Group of Nuclear Engineering of the Engineering Faculty (GrINFI) of the National Autonomous University of Mexico (UNAM). The module of Severe Accidents has the purpose of counting with installed and operational capacity for the simulation of accident sequences with capacitation purposes, training, analysis and design. A shallow description of SimAula is presented, and the philosophy used to obtain the interactive version of MELCOR are discussed, as well as its implementation in the atmosphere of SimAula. Finally, after confirming the correct operation of the development of the tool, some possible topics are discussed for specific applications of the MAS. (Author)

  18. Central Neuropathic Pain Syndromes.

    Science.gov (United States)

    Watson, James C; Sandroni, Paola

    2016-03-01

    Chronic pain is common in patients with neurologic complications of a central nervous system insult such as stroke. The pain is most commonly musculoskeletal or related to obligatory overuse of neurologically unaffected limbs. However, neuropathic pain can result directly from the central nervous system injury. Impaired sensory discrimination can make it challenging to differentiate central neuropathic pain from other pain types or spasticity. Central neuropathic pain may also begin months to years after the injury, further obscuring recognition of its association with a past neurologic injury. This review focuses on unique clinical features that help distinguish central neuropathic pain. The most common clinical central pain syndromes-central poststroke pain, multiple sclerosis-related pain, and spinal cord injury-related pain-are reviewed in detail. Recent progress in understanding of the pathogenesis of central neuropathic pain is reviewed, and pharmacological, surgical, and neuromodulatory treatments of this notoriously difficult to treat pain syndrome are discussed. PMID:26944242

  19. NIDDK Central Repository

    Data.gov (United States)

    U.S. Department of Health & Human Services — The NIDDK Central Repository stores biosamples, genetic and other data collected in designated NIDDK-funded clinical studies. The purpose of the NIDDK Central...

  20. Central and peripheral demyelination

    OpenAIRE

    Man Mohan Mehndiratta; Natasha Singh Gulati

    2014-01-01

    Several conditions cause damage to the inherently normal myelin of central nervous system, perepheral nervous system or both central and perepheral nervous system and hence termed as central demyelinating diseases, perepheral demyelinating diseases and combined central and perepheral demyelinating diseases respectively. Here we analysed and foccused on the etiology, prevalance, incidence and age of these demyelinating disorders. Clinical attention and various diagnostic tests are needed to ad...

  1. Analysis of a natural draught tower in the circulation seawater system of nuclear power plant of Laguna Verde; Analisis de una torre de tiro natural en el sistema de agua de circulacion de mar de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Vargas A, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Veracruz (Mexico)], e-mail: francisco.tijerina@cfe.gob.mx

    2009-10-15

    The analysis of a natural draught tower in open circuit for the cooling system of seawater circulation on the nuclear power plant of Laguna Verde, it is based on conditions of 2027 MWt and 2317 MWt, where the flows of circulation water system hardly vary and whose purpose will be, to cool the seawater circulation. The circulation water system is used as heat drain in main condenser of turbo generator to condense the nuclear vapor. The annual average temperature in the seawater at present is of 26 C to the entrance to circulation water system and it is vary in accordance with the time of year. The mean temperature of leaving of circulation water system to the sea is of 41 C. Having a cooling tower to reduce the entrance temperature to the circulation water system, it improves the efficiency of thermal transfer in condenser, it improves the vacuum in condenser giving more operative margin to avoid condenser losses by air entrances and nuclear power plant shutdowns, as well as for to improve the efficiency of operative balance of nuclear power plant, also it prevents the impact in thermal transfer efficiency in condenser by the climatic change. (Author)

  2. Pensar la organización del tiempo de trabajo cuando la tecnología cambia: el caso del equipo de trabajo de operación de una central nuclear

    Directory of Open Access Journals (Sweden)

    Sophie Prunier-Poulmaire

    2011-12-01

    Full Text Available The construction of a new generation of nuclear power plant has implied an ergonomics contribution in order to define the shift work schedule for the future operation crew. The study was carried out in three existing nuclear power plants through observation of activities specific to the concerned operating professionals. The data collected highlights major disparities between the performed tasks and their dynamics in terms of physical and mental demands. Furthermore, the same data underlines a strong temporal interdependence amidst the operation crew based on shift work schedules and the maintenance crew organized with set day time schedules. Vast differences are also recorded in terms of physical and mental demands of the tasks performed between day and night shifts as well as between the different stages of nuclear installations. The difficulties of workforce management are also at the source of large differences concerning the theoretical shift work schedule and the shift work schedule in place. In a multifactorial and systemic approach, with the general knowledge of chronobiology and the characteristics of the population involved, the outcomes will be a necessary component to define the shift work schedule for the operation crew of the nuclear power plant in construction.

  3. Exploitation continuation of Fessenheim nuclear plant nr 1 reactor after thirty years of operation; Poursuite d'exploitation du reacteur n.1 de la centrale nucleaire de fessenheim apres trente annees de fonctionnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After having recalled the regulatory framework, this report indicates how the Fukushima accident has been taken into account by the French nuclear safety authority (ASN) for the decision of keeping on operating the Fessenheim nuclear plant. Then, after a general presentation of nuclear installations, the report describes some peculiarities of the Fessenheim power plant with respect to the other French nuclear plants. It comments and discusses various issues: reactor exploitation, fuel management, vessel exploitation, exploitation of the main secondary circuits, of the confinement enclosure, and of other equipment. It recalls significant events, exploitation rules, and modifications brought to the reactor. It gives a global assessment. The authors report the safety re-examination (approach, compliance examination, security re-assessment), controls performed during decennial inspection (main controls and tests, implementation of modifications foreseen by safety re-examination, significant events, monitoring by the ASN, reactor restarting after the third decennial inspection). Perspectives are then discussed for the ten following years in terms of maintenance policy, ageing management, reactor vessel serviceability, and additional actions within the frame of ageing management. The operation continuation is then discussed

  4. Microbiological quality for bathing water in the "Conde del Guadalhorce" reservoir of Málaga City, Spain, 2000-2005 Calidad microbiológica de las aguas de baño del embalse Conde de Guadalhorce, de Málaga (España, 2000-2005

    Directory of Open Access Journals (Sweden)

    Joaquín Jesús Gámez de la Hoz

    2008-06-01

    Full Text Available Background. Determine the presence and evolution of indicators microorganisms of water pollution in “Conde del Guadalhorce” reservoir, Málaga city, Spain. A second objective was to analyze pollution degree and evaluate the sanitary quality of bathing water and compliance with European Directive 76/160/CE. Method. A total of 120 water samples were collected in two bathing freshwater sites during May to September sampling period between 2000 to 2005, and the numbers of total coliforms (CT, faecal coliforms (CF and faecal streptococci (EF were enumerated using the membrane filtration method. We used the log-normal distribution method and calculate the logarithmic means, percentile points, ratios CF:EF, ANOVA and Pearson correlations. Results. Only two samples overcome CF limit values at Camping sampling station during 2000 year. Ratios CF:EF values were higher (> 4 during 2000 to 2002, and lower (∝ ∝ Conclusions. “Conde del Guadalhorce” reservoir showed hygienic conditions for safety bathing. Globally, water bathing quality is good. CT, CF y EF indicators were agreed with UE Directive during 2000-2005, with exception CF at Camping station in 2000 year. CT y CF concentrations at Camping were frecuently higher than Kiosko, it could be caused to swimmers abundance and recreational activities. There was a trend towards rising EF, it could be caused to faecal pollution source of animal origin, needed to research it.Introducción. Determinar la presencia y evolución de microorganismos indicadores de contaminación en las aguas del embalse Conde del Guadalhorce, Málaga (España. Un segundo objetivo fue analizar el grado de contaminación y evaluar la calidad sanitaria del agua de baño según la Directiva 76/160/CE. Método. Se tomaron 120 muestras de aguas en 2 lugares de baño durante la temporada de mayo a septiembre en el período 2000 a 2005, y se enumeraron las bacterias coliformes totales (CT, coliformes fecales (CF y estreptococos

  5. Activities of nuclear human resource development in nuclear industry

    International Nuclear Information System (INIS)

    Since 2007, the JAIF (Japan Atomic Industrial Forum) had established the nuclear energy human resource development council to make analysis of the issue on nuclear human resource development. The author mainly contributed to develop its road map as a chairman of working group. Questionnaire survey to relevant parties on issues of nuclear human resource development had been conducted and the council identified the six relevant issues and ten recommendations. Both aspects for career design and skill-up program are necessary to develop nuclear human resource at each developing step and four respective central coordinating hubs should be linked to each sector participating in human resource development. (T. Tanaka)

  6. French nuclear energy development strategy

    International Nuclear Information System (INIS)

    The nuclear energy development in France is based on the spirit of democracy. Through the discussions in various groups and so on, an energy independent policy has been decided. That is, the energy independence of 50% is aimed at by 1990, by reducing the energy import. In order to lower the current petroleum reliance from 48.5% to 32% (by 1990), the development of new energy sources, including nuclear power, is essential. Nuclear energy is particularly important for French energy independence. The nuclear energy development program is on a very large scale; the share of nuclear energy in the total primary energy will be from 26% to 28% by 1990. Nuclear power generation features its low cost, and its remarkably high safety. For the nuclear power development, the consensus by all people is necessary. For the purpose, the network of both local and central organs is set up. (Mori, K.)

  7. Computerized management of nuclear material at the Grenoble nuclear research centre

    International Nuclear Information System (INIS)

    Under French law the production, possession, transfer, use and transport of nuclear material are subject to prior authorization by the Ministry of Industry and to control with a view to preventing losses, theft or diversion of such material. The holder of the authorization is required, in particular, to take measures for the monitoring and accounting of the nuclear material. For this purpose, the Grenoble Nuclear Research Centre, in collaboration with the Central Directorate for Safety and the Institute for Nuclear Protection and Safety (IPSN) of the Commissariat a l'energie atomique, has designed a computerized network which can be used for automation and centralization of nuclear material monitoring and accounting at the Centres and for interfacing with the IPSN's national centralized accounting system. The paper describes this network with the possibilities of its use in real time and emphasizes the advantages offered by automated centralized nuclear material management. (author). 2 figs, 2 tabs

  8. Nuclear power in perspective

    International Nuclear Information System (INIS)

    The nuclear power debate hinges upon three major issues: radioactive waste disposal, reactor safety and proliferation. An alternative strategy for waste disposal is advocated which involves disposing of the radwaste (immobilized in SYNROC, a titanate ceramic waste form) in deep (4 km) drill-holes widely dispersed throughout the entire country. It is demonstrated that this strategy possesses major technical (safety) advantages over centralized, mined repositories. The comparative risks associated with coal-fired power generation and with the nuclear fuel cycle have been evaluated by many scientists, who conclude that nuclear power is far less hazardous. Considerable improvements in reactor design and safety are readily attainable. The nuclear industry should be obliged to meet these higher standards. The most hopeful means of limiting proliferation lies in international agreements, possibly combined with international monitoring and control of key segments of the fuel cycle, such as reprocessing

  9. Organization of the nuclear safety in France

    International Nuclear Information System (INIS)

    The organization of the French public authorities in nuclear safety is presented: the Central Department of Safety for Nuclear Facilities (S.C.S.I.N.), the Institute of Nuclear Protection and Safety (I.P.S.N.), the Central Department for Ionizing Radiation Protection (S.C.P.R.I.) and Interministerial Commission for Nuclear Safety; the Permanent Groups of specialists (reactors, accelerators and other facilities); the Permanent Nuclear Section for nuclear boiler safety. The safety principles for basic nuclear installations are recalled (technical inspection, risks, radioactive wastes, radioactive effluents, decommissioning). The French regulation is completed by instructions relating to the procedure (authorization, operation, effluent release), the monitoring of installations, protection of the workers exposed to ionizing radiations. The situation is compared with USA and the Federal Republic of Germany. A list of the French nuclear facilities is given

  10. Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant; Estimacion de requerimientos de energia eolica equivalente a la generacion electrica de la Central Nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A.; Hernandez M, I.A. [Facultad de Ingenieria, Division de Ingenieria Electrica, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: maiki27@yahoo.com; Martin del Campo M, C. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2004-07-01

    The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

  11. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  12. Nuclear Medicine.

    Science.gov (United States)

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  13. Nuclear power

    OpenAIRE

    Waller, David; McDonald, Alan; Greenwald, Judith; Mobbs, Paul

    2005-01-01

    David Waller and Alan McDonald ask whether a nuclear renaissance can be predicted; Judith M. Greenwald discusses keeping the nuclear power option open; Paul Mobbs considers the availability of uranium and the future of nuclear energy.

  14. Nuclear electronics

    International Nuclear Information System (INIS)

    A short survey is given on nuclear radiation detectors and nuclear electronics. It is written for newcomers and those, who are not very familiar with this technique. Some additional information is given on typical failures in nuclear measurement systems. (orig.)

  15. Reactivity follow of the two first loadings of the Jose Cabrera Reactor; Seguimiento de la ractividad durante las dos primeras cargas del Reactor de la Central Nuclear Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Bru, A.

    1975-07-01

    In this paper the first two cores together with the in-core measurements taken during the operation of the Nuclear Power Station Jose Cabrera are described. The results of this measurements have been processed with the INCORE and FOLLOW codes. The peaking factors and the boron concentration versus burn-up are displayed. The final burn-up of the fuel elements in these two loading are given, too. (Author)

  16. Technical economic feasibility study for the implementation of a nuclear power plant for the production of electricity in Colombia; Estudio de factibilidad tecnico economica para la implementacion de una central de energia nuclear para la produccion de energia electrica en Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Gonzales, David E.; Bolanos, Hernan G.; Mayorga, Manuel A.; Rodriguez, Edwin A., E-mail: david_egO@yahoo.es, E-mail: hernanbolaos@yahoo.com.ar, E-mail: alejo_mayorga@yahoo.com, E-mail: edwin.rodriguez@distoyota.com.co [Escuela Colombiana de Carreras Industriales (ECCI), Bogota (Colombia). Grupo de Investigacion GIATME

    2013-07-01

    A study on the technical and economic feasibility will be used to implement a nuclear power in Colombia to generate electricity. To this will be searched if there are previous studies on this topic and what they concluded. The manner in which power is supplied will be discussed in a national level nowadays, its strengths and weaknesses. It will be investigated the legal norms that exists in the country on nuclear power and renewable energy sources, the standards established at world level, the nuclear accidents and the great examples. Providers will be sought on the world market nuclear equipment which serve to this purpose and the technical characteristics of these equipment will be discussed. The type of fuel used in nuclear reactors, its origin, method of production, specifications, availability and long-term and safe handling and final disposal are considered. safe handling of this technology and policy or international rules that will studied.

  17. Experiences in the implementation of the Coaching project in the nuclear power plant of Laguna Verde (NPP-L V); Experiencias en la implementacion del proyecto Coaching en la Central Nucleoelectrica Laguna Verde (CNLV)

    Energy Technology Data Exchange (ETDEWEB)

    Mendez M, H. I., E-mail: hugo.mendez01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Departamento del Centro de Entrenamiento, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2012-10-15

    This document has the purpose of to share acquired experiences during the implementation of the Coaching project focused the training of supervisors and directive personnel of the nuclear power plant of Laguna Verde (NPP-L V). Derived of the improvement areas identified by the supervisor organization of the nuclear power stations WANO (World Association Nuclear of Operators) and of the auto-evaluations realized by the expert personnel of the same power station that based on external experiences carried out through the Benchmarking (comparison with other power stations) they have reflected the necessity to activate a training process in Coaching with a practical focus toward the directive and supervisor personnel in the power station. By means of the observation of the personnel's acting so much in the control rooms like in different areas, three focus areas have been identified for the training in Coaching, these are the personnel's motivation, the organizational communication so much in vertical form as horizontal and the perception of confidence lack among directive, supervisors, operators and technicians. The plan focused in the abilities training of Coaching with practical sense was development, supported with an evaluation of 360 grades as tool of competitions development through a computer application e-Coaching. The use of application and Coaching following techniques facilitated the conformation of the practical focus, same that are of continuous use starting from the training of the supervisor and directive personnel. (Author)

  18. Nuclear power

    International Nuclear Information System (INIS)

    The subject is covered in chapters entitled: nuclear power certainties and doubts; nuclear power in the Western World to 2000; the frequency of core meltdown accidents; hidden costs of the accident at Three Mile Island; costs of nuclear accidents - implications for reactor choice; defining the risks of nuclear power; the uncertain economics of a nuclear power program; the economics of enabling decisions (Sizewell B as an enabling decision); trade in nuclear electricity; some pointers to the future. (U.K.)

  19. Nuclear data needs in Thailand

    International Nuclear Information System (INIS)

    The major nuclear facilities in Thailand are composed of nuclear research reactor, neutron generators, electron linear accelerators and 1 GeV Synchrotron facility, which is under construction. The other small facilities are radioisotope sources and X ray tubes for X ray diffraction and fluorescence studies. Office of Atomic Energy for Peace (OAEP) is the function arm for nuclear institutions in Thailand. Its major roles are nuclear regulatory, coordinating for nuclear affairs and foreign relations, R and D for nuclear science and technology and giving nuclear services. Nuclear data activities concerning Thai Research Reactor (TRR-1/M1) are for examples: neutronics and thermalhydraulics for reactor operation, neutron energy spectrum and neutron flux measurement for neutron activation analysis and isotope production, neutron and gamma doses, shielding and material testing for radiation safety, and neutron beam experiments. OAEP is taking part in the areas of regional cooperation on utilization of nuclear research reactors, education and training, sharing of research reactor experimental facilities, establishment of nuclear data program and information exchange. The nuclear data reports have been shared among institutions in Thailand through OAEP, which is served as a central nuclear data depository including e.g., INIS, IAEA-NDS, Joint Research Centre Commission of the European Communities and Japanese Nuclear Data Committee (JNDC). This report shows the nuclear facilities in Thailand, the roles of the Office of Atomic Energy for Peace on nuclear data depository and nuclear power development program. The main activities at the Thai Research Reactor TRR-1/M1 concerning nuclear data needs for specific uses in both theoretical and experimental aspects are also described. (J.P.N.)

  20. Nuclear data needs in Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Chongkum, S. [Physics Division, Office of Atomic Energy for Peace, Bangkok (Thailand)

    1999-03-01

    The major nuclear facilities in Thailand are composed of nuclear research reactor, neutron generators, electron linear accelerators and 1 GeV Synchrotron facility, which is under construction. The other small facilities are radioisotope sources and X ray tubes for X ray diffraction and fluorescence studies. Office of Atomic Energy for Peace (OAEP) is the function arm for nuclear institutions in Thailand. Its major roles are nuclear regulatory, coordinating for nuclear affairs and foreign relations, R and D for nuclear science and technology and giving nuclear services. Nuclear data activities concerning Thai Research Reactor (TRR-1/M1) are for examples: neutronics and thermalhydraulics for reactor operation, neutron energy spectrum and neutron flux measurement for neutron activation analysis and isotope production, neutron and gamma doses, shielding and material testing for radiation safety, and neutron beam experiments. OAEP is taking part in the areas of regional cooperation on utilization of nuclear research reactors, education and training, sharing of research reactor experimental facilities, establishment of nuclear data program and information exchange. The nuclear data reports have been shared among institutions in Thailand through OAEP, which is served as a central nuclear data depository including e.g., INIS, IAEA-NDS, Joint Research Centre Commission of the European Communities and Japanese Nuclear Data Committee (JNDC). This report shows the nuclear facilities in Thailand, the roles of the Office of Atomic Energy for Peace on nuclear data depository and nuclear power development program. The main activities at the Thai Research Reactor TRR-1/M1 concerning nuclear data needs for specific uses in both theoretical and experimental aspects are also described. (J.P.N.)