Real time neutronic evolution CNE (Embalse nuclear power plant)

International Nuclear Information System (INIS)

Notari, C.; Waldman, R.M.

1993-01-01

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

Structural radioactive waste from 'retubing/refurbishment' of Embalse nuclear power plant. Regulatory perspective

International Nuclear Information System (INIS)

Alvarez, Daniela E.; Lee Gonzales, Horacio M.; Medici, Marcela A.; Piumetti, Elsa H.

2009-01-01

Unlike the building of a new nuclear reactor, the 'retubing / refurbishment' of nuclear reactors that have been in operation for many years, involves the replacement of components in a radioactive environment. This requires a carefully planned radiation protection program to ensure protection of workers, the public and the environment as well as a radioactive waste management program for those radioactive waste generated during the process, which go beyond those generated during the normal operation and maintenance of the plant. Nucleoelectrica Argentina Sociedad Anonima (NA-SA) is scheduled to conduct the Life Extension Process of Embalse Nuclear Power Plant (CNE) which essentially consist of 'retubing / refurbishment' of the installation. The Nuclear Regulatory Authority (ARN) will then have an important activity related to the above process. In particular, this paper will describe some points of interest related to the generation and management of radioactive waste during the 'retubing / refurbishment' of the CNE, from the regulatory point of view. (author)

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)

Arestin, M.L.

1988-01-01

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.) [pt

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

International Nuclear Information System (INIS)

Pomerantz, Marcelo E.; Coutsiers, Eduardo E.; Moreno, Carlos A.

1999-01-01

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)

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

International Nuclear Information System (INIS)

Villar, Javier; Pomerantz, Marcelo E.

2003-01-01

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)

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

International Nuclear Information System (INIS)

Chocron, Mauricio; Saucedo, Ramona E.; Sainz, Ricardo A.; Ovando, Luis E.

2006-01-01

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)

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

Embalse steam generators - status in 2009

International Nuclear Information System (INIS)

Luna, P.; Yetisir, M.; Roy, S.; MacEacheron, R.

2009-01-01

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 plan 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

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

International Nuclear Information System (INIS)

Biondo, C.D.; Carloni, J.G.; Aba, J.A.

1987-01-01

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)

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

International Nuclear Information System (INIS)

Paz, A.O. de; Moreno, C.A.; Vinez, J.C.

1987-01-01

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)

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

International Nuclear Information System (INIS)

Garcia, A.E.; Parkansky, D.G.

1993-01-01

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)

Process improvement of the emergency operating procedures for Embalse Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Mariotti, A.D.; Pomerantz, M.; Moreno, C., E-mail: dmariotti@na-sa.com.ar, E-mail: mpomerantz@na-sa.com.ar, E-mail: cmoreno@na-sa.com.ar [Embalse Nuclear Power Plant, Nuclear Safety Dept., Embalse (Argentina)

2014-07-01

Emergency Operating Procedures (EOP) package of the Embalse Nuclear Power Plant (CNE) were made entirely by the plant staff since the beginning of its operation. With the emergence of Severe Accidents Guidelines (SAMG) and the latest events related to Fukushima, the EOP philosophy should include a new concept. It should consider that the EOP may be unsuccessful and an exit to the SAMG must be necessary. However, due to abnormal event mitigation using EOP is the way to prevent the beginning of a severe accident, EOP always had significant relevance in the plant documentation. For this reason, added to the overall requirement of an exit to the SAMG, it emerges a general review of the use efficiency of the EOP during an abnormal event. For this reason, a comprehensive process improvement has emerged using the operating experience, full-scope simulator training of the control room staff, advances in technology and the arrival of new generations. In this work, fundamental changes, new document format and ergonomic redesign for validation at full-scope simulator and use at main control room of new EOP for CNE are presented. (author)

Utilization of noise analysis technique for mechanical vibrations estimation in the ATUCHA{sub 1} and Embalse Argentine NPP; Uso de la tecnica de analisis de ruido para la estimacion de vibraciones mecanicas en las centrales nucleares argentinas Atucha I y Embalse

Energy Technology Data Exchange (ETDEWEB)

Lescano, V.H.; Wentzeis, L.M. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Centro Atomico Constituyentes; Guevara, M.; Moreno, C. [Nucleoelectrica Argentina S.A., Cordoba (Argentina). Central Nuclear Embalse; Pineyro, J. [Nucleoelectrica Argentina S.A., Buenos Aires (Argentina). Central Nuclear Atucha I

1996-07-01

In Argentine, comprehensive noise measurements have been performed with the reactor instrumentation of the PHWR power plant Atucha I and Embalse. The Embalse reactor is a CANDU-600 (600 Mwe) type pressurized heavy water reactor. It's a heavy water moderator and heavy water cooled natural uranium fueled pressure tube system. Signal of vanadium and platinum type in core-self power neutron detectors of ex-core ion chambers and of a moderator pressure sensor have been recorded and analysed. The vibration of reactor internals as vertical and horizontal in-core neutron flux detectors units and the coolant channels systems, consisting of calandria and pressure tubes with fuel bundles, have been identified and monitored during normal reactor operation. Atucha I, is a PHWR reactor natural uranium fueled, and heavy water moderated and cooled. Neutron noise techniques using of ex-core ionization chambers and in-core Vanadium SPND's were implemented, among others, in order to produce early detection of anomalous vibrations in the reactor internals. Noise analysis was successfully performed to identify normal and peculiar vibrations in particular reactor internals. (author)

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

International Nuclear Information System (INIS)

Bordoni, Roberto A.; Olmedo, Ana M.; Villegas, Marina; Miyagusuku, Marcela; Maroto, Alberto J. G.; Sainz, Ricardo A.; Fernandez, Alberto N.; Allemandi, Walter D.

1999-01-01

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)

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

International Nuclear Information System (INIS)

Acevedo, C.F.

1998-01-01

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)

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)

Suarez, P.O.

1990-01-01

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 CO 2 annular gas (thermal insulator) circulating between the pressure tube and the Calandria one during the functioning of the plant. (Author) [es

Application of reliability centered maintenance to Embalse NPP

International Nuclear Information System (INIS)

Torres, Antonio; Perdomo, Manuel; Fornero, Damian; Corchera, Roberto

2010-01-01

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)

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

International Nuclear Information System (INIS)

Rabiti, Arnaldo; Coutsiers, Ernesto; Schivo, Miguel; Mazanttini, Oscar

2003-01-01

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)

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

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)

Raffo, J.L

2001-01-01

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

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

International Nuclear Information System (INIS)

Godoy, A.R.; Marinelli, C.A.; Gruenbaum, C.E.

1978-01-01

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)

Simulation of a hypothetical liquid relief valve failure (open) at Embalse nuclear power plant when a reactor shutdown is considered; Simulacion de la evolucion de la CNE (central nuclear Embalse) en el caso hipotetico de la apertura espuria de una valvula de alivio liquido con disparo del reactor

Energy Technology Data Exchange (ETDEWEB)

Bedrossian, G; Gersberg, S [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

1997-12-31

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.

Transport of Cobalt 60 from the Argentine Nuclear Power Plant in Embalse

International Nuclear Information System (INIS)

Lopez Vietri, J.R.

2011-01-01

Full text: The purpose of this presentation is to point out some relevant issues related to the transport of cobalt 60 for domestic uses and export from the Argentine Nuclear Power Plant located in Embalse (ENPP). It is remarked that in last 22 years, ENPP produced about 2600 PBq (70 MCi) of Co-60, and that Argentina is the third Co-60 producer, after Canada and Russia. It is mentioned that in Argentina there are facilities which manufacture Zircaloy seamless tubes and reactivity control bars containing cobalt 59 to be used in ENPP, the operation of Candu reactor at ENPP including cobalt-related activities, and the manufacture and commercialization of Co-60 sealed sources. The Argentine Nuclear Regulatory Authority verifies the compliance of nuclear activities with regulatory standards, including those related to the transport of radioactive material. Then, it is described the process for obtaining Co-60 at ENPP with an activity concentration to allow its use in medicine and industry. After that, is considered in detail the type of package used for the transport of Co-60 from ENPP: it is to say, Type B(U) package designs that must be approved by the Competent Authority origin of the design, and they are able to withstand routine, normal and accident conditions of transport, including severe impacts, fires and immersion in water. The overall dimensions of packages are about 1.0 m to 1.5 m diameter by 1.2 m to 1.8 m high, as well as the gross mass could vary from 6500 kg to 9500 kg. Radioactive contents consist of Co-60 sealed sources (called pencils), with an activity range from 8 PBq to 16 PBq. Then, it is considered activities prior to dispatch of Type B(U) packages at ENPP, including the preparation of radioactive contents, packaging and package (labelling and marking) as well as necessary tests and documentation for transport in order to fulfil pertinent requirements of package design operation manual of the package and related standards. Finally, it is pointed

Embalse de Puente Alta

OpenAIRE

Isabel Crespo, Josué

2014-01-01

El presente proyecto de construcción define todas las actuaciones necesarias para la realización de las obras del Embalse de Puente Alta, ubicado en el término municipal de Revenga, provincia de Segovia. El proyecto se plantea debido a las previsiones de fuerte crecimiento poblacional, con motivo de la llegada del Tren de Alta Velocidad, puesto que el mantenimiento de la situación actual podría causar en su momento un déficit estructural en esta zona.

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

International Nuclear Information System (INIS)

Aguiar, J.C.; Fernandez, J.

2006-01-01

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

Reduced program of inspection by induced currents for condenser of Embalse nuclear power plant

International Nuclear Information System (INIS)

Obrutsky, L.; Mendonca, H.

1986-01-01

In this work it's presented a reduced inspection in service program by the technique of induced currents to the turbine condenser of Embalse's Power Plant (Cordoba). The authors based its elaboration on the results obtained in the exam of a small number of tubes and on experience obtained through four inspections in the condensers of Atucha I Power Plant, through mathematical models of oxygen and ammoniac distribution in both Power Plants, and its experimental verification in the case of Atucha I. This program improves the quality of inspection thereby reducing time, equipment and personnel employed. (C.M.) [pt

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

International Nuclear Information System (INIS)

Fornero, D.A.

2001-01-01

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)

Embalse PLiM/PLEx

International Nuclear Information System (INIS)

Ranalli, Juan M.

2006-01-01

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)

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.

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

International Nuclear Information System (INIS)

Bedrossian, Gustavo C.; Gersberg, Sara

2000-01-01

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)

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

International Nuclear Information System (INIS)

Couto, A.J.; Perez, S.S.

1987-01-01

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)

Software system for fuel management at Embalse nuclear power plant

International Nuclear Information System (INIS)

Grant, C.; Pomerantz, M.E.; Moreno, C.A.

2002-01-01

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

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.

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)

Separating rings detection in fuel channels of Embalse NPP

International Nuclear Information System (INIS)

Obrutsky, L.S.; Otero, P.A.; Schmidt, O.A.

1988-01-01

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

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

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Gilberto Mora Monroy

2000-01-01

de Guatavita y frente a la desembocadura de la quebrada El Muña que drena áreas de cultivo y su cuenca presenta alta concentración de viviendas. Los sectores restantes del embalse, que corresponden al “cuerpo” y la presa, muestran un estado de OLIGOTROFIA. Los nutrientes y materia orgánica vertidos al embalse determinan los niveles altos de fósforo y nitrógeno, que a su vez condicionan los demás procesos biológicos, que marcan la calificación de sectores del embalse en un nivel eutrófico (sector de la cola.

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...

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

International Nuclear Information System (INIS)

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

2006-01-01

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)

Técnicas moleculares para la detección de cianobacterias en los embalses Riogrande II y La Fe, Colombia

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Julio César Hurtado-Alarcón

2014-03-01

Full Text Available En embalses, la eutrofización es consecuencia de procesos naturales y de actividades humanas, lo cual puede facilitar la aparición de afloramientos de cianobacterias potencialmente tóxicas. En este trabajo, se utilizaron dos técnicas moleculares en la detección de genes presentes en cepas potencialmente tóxicas de cianobacterias y evaluaciones de diversidad molecular de cianobacterias en los embalses para potabilización de agua, Riogrande II y La Fe, Colombia. Entre 2010-2011, se tomaron 12 muestras de agua en ambos embalses y se realizaron extracciones de ADN para un análisis de marcadores moleculares mediante PCR y DGGE. Se amplificaron secuencias entre 250-300pb de los genes mcyA y mcyE, implicados en la toxicidad de cepas de cianobacterias. Asimismo, se amplificaron secuencias de la región 16S del ARN ribosomal (422pb, para la técnica DGGE. Se corrieron geles de poliacrilamida en gradientes de desnaturalización, se realizó agrupamiento genético (UPGMA, y se separaron por patrones de bandeo las muestras de cada embalse evaluado. Se demuestra la utilidad de las técnicas moleculares en estudios relacionados con la búsqueda de genes asociados con toxicidad y diversidad molecular de cianobacterias en muestras de agua provenientes de embalses de agua con fines de potabilización para centros urbanos.

Simulation of a turbine trip transient at Embalse NPP with full-circuit CATHENA model

Energy Technology Data Exchange (ETDEWEB)

Rabiti, A., E-mail: arabiti@na-sa.com.ar [Nucleoelectrica Argentina S.A., Embalse Nuclear Power Plant, Engineering Management Branch, Embalse (Argentina); Parrondo, A., E-mail: aparrondo@na-sa.com.ar [Nucleoelectrica Argentina S.A., Engineering Management, Buenos Aires (Argentina); Serrano, P., E-mail: pserrano@na-sa.com.ar [Nucleoelectrica Argentina S.A., Licensing Coordination Branch, Atucha II Project Branch (Unidad de Gestion), Buenos Aires (Argentina); Sablayrolles, A.; Damiani, H., E-mail: asablayrolles@na-sa.com.ar, E-mail: hdamiani@na-sa.com.ar [Nucleoelectrica Argentina S.A., Embalse Nuclear Power Plant, Embalse Life Extension Project Management, Embalse (Argentina)

2015-07-01

Embalse NPP is carrying on a Periodic Safety Review to deal with its life extension. This review includes tasks like Deterministic Analysis review for the Final Safety Analysis Report. In 2011, NA-SA (Nucleoelectrica Argentina S.A.) issued a first CATHENA full-circuit model representing the current plant. This model is used in this work. The simulation presented here corresponds to a turbine trip that occurred at Embalse NPP. Consistency between the simulation and the real event is demonstrated. Furthermore, NASA is currently performing Safety Analysis with a new model developed jointly with AECL and Candu Energy which includes post refurbishment changes and other improvements. (author)

The text of the agreement between the Agency and Argentina for the application of safeguards to Embalse Power Reactor Facility

International Nuclear Information System (INIS)

1995-01-01

The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 6 December 1974 between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Embalse Power Reactor Facility has been suspended

Evolución de la calidad de las aguas del embalse de los Hurones para consumo público (Cádiz, España)

OpenAIRE

Rodríguez Barroso, María del Rocío; Vidal Valderas, Luis; Sales Márquez, Diego; Quiroga Alonso, José María

2002-01-01

La calidad de las aguas de los embalses que se destinan al abastecimiento de poblaciones debe ser protegida, mantenida y vigilada con especial atención, teniendo en cuenta en cada caso los sistemas de tratamiento para su potabilización. El embalse de los Hurones, situado en la cuenca del río Majaceite en la provincia de Cádiz, es el quinto más importante de la provincia en cuanto a capacidad de embalse y de los primeros en cuanto a calidad físico-química. No obstante, y con las sequías sufrid...

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

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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

CARACTERÍSTICAS LIMNOLÓGICAS DEL EMBALSE EL PEÑOL-GUATAPÉ, COLOMBIA

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Néstor Jaime Aguirre Ramírez

2007-01-01

Full Text Available Con el propósito de estudiar las características hidrobiológicas de dos columnas de agua en el embalse El Peñol-Guatapé, entre julio de 1992 y agosto de 1993 se realizaron muestreos mensuales en la cola del embalse y en aguas abiertas (Isla del Sol. En cada estación y a cinco profundidades se analizaron algunas variables fisicoquímicas, y en la zona eufótica se estudió la comunidad fitoplanctónica, excluyendo el grupo de las Diatomophyceas. En las dos estaciones se encontraron gradientes térmicos y químicos; desde el punto de vista hidrobiológico la calidad del agua fue oligomesotrófica. La producción primaria fue baja durante todo el período estudio y, al igual que las demás variables, estuvo fuertemente influida por la variación en los niveles del embalse en la época de estudio.Between July of 1992 and August of 1993 and with the purpose of studying the hydrologic characteristics of two water columns in the Peñol-Guatapé Reservoir, monthly sampling in the reservoir's tail were carried out and in open water (Isla del sol. In each station and at five depths, some physical and chemical variables were analyzed; and in the fotic zone, the phytoplankton community was studied, excluding the Diatomophyceae group. Thermal and chemical gradients were found in the two stations and from the hydro-biological point of view, the quality of water was oligomesotrofic. The primary production was low during the entire period of sampling, and just as the other variables, it was deeply influenced by the variation in the reservoir levels at the time of study.

Variaciones de abundancia y biomasa del zooplancton en un embalse tropical oligo-mesotrófico del norte de Venezuela

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Sandra Merayo

2010-06-01

Full Text Available La abundancia del zooplancton en los embalses está determinada principalmente por la velocidad y el contenido del agua, pero se sabe relativamente poco sobre los embalses tropicales. Se estudió la distribución temporal y espacial de la abundancia y la biomasa del zooplancton en el eje longitudinal del embalse de Clavellinos, en el norte de Venezuela, entre octubre 2006 y septiembre 2007. El zooplancton fue recolectado en el estrato oxigenado con una red de plancton. Un total de 16 taxones fueron identificados: Copepoda, Cladocera, Rotifera, Ostracoda y Diptera. Thermocyclops decipiens (Copepoda, Cyclopoida dominó la comunidad, mientras que los rotíferos fueron los más diversos, con 10 especies. La abundancia del zooplancton varió de 31 a 101ind/l en E1, 36 a 84ind/l en E2, y, de 30 a 250ind/L en el E3. La biomasa varió de 97,4 a 1406.3μg/l en E1, 108,5 a 397.2μg/l en E2, y de 25,9 a 763.9μg/l en el E3. Esta comunidad de zooplancton pareciσ responder a las variaciones ambientales en el embalse, mαs que a las variaciones en la disponibilidad de recursos.

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

International Nuclear Information System (INIS)

Santaliz, Jorge O.; Paredes, Juan A.

1998-01-01

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)

IMPLICACIONES TERRITORIALES DE UNA GRAN OBRA HIDRÁULICA: EL EMBALSE DEL TRANCO (CABECERA DEL GUADALQUIVIR

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Eduardo Araque Jiménez

2012-01-01

Full Text Available Situado en la cabecera del Guadalquivir, el embalse del Tranco fue durante muchos años el de mayor capacidad de almacenamiento de agua de toda Andalucía. Sus aportaciones resultaron fundamentales para el sostenimiento del regadío en el gran valle bético, al tiempo que con sus aguas pudo generarse una parte de la energía eléctrica que se precisaba para la modernización del aparato productivo andaluz y la mejora de las condiciones de vida en multitud de hogares en el valle del Guadalquivir. Frente a estas perspectivas tan halagüeñas, las aguas embalsadas en el Tranco apenas tuvieron repercusiones socioeconómicas positivas para la Sierra de Segura. Las expropiaciones masivas a las que dio origen tanto la construcción del embalse como la repoblación forestal que lo acompañó, propiciaron la emigración masiva de centenares de vecinos, muchas veces en condiciones de extrema precariedad. Por otro lado, las aguas del Tranco nunca se utilizaron para la expansión del regadío por algunos de los fértiles valles próximos al embalse, ni la electricidad generada a pie de presa llegó a los hogares serranos, que siguieron careciendo de este servicio durante muchos años.

Analysis of the time dependence of the tritium concentration in the Embalse Rio Tercero lake

International Nuclear Information System (INIS)

Lopez, F.O.; Bruno, H.A.

1998-01-01

In natural uranium and heavy water reactors, tritium is produced mainly as the activation product of the deuterium in the moderator and cooling medium. About 75% of the liquid effluents discharged by nuclear power plants in Argentina correspond to tritium. In the case of the Embalse nuclear power plant, the liquid effluents are discharged into the Rio Tercero reservoir. As its water is used for drinking, 98% of the dose received by the critical group is due to these discharges. A simple mathematical model was developed which predicts the variation in the tritium concentration in the reservoir. It is a complete mixture type model and the entry parameters are the lake volume, entrance volume and discharge volume. The model was solved by means of a Runge-Kutta method of second order. The chosen method is a modified Euler. A good correlation is observed when the values obtained by means of the numeric resolution of the developed model are compared with the values obtained by the tritium measurement made during the 1996 and 1997 environmental monitoring program. (author) [es

Nuclear Activities in Argentina, 2010

International Nuclear Information System (INIS)

Ferreri, J.C.; Ferreri, J.C.; Clausse, A.; Clausse, A.; Clausse, A.; Ordonez, J.P.; Mazzantini, O.A.

2011-01-01

Nuclear activities in Argentina are restarted. After almost two decades of near stagnation, the governments political decision of August 2006 regarding electrical energy production, considered the nuclear option as a valid one to solve the problems of the growing demand of electrical energy. This decision triggered again the activities related to the finalization of the third nuclear power reactor (Atucha-II), now actively progressing, the construction of a prototype of the CAREM integral advanced reactor, the life extension of the Embalse CANDU nuclear power plant (NPP) and the studies for the emplacement of a fourth NPP in an appropriate site. In all those years of near stagnation, there were notable exceptions related to the design and construction of experimental and radioisotope production reactors, led by INVAP, a state-owned industry, which exported its production. The accompanying industries of nuclear fuel elements production also remained active, given the demand of the two active NPPs. Meanwhile, the National Atomic Energy Commission of Argentina continued the efforts on research and development that were at the base of the technological achievements of the nuclear activities in Argentina. Nuclear safety studies associated with Atucha II and Embalse NPPs and radiological safety were also a substantive part of the continued efforts by Nucleo-Electrica de Argentina SA and the Nuclear Regulatory Authority of Argentina

La reactivación del Deslizamiento Zapotal y su relación con el llenado del embalse del Proyecto Hidroeléctrico Pirris

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Mora Chinchilla, Rolando

2011-12-01

Full Text Available El 3 de agosto de 2011 varias viviendas en la comunidad de Zapotal Abajo, perteneciente al distrito de San Lorenzo del cantón de Tarrazú, empezaron a mostrar un deterioro progresivo. Este proceso coincidió con el llenado del embalse del Proyecto Hidroeléctrico Pirrís. Ante esta coincidencia, personeros del Instituto Costarricense de Electricidad (ICE y de CoopeTarrazú contactaron a la Escuela Centroamericana de Geología de la Universidad de Costa Rica, con el fin de que realizara un estudio para verificar si el proceso fue desencadenado o no por el llenado del embalse. Se realizó la respectiva investigación y se entregaron los resultados a las partes interesadas en una actividad realizada en el Auditorio César Dondoli B, de la Escuela Centroamericana de Geología, el día 5 de octubre de 2011. La reactivación del deslizamiento es consecuencia del llenado del embalse. Como una de las recomendaciones más importantes se sugiere que las laderas inestables deben ser vistas como factores de gran importancia dentro de la vialidad técnica de una obra civil, que en el caso que nos ocupa, serían las represas para proyectos hidroeléctricos August 3, 2011, several houses from the community Zapotal Abajo, San Lorenzo - Tarrazú, showed progressive deterioration. This process coincided with the filling of the Pirrís Hydro electrical Project. This coincidence made personnel from the Costa Rican Electricity Institute (Instituto Costarricense de Electricidad - ICE and CoopeTarrazú contact the Central American Geology Faculty of the University of Costa Rica to develop a study to verify if the process was caused or not by the reservoir filling. An investigation was developed and the results were delivered to the interested parties in an activity held at the César Dondoli B Auditorium, at the Central American Geology Faculty, October 5, 2011. The reactivation of the slide is a consequence of the reservoir filling. One of the most important

SITUACIÓN DE Menidia jordani (Pisces: Atherinopsidae EN EL EMBALSE LA GOLETA, ESTADO DE MÉXICO

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N. A. Navarrete-Salgado

2010-01-01

Full Text Available En este estudio se analiza la situación del charal Menidia jordani (Pisces, Atherinopsidae en el embalse La Goleta, Estado de México y las variaciones poblacionales desde 1998, cuando se registró por primera vez en el embalse. Para ello se realizaron visitas en 1998, 2007 y 2008 durante las épocas secas y de lluvias. Los peces fueron capturados con un chinchorro charalero de 30.0 m de largo, 1.5 m de caída y 8.0 mm de abertura de malla, fijados con formalina al 10 %, llevados al laboratorio e identificados. Los resultados muestran que la mayor abundancia de M. jordani se registró en 1998 (3,000 peces·1000 m-2, mientras que la menor abundancia se presentó en 2008 (5 orgs.·1000 m-2. Se concluye que estas variaciones están en función de la presencia de especies exóticas como la carpa común (Cyprinus carpio y la carpa dorada (Carassius auratus, con las cuales compite, asimismo, la presencia de una especie carnívora (Micropterus salmoides afecta la población del charal en el embalse. El céstodo (Bothriocephalus acheilognathi, influyó en la disminución de este pez y el vertido de aguas negras hacia este sistema afectaron también su abundancia.

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

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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

Characterization of the inside and outside oxide surfaces of irradiated pressure tubes of Embalse nuclear power plant

International Nuclear Information System (INIS)

Bordoni, Roberto A.; Olmedo, Ana M.

2004-01-01

The inside and outside surfaces of two pressure tubes (PT) removed from Embalse nuclear power plant (CNE) after 10 of effective full power years (EFPY) were characterized. The oxide thickness of both faces, in different zones, was also measured. The inside surfaces of both PTs, B-102 (A-14) and B-298 (L-12), were covered with a black oxide that replicates the original PT surface. A network of microcracks perpendicular to the inside surface in contact with the coolant was found. In some cases, near the outlet of the PT, some spalling of the oxide was also found. These small microcracks and spalling do not affect the protective character of the oxide since a thickness about 5 or 6 μm of an undamaged oxide is found at the metal/oxide interface side. The oxide thickness changes between approximately 6 to 12 μm for B-102 tube and around 7 to 15 μm for B-298 tube. The average corrosion rate is 1.16 μm/10 4 HH for B-102 tube and 1.35 μm/10 4 HH for B-298 tube at 5.8 m position for both PTs. These corrosion rates show good corrosion behaviour of CNE PTs. The average corrosion rate of the inside surface of the PTs depends on the coolant temperature but not on fast neutron flux. The outside oxide film is black, shiny, compact and protective, replicating also the original surface. The oxide thickness changes between 2 to 6.5 μm in B-102 tube and between 1.8 to 3.7 μm B-298 tube. These oxide thicknesses are within the values reported for PTs in CANDU Stations. (author) [es

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

International Nuclear Information System (INIS)

Salas, Carlos

2008-01-01

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)

Nuclear Energy in Central Europe 98, Proceedings

International Nuclear Information System (INIS)

Ravnik, M.; Jencic, I.; Zagar, T.

1998-01-01

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

Maintenance and life assessment of steam generators at Embalse Nuclear Station

International Nuclear Information System (INIS)

Luna, P.; Diaz, G.; Sveruga, H.; Sainz, R.

2006-01-01

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

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)

Paz, A.O. de; Moreno, C.A.; Vinez, J.C.

1990-01-01

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) [es

Cianobacterias del embalse San Roque (Córdoba, Argentina Cyanobacteria of the San Roque reservoir (Córdoba, Argentina

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Inés Claudia Daga

2011-12-01

Full Text Available Este trabajo es una contribución al conocimiento de las cianobacterias presentes en el embalse San Roque y forma parte de un estudio integral de la flora algal del mencionado embalse. Se citan 24 taxa correspondientes a los Ordenes Chroococcales (11, Nostocales (8 y Oscillatoriales (5. Synechocystis aquatilis, Gloeocapsa rupestris, Gomphosphaeria aponina, Chamaesiphon incrustans f. incrustans, Scytonema crispum, Tolypothrix distorta, Gloeotrichia pisum, Calothrix fusca, Trichodesmium lacustre, Geitlerinema splendidum, Lyngbya aestuarii y Borzia trilocularis son nuevas citas para la zona de estudio.This work is a contribution to the knowledge of the Cyanobacteria present in the San Roque reservoir and forms a part of an integral study of its algal flora. Twenty-four taxa are described and ilustrated: 11 Chroococcales, 8 Nostocales, and 5 Oscillatoriales. Synechocystis aquatilis, Gloeocapsa rupestris, Gomphosphaeria aponina, Chamaesiphon incrustans f. incrustans, Scytonema crispum, Tolypothrix distorta, Gloeotrichia pisum, Calothrix fusca, Trichodesmium lacustre, Geitlerinema splendidum, Lyngbya aestuarii and Borzia trilocularis.

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.

Utilization of noise analysis technique for mechanical vibrations estimation in the ATUCHA1 and Embalse Argentine NPP

International Nuclear Information System (INIS)

Lescano, V.H.; Wentzeis, L.M.; Guevara, M.; Moreno, C.; Pineyro, J.

1996-01-01

In Argentine, comprehensive noise measurements have been performed with the reactor instrumentation of the PHWR power plant Atucha I and Embalse. The Embalse reactor is a CANDU-600 (600 Mwe) type pressurized heavy water reactor. It's a heavy water moderator and heavy water cooled natural uranium fueled pressure tube system. Signal of vanadium and platinum type in core-self power neutron detectors of ex-core ion chambers and of a moderator pressure sensor have been recorded and analysed. The vibration of reactor internals as vertical and horizontal in-core neutron flux detectors units and the coolant channels systems, consisting of calandria and pressure tubes with fuel bundles, have been identified and monitored during normal reactor operation. Atucha I, is a PHWR reactor natural uranium fueled, and heavy water moderated and cooled. Neutron noise techniques using of ex-core ionization chambers and in-core Vanadium SPND's were implemented, among others, in order to produce early detection of anomalous vibrations in the reactor internals. Noise analysis was successfully performed to identify normal and peculiar vibrations in particular reactor internals. (author)

Central depression of nuclear charge density distribution

International Nuclear Information System (INIS)

Chu Yanyun; Ren Zhongzhou; Wang Zaijun; Dong Tiekuang

2010-01-01

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 46 Ar and 44 S is supported by the relativistic mean-field calculation. According to the calculation, the valence protons in 46 Ar and 44 S prefer to occupy the 1d 3/2 state rather than the 2s 1/2 state, which is different from that in the less neutron-rich argon and sulfur isotopes. As a result, the central proton densities of 46 Ar and 44 S 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.

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)

1975-01-01

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

Central Institute for Nuclear Research (1956 - 1979)

International Nuclear Information System (INIS)

Flach, G.; Bonitz, M.

1979-12-01

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)

Caracterización de la contaminación por metales pesados y reducción de capacidad de almacenamiento hidráulico por azolve de un embalse mexicano

OpenAIRE

García Aragón, Juan Antonio; Díaz-Delgado, Carlos; Quentin, Emmanuelle; Ávila Pérez, Pedro; Tejeda Vega, Samuel; Zarazúa Ortega, Graciela

2007-01-01

El embalse José Antonio Alzate es el primero sobre el curso del río Lerma y acumula los sedimentos erosionados de la cuenca del Curso Alto del río Lerma (CARL), un área densamente urbanizada. Desde el punto de vista hidráulico, dicho embalse cumple la función de control de avenidas y surte de agua a distritos de riego. La realización reciente de un estudio batimétrico del mismo permitió definir el perfil actual de fondo del terreno. Estos niveles se compararon con los originales (antes de su ...

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)

Amado, Valeria A.

2007-01-01

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) [es

Variaciones de abundancia y biomasa del zooplancton en un embalse tropical oligo-mesotrófico del norte de Venezuela

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Sandra Merayo

2010-06-01

Full Text Available La abundancia del zooplancton en los embalses está determinada principalmente por la velocidad y el contenido del agua, pero se sabe relativamente poco sobre los embalses tropicales. Se estudió la distribución temporal y espacial de la abundancia y la biomasa del zooplancton en el eje longitudinal del embalse de Clavellinos, en el norte de Venezuela, entre octubre 2006 y septiembre 2007. El zooplancton fue recolectado en el estrato oxigenado con una red de plancton. Un total de 16 taxones fueron identificados: Copepoda, Cladocera, Rotifera, Ostracoda y Diptera. Thermocyclops decipiens (Copepoda, Cyclopoida dominó la comunidad, mientras que los rotíferos fueron los más diversos, con 10 especies. La abundancia del zooplancton varió de 31 a 101ind/l en E1, 36 a 84ind/l en E2, y, de 30 a 250ind/L en el E3. La biomasa varió de 97,4 a 1406.3μg/l en E1, 108,5 a 397.2μg/l en E2, y de 25,9 a 763.9μg/l en el E3. Esta comunidad de zooplancton pareciσ responder a las variaciones ambientales en el embalse, mαs que a las variaciones en la disponibilidad de recursos.Variations of zooplankton abundance and biomass in a tropical oligo-mesotrophic reservoir in Northern Venezuela. Zooplankton abundance in reservoirs is mainly determined by the speed and content of the water, but relatively little is known regarding tropical reservoirs. We studied the seasonal and spatial distribution of zooplankton abundance and biomass along the longitudinal axis of Clavellinos reservoir, northern Venezuela, from October 2006 to September 2007. Zooplankton was collected from the oxygenated layer using a plankton net. A total of 16 taxa were identified: Copepoda, Cladocera, Rotifera, Ostracoda and Diptera. Thermocyclops decipiens (Copepoda, Cyclopoida dominated the community, while rotifers were the most diverse, with 10 species. Zooplankton abundance varied from 31 to 101ind/L in E1, 36 to 84ind/L in E2, and, from 30 to 250ind/L in E3. Biomass varied from 97.4 to

New fuel advanced heavy water reactors

International Nuclear Information System (INIS)

Notari, Carla

1999-01-01

A redesign of the PHWR fuel element (FE) to be used in all Argentine nuclear power plants has been proposed elsewhere. This new FE presents several characteristics aimed to an improved in-core performance and economical benefits derived from the unification of most of the fabrication processes that today constitute two different production lines: one for Embalse nuclear power plant CANDU type fuel and another for Atucha I. Atucha I and Embalse, the two operating nuclear power plants in Argentina, are PHWR of different conception. Atucha I (357 M we) is of pressure vessel type and the fuel elements are full-length assemblies (530 cm of active length) with 36 uranium rods in the cluster and a support one in the outer ring. Embalse (648 M we) is a CANDU pressure tube reactor fuelled with the well known 37 rod / 50 cm length fuel bundles, twelve of which are loaded in each channel. The more relevant changes in the proposed design are an increased subdivision of the fuel material in 52 rods and a 100 cm long bundle. The combined features give the adequate channel pressure drop. The proposed CARA design shows a superior neutronic performance than the standard PHWR fuel elements currently used in Atucha I and Embalse nuclear power plants. A variant of the CARA FE consisting in the elimination of the central four rods, leaving 48 rods and a central free space, is strongly recommended because it saves materials (less uranium, less sheaths) with no loss of burnup. The central D 2 O zone allows a better utilization of the inner rods and compensates the diminished uranium loading. In Embalse no differences in core physics are expected except the beneficial decrease in linear power density. In Atucha I besides the lower power density, a higher exit burnup appears as a consequence of the higher uranium inventory. The exit burnup figures have been calculated with cell and reactor models and the result is that similar fuel management schemes as the proposed for Atucha I for the

Fourth Regional Meeting: Nuclear Energy in Central Europe, Proceedings

Energy Technology Data Exchange (ETDEWEB)

Mavko, B; Cizelj, L [eds.; Nuclear Society of Slovenia (Slovenia)

1997-07-01

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.

Case study - Argentina

International Nuclear Information System (INIS)

Diaz, E.

1986-01-01

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)

Nuclear insurance in Central and Eastern Europe

International Nuclear Information System (INIS)

Warren, G.

1998-01-01

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)

Nuclear Electric's central dose record service

International Nuclear Information System (INIS)

Goldfinch, E.P.; Mullarkey, D.T.; McWhan, A.W.; Risk, G.; Vaughan, L.

1991-01-01

This paper describes the conception, development and operation of the Nuclear Electric Central Dose Record Service, including the initial philosophy considered necessary for a database for a large multi-site organisation, the setting up of the data and current routine operation. Lessons learned are briefly described. CDRS holds 35,000 records in a high security environment. The database includes records of radiation doses received by contractor's employees working at Nuclear Electric sites as well as dose records and dose histories for classified and non classified Nuclear Electric employees. (Author)

Estudio de la composición y abundancia del zooplancton durante la fase de llenado del embalse Amaní, Norcasia (Caldas

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Juan Pablo Álvarez Silva

2003-01-01

Full Text Available La variación de la composición, abundancia y diversidad del zooplancton fue analizada durante la fase de llenado del embalse Amaní en un gradiente horizontal y vertical, a partir de trece muestreos semanales realizados entre junio y agosto de 2002. La composición del zooplancton es similar a otros ecosistemas lénticos tropicales de baja altitud y fue registrado un total 32 taxa, de los cuales se destaca el rotífero Keratella por su elevada abundancia durante junio y julio. Rotifera fue el grupo que presentó la mayor riqueza de especies (16 así como una sobresaliente dominancia numérica sobre copépodos y cladóceros, con una abundancia relativa superior al 60%. La densidades promedio del zooplancton fluctuaron de manera significativa (6 a 1525 org l-1, y de forma diferencial entre los brazos del embalse y los sectores de confluencia y presa, que presentaron los menores intervalos (14-208 org l-1 y 6-108 org l-1, respectivamente. En el presente trabajo se incluyen los patrones de comportamiento de la abundancia de los géneros más frecuentes de zooplancton así como de aspectos relacionados con la dinámica poblacional de los copépodos Thermocyclops decipiens y Mesocyclops aspericornis. Se discuten los cambios en la estructura de la comunidad del zooplancton y se mencionan las posibles interacciones y fenómenos de regulación entre los diferentes taxa zooplanctónicos y de estos con el fitoplancton. Finalmente se presenta un catalogo de microfotografías de los organismos registrados. Este trabajo constituye un aporte importante de ecología descriptiva del zooplancton limnético y da pautas para posteriores monitoreos en este embalse.

Nuclear Activities in Argentina. A short Review. Part 2

International Nuclear Information System (INIS)

Coll, Jorge A.; Radicella, Renato

2002-01-01

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)

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

International Nuclear Information System (INIS)

Daverio, H; Juanico, L

2000-01-01

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

Nuclear power production costs

International Nuclear Information System (INIS)

Erramuspe, H.J.

1988-01-01

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) [es

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

International Nuclear Information System (INIS)

Chocron, Mauricio A.; Becquart, Elena T.; Iglesias, Alberto M.; La Gamma, Ana M.; Villegas, Marina

2003-01-01

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)

Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

International Nuclear Information System (INIS)

Stritar, A.; Jencic, I.

1996-01-01

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

Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

Energy Technology Data Exchange (ETDEWEB)

Stritar, A; Jencic, I [Nuclear Society of Slovenia (Slovenia); eds.

1996-07-01

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.

Embalse de laguna de Barlovento la Palma, Canarias – España

Directory of Open Access Journals (Sweden)

Forteza Steegmann, C.

1976-04-01

Full Text Available This article describes various studies and the works that have been necessary to transform the natural existing basin into a dam, although the actual idea is rather that of a big water reservoir; analysis of the gorge, construction of the water-pipes, canals and weirs; the most suitable solution of the casting problem, etc. The dam volume has a geometric shape enclosed by two concentric oval lines, one at 732 m height, and the lower at 695 m. The axes of the two ovals are 615 x 570 m and 249 x 144 m, respectively. The maximum height of the water is 730 m (with a 2 m margin to allow for waves and water rushes and to meet the specifications for inland dikes. Hence, its capacity is approximately 4,450,406 m2.Se describen en este artículo los diversos estudios y las obras necesarias para acondicionar la depresión natural existente, utilizándola como embalse, aunque la idea conceptual es más bien la de un depósito de grandes dimensiones; análisis de barrancos, construcción de las conducciones de trasvase precisas para su llenado, de canales, túneles, tuberías y azudes; solución más idónea de los problemas de vaciado, etc. La superficie total de cuencas trasvase es de 2.562 ha, estando constituida la configuración geométrica del depósito por una superficie reglada engendrada por una directriz quebrada que se apoya en dos óvalos concéntricos a las cotas 732 y 695; el superior tiene 615 x 510 m, y el inferior, 249 x 144 m. La cota máxima de embalse es de 730 (con 2 m de resguardo para absorber sobre elevaciones, en avenidas y oleajes, y en cumplimiento de la Instrucción para diques de fierra], con lo cual su capacidad es de unos 5.450.406 m2.

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

Energy Technology Data Exchange (ETDEWEB)

Gortnar, O; Stritar, A [Nuclear Society of Slovenia (Slovenia)

1999-07-01

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.

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

International Nuclear Information System (INIS)

Gortnar, O.; Stritar, A.

1999-01-01

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

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)

Rouben, B.; Chow, H.C.; Leung, L.K.H.; Inch, W.; Fink, J.; Moreno, C.

2004-01-01

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% 235 U 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

Proceedings of the 2000 International Conference on Nuclear Energy in Central Europe

International Nuclear Information System (INIS)

Mavko, B.; Cizelj, L.; Kovac, M.

2000-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 108 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: thermal hydraulics, severe accidents, probabilistic safety assessment (PSA), nuclear waste, safety analyses, nuclear power plant operation, structural integrity and aging, nuclear energy and public, other related topics, research reactors, education and training and Monte Carlo transport calculations

Central eastern Europe approach to the security over nuclear materials

International Nuclear Information System (INIS)

Smagala, G.

2002-01-01

Full text: This paper presents an overview of the national approaches to physical protection of nuclear materials in Central Eastern Europe (CEE), with an emphasis on Poland. Soviet influence in the past led to inadequate safety culture in nuclear activities and insufficient security of nuclear materials and facilities in the region. In the centralized economies all aspects of nuclear activities, including ownership of the nuclear facilities, were the responsibility of the state with no clear separation between regulating and promoting functions. During the last decade a significant progress has been made in the region to clean up the legacy of the past and to improve practices in physical protection of nuclear materials. The countries of Central Eastern Europe have had many similar deficiencies in nuclear field and problems to overcome, but cannot be viewed as a uniform block. There are local variations within the region in a size of nuclear activities, formulated respective regulations and adopted measures to secure nuclear materials and facilities. Nevertheless, all twelve nations, with nuclear reactors and without nuclear facilities, have joined the convention on the physical protection of nuclear material and most of them declare that they have followed the IAEA recommendations INFCIRC/225/Rev.4 to elaborate and implement their physical protection systems of nuclear materials and facilities. The largest request for an international advisory mission (IPPAS) to review states' physical protection systems and to address needs for improvement was received from the countries of Central Eastern Europe. Poland belongs to the beneficiaries where the IPPAS mission and later follow-up consultations resulted in physical protection upgrade of the research reactor under the IAEA/US/UK technical assistance project. A powerful incentive to the progress made in a number of CEE countries was the goal of accession to the European Union. The physical protection of nuclear

Central Institute of Nuclear Research Rossendorf 25 years old

International Nuclear Information System (INIS)

Hohmuth, K.; Kaun, K.H.; Schmidt, A.; Hennig, K.; Brinckmann, H.F.; Lehmann, E.; Rossbander, W.; Bitterlich, H.; Weibrecht, R.; Fuelle, R.; Nebel, D.; Reetz, T.; Beyer, G.J.; Muenze, R.

1981-12-01

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)

Proceedings of the International Conference Nuclear Energy in Central Europe 2001

International Nuclear Information System (INIS)

Jencic, I.; Glumac, B.

2001-01-01

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

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.

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

International Nuclear Information System (INIS)

Stritar, A.; Jencic, I.

1995-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Stritar, A; Jencic, I [eds.; Nuclear Society of Slovenia (Slovenia)

1996-12-31

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

Nuclear and radiation safety of the centralized spent fuel storage facility in Ukraine

International Nuclear Information System (INIS)

Grigorash, O.V.; Dibach, O.M.; Panchenko, A.V.; Shugajlo, Ol-r P.; Kovbasenko, YU.P.; Vishemyirskij, M.P.; Bogorad, V.I.; Belykh, D.O.; Shendrovich, V.Ya.

2017-01-01

The paper presents the analysis of ensuring nuclear and radiation safety in the management of spent nuclear fuel at the Centralized SFSF and activities planned for Centralized SFSF life cycle stages. There are results of comparing requirements of U.S. regulatory documents used by the HOLTEC Company to design Centralized SFSF equipment staff with relevant requirements of Ukrainian regulations, results based on analysis of the most important factors of Centralized SFSF safety (strength and reliability, nuclear safety, thermal regimes and biological protection) and verified expert calculations of the SSTC NRS. The paper includes issues to be considered in further implementation of Centralized SFSF project.

First-order effects of a nuclear moratorium in Central Europe

International Nuclear Information System (INIS)

Messner, S.; Strubegger, M.

1986-12-01

An energy supply model developed at IIASA previously is used to investigate the consequences of a hypothetical nuclear power phaseout in Central Europe. It is assumed that no new nuclear power plants will be built in Central Europe after 1990 but the existing ones will be used for a planned lifetime of 25 years. Energy-specific consequences, import dependence, emissions, energy prices and investments from the energy sector are considered. (G.Q.)

The innovation of nuclear science and technology supporting for the central plains economic zone construction

International Nuclear Information System (INIS)

Yang Xiaowei

2014-01-01

This paper discusses the nuclear agronomy support for the central plains economic zone construction, radiation chemical new material support for the central plains economic zone construction, nuclear medical support for the central plains economic zone construction, nuclear instrument and meter industry support for the central plains economic zone construction and the development trend of related disciplines. (author)

Current situation and future of a nuclear power plan in Argentina

International Nuclear Information System (INIS)

Messi, E.

2006-01-01

After the crisis suffered by Argentina during the first years of the new millennium, the economic variables improved significantly, thus showing the need for an increase in the electric supply. While the growth rate of the electric demand has been of a steady 4%, the electric supply didn't come along as expected; mainly due to the decrease in the gas reserves, among other things. This scenario opens new opportunities for the nuclear area in our country: especially with Atucha II NPP termination that will contribute with 745 MWe gross output, together with Embalse NPP's life extension and refurbishment, and the analysis for the installation of new generation nuclear power plants in the decades to come, therefore strengthening the nuclear industry in Argentina. (author)

Reproducción de Micropterus salmoides (Pisces: Centrarchidae, en el embalse Gustavo Díaz Ordaz, Sinaloa, México

Directory of Open Access Journals (Sweden)

Rigoberto Beltrán Alvarez

2013-09-01

Full Text Available Micropterus salmoides es un pez de importancia para la pesca deportiva en la mayoría de los embalses de México y del mundo, por lo que en el embalse Gustavo Díaz Ordaz se realizó un estudio sobre aspectos reproductivos entre agosto 2008 y marzo 2011. Se recolectaron 938 organismos, a los cuales se les midió la longitud (Lt cm, peso (Pt g, se determinó el sexo, índice gonadosomático, factor de condición, fecundidad y talla de primera madurez. La longitud y peso de los ejemplares recolectados varió de 15.9 a 63 cm (37.4±78.0 y de 57 a 4 431g (731.7±619.0, respectivamente. La relación peso total-longitud total se ajustó a un modelo tipo potencial, el crecimiento fue alométrico positivo, no se obtuvieron diferencias significativas entre machos y hembras (F=0.9955, p=0.3187. La proporción macho-hembra fue 1:0.83. Los desoves masivos inician en diciembre y finalizan en abril. La talla de primera reproducción fue de 33.7cm y la fecundidad promedio de 32 294±12 878.7 ovocitos/hembra. El índice gonadosomático se mantuvo bajo desde mayo hasta noviembre y alto entre enero y marzo. El factor de condición registró valores altos previos al desove y disminuyó al final del periodo reproductivo.

Nuclear Safety in Central and Eastern Europe

International Nuclear Information System (INIS)

2001-04-01

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

Conceptual evaluation of type B(U) casks for the nuclear power plants of Argentina

International Nuclear Information System (INIS)

Florido, P.C.; Isnardi, E.R.

1993-01-01

In Argentina two different nuclear power plants are in operation, Atucha I (PHWR-Siemens) and Embalse (PHWR-CANDU). Thus two very different fuel elements could be potentially transported. In order to optimize the research and development needed for the design and construction of the cask, the cost-benefit and flexibility of the engineering solutions are studied, for the two fuel elements. Different casks, for both types of existing fuel elements (Atucha I and Embalse), for different burnup-levels (regarding the advanced fuel cycle available), decay times, distances, and transported weight were studied. Three materials for shielding were used: uranium lead and steel. Only transport by road was considered, due to the reduced availability of the train. In this stage (conceptual design) small, easy and fast computer programs should be used. The principal issues that have to be fixed are shielding properties, thermal effects and mechanical behavior. As a result of the evaluation, different options for the casks were founded, as well as the importance of different parameters and the effect of two different designs of fuel elements. (author)

Prospects for a nuclear-weapon-free zone in Central Asia

International Nuclear Information System (INIS)

Potter, W.C.

1997-01-01

This paper examines the concept of a Nuclear-Weapon-Free Zone (NWFZ) as an approach to nuclear nonproliferation with special reference to Central Asia . 20 More specifically, it describes the evolution of a NWFZ in the region, the potential benefits of a zone, the principal obstacles in the path of its implementation, and the practical steps that need to be taken if a NWFZ in Central Asia is to be realized. The paper concludes that a NWFZ in Central Asia, as with prior NWFZ, would likely lead to advances in the application of an important nonproliferation approach. One innovative aspect of the zone in Central Asia might be its treatment of environmental issues. Although it will not be a simple process to rally support from all of the P-5 states for a new NWFZ, all countries of Central Asia - as well as global community of nations - should profit from creation of a zone which reinforces the international nonproliferation regime improves prospects for political and economic stability in a region of growing importance

Nuclear spin noise in the central spin model

Science.gov (United States)

Fröhling, Nina; Anders, Frithjof B.; Glazov, Mikhail

2018-05-01

We study theoretically the fluctuations of the nuclear spins in quantum dots employing the central spin model which accounts for the hyperfine interaction of the nuclei with the electron spin. These fluctuations are calculated both with an analytical approach using homogeneous hyperfine couplings (box model) and with a numerical simulation using a distribution of hyperfine coupling constants. The approaches are in good agreement. The box model serves as a benchmark with low computational cost that explains the basic features of the nuclear spin noise well. We also demonstrate that the nuclear spin noise spectra comprise a two-peak structure centered at the nuclear Zeeman frequency in high magnetic fields with the shape of the spectrum controlled by the distribution of the hyperfine constants. This allows for direct access to this distribution function through nuclear spin noise spectroscopy.

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

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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.

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

Directory of Open Access Journals (Sweden)

A. Maldonado

2000-07-01

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.

Use of 'tail' as spent fuel dilution factor of Angra-1 (PWR) for use in the Embalse (Candu) reactor

International Nuclear Information System (INIS)

Mai, Luiz Antonio; Maiorino, Jose Rubens

1995-01-01

This work purposes a process to use the tail of isotopic enrichment as a factor of dilution (blending) for the burned fuel of Angra-I reactor (PWR) for final utilization in the Embalse (Candu). It was made use of the same technic in previous works that used natural uranium. For this purpose, it was made a tail parametrization inside of the traditional limits of enrichment (between 0.2 and 0.3%). The study showed that the tail utilization represents great savings for the uranium supplies and environment and economic advantages. (author). 8 refs, 4 figs, 11 tabs

Radiological protection for spent fuel dry storage at Embalse NPP

International Nuclear Information System (INIS)

Carballo, Carlos; Melo, Rodolfo

2008-01-01

Embalse NPP dry-stores used fuel elements in concrete silos inside the premises: The fuel elements are kept for at least 6 years in pools located in the controlled area , before being moved into the silos. This paper describes the radiological protection for the different stages of the process, i.e., when the used fuel elements are moved from the pools into the silos, and while they are kept in the concrete silos. The occupational exposure of the personnel operating this system at each stage is showed, as well as the environmental dose rates around the silos, and the dose rate in the shields used during the transfer. These environmental dose rates are assessed with portable instruments and with TLD dosimeters placed around the silos. This paper also describes the periodical routine control performed every two years in the atmosphere inside the silo, the moisture control and the detection of possible aerosols (in some cases, traces of krypton 85 were detected). It is important to point out that the maximum equivalent environmental dose rate H* (10) detected at approximately 20 metres from the silos is overly low: (0.35 micro sievert / hour). Our experience demonstrates that dry storage is totally compatible with the environment and with the ALARA criterion for personnel's doses. (author)

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

International Nuclear Information System (INIS)

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

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.

Accounting for and control of nuclear material at the Central Institute of Nuclear Research, Rossendorf

International Nuclear Information System (INIS)

Heidel, S.; Rossbander, W.; Helming, M.

1983-01-01

A survey is given of the system of accounting for and control of nuclear material at the Central Institute for Nuclear Research, Rossendorf. It includes 3 material balance areas. Control is implemented at both the institute and the MBA levels on the basis of concepts which are coordinated with the national control authority of the IAEA. The system applied enables national and international nuclear material control to be carried out effectively and economically at a minimum of interference with operational procedures. (author)

Nuclear Research and Development Institutes in Central and Eastern Europe

International Nuclear Information System (INIS)

2009-06-01

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

Strain measurements of nuclear power plant steam generator antiseismic supports

International Nuclear Information System (INIS)

Kulichevsky, R.

1997-01-01

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) [es

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

International Nuclear Information System (INIS)

Migliori de Beninson, A.; Cancio, D.

1984-01-01

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)

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

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Juan Pablo Niño Garcia

2003-01-01

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 respondieron a las fluctuaciones estacionales de las afluencias y cambios de nivel del agua, así como a la distribución espacial de E. densa;. esta última se relacionó con el aumento en las tasas de sedimentación del seston, nitrógeno y fósforo. Durante la descomposición estos dos nutrientes se perdieron rápidamente en los primeros días, volviéndose limitantes para los microorganismos descomponedores en fases posteriores del proceso. Estos recurren a nutrientes disueltos, escasos en la columna de agua, que en consecuencia pueden ser limitantes para los procesos de descomposició.

Perspectives for nuclear electricity in central Africa

International Nuclear Information System (INIS)

Wa Kalenga, M.

1977-01-01

The paper analyses the energetic system of Central African countries and evaluate the projected global demand of energy. It compares the economy of the nuclear solution for the satisfaction of future demand versus other forms of energy available in the region. It appreciates finally the role that the countries involved can play in the fuel cycle (supply of raw material, possibilities of fuel enrichment) [fr

Perspectives for nuclear electricity in Central Africa

International Nuclear Information System (INIS)

Wa Kalenga, M.

1977-01-01

The paper analyses the energy system of the Central African countries and evaluates the projected global demand of energy. It compares the economy of the nuclear solution for satisfying future demands in relation to other forms of energy available in the region. Finally, it discusses the role that the countries involved can play in the fuel cycle (supply of raw material, possibilities of fuel enrichment). (author)

Safeguards at the Central Institute for Nuclear Research at Rossendorf/GDR

International Nuclear Information System (INIS)

Helming, M.; Rehak, W.; Schillert, B.

1989-01-01

Experience in the implementation of domestic and international safeguards at the Central Institute for Nuclear Research at Rossendorf is reported covering the following topics: overview of the main nuclear installations belonging to the Institute; structure of its material balance areas; responsibilities for the different aspects of accounting for and control of nuclear material at facility level; the various types of nuclear materials handled and their flow, accessibility and strategic significance; the assessment of IAEA safeguards effectiveness. 2 tabs., 2 figs. (author)

30 years of Central Institute for Nuclear Research at Rossendorf

International Nuclear Information System (INIS)

Scheler, W.; Flach, G.; Hennig, K.; Collatz, S.; Muenze, R.; Baldeweg, F.

1986-10-01

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)

Chlorococcales nuevas para el embalse Paso de las Piedras (Buenos Aires, Argentina New Chlorococcales for Paso de las Piedras Reservoir (Buenos Aires, Argentine

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Carolina Fernández

2005-12-01

Full Text Available En el presente trabajo se citan e ilustran 22 especies pertenecientes al orden Chlorococcales (Chlorophyceae, Chlorophyta halladas en el embalse Paso de las Piedras que representan nuevas citas para este ambiente. Pseudokirchneriella subcapitata, Tetraedron hemisphaericum y Scenedesmus semipulcher constituyen nuevas citas para la República Argentina.In this paper, we record and illustrate 22 species of Chlorococcales (Chlorophyceae, Chlorophyta found in Paso de las Piedras Reservoir, which are new records for this area. Pseudokirchneriella subcapitata, Tetraedron hemisphaericum and Scenedesmus semipulcher are new for Argentina.

Application of the neutron noise analysis technique in nuclear power plants

International Nuclear Information System (INIS)

Lescano, Victor H.; Wentzeis, Luis M.

1999-01-01

Using the neutron noise analysis in nuclear power plants, and without producing any perturbation in the normal operation of the plant, information of the vibration state of the reactor internals and the behavior of the operating conditions of the reactor primary circuit can be obtained. In Argentina, the neutron noise analysis technique is applied in customary way in the nuclear power plants Atucha I and Embalse. A database was constructed and vibration frequencies corresponding to different reactor internals were characterized. Reactor internals with particular mechanical vibrations have been detected and localized. In the framing of a cooperation project between Argentina and Germany, we participated in the measurements, analysis and modelisation, using the neutron noise technique, in the Obrigheim and Gundremmingen nuclear power plants. In the nuclear power plant Obrigheim (PWR, 350 M We), correlations between the signals measured from self-power neutron detectors and accelerometers located inside the reactor core, were made. In the nuclear power plant Gundremmingen (BWR, 1200 M We) we participated in the study of a particular mechanical vibration detected in one of the instrumentation tube. (author)

Central depression in nucleonic densities: Trend analysis in the nuclear density functional theory approach

Science.gov (United States)

Schuetrumpf, B.; Nazarewicz, W.; Reinhard, P.-G.

2017-08-01

Background: The central depression of nucleonic density, i.e., a reduction of density in the nuclear interior, has been attributed to many factors. For instance, bubble structures in superheavy nuclei are believed to be due to the electrostatic repulsion. In light nuclei, the mechanism behind the density reduction in the interior has been discussed in terms of shell effects associated with occupations of s orbits. Purpose: The main objective of this work is to reveal mechanisms behind the formation of central depression in nucleonic densities in light and heavy nuclei. To this end, we introduce several measures of the internal nucleonic density. Through the statistical analysis, we study the information content of these measures with respect to nuclear matter properties. Method: We apply nuclear density functional theory with Skyrme functionals. Using the statistical tools of linear least square regression, we inspect correlations between various measures of central depression and model parameters, including nuclear matter properties. We study bivariate correlations with selected quantities as well as multiple correlations with groups of parameters. Detailed correlation analysis is carried out for 34Si for which a bubble structure has been reported recently, 48Ca, and N =82 , 126, and 184 isotonic chains. Results: We show that the central depression in medium-mass nuclei is very sensitive to shell effects, whereas for superheavy systems it is firmly driven by the electrostatic repulsion. An appreciable semibubble structure in proton density is predicted for 294Og, which is currently the heaviest nucleus known experimentally. Conclusion: Our correlation analysis reveals that the central density indicators in nuclei below 208Pb carry little information on parameters of nuclear matter; they are predominantly driven by shell structure. On the other hand, in the superheavy nuclei there exists a clear relationship between the central nucleonic density and symmetry energy.

Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

1963-10-15

This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

Experimental and inspection facilities in post-irradiation of spent fuel pools for the analysis of the behaviour of nuclear fuels in power reactors

International Nuclear Information System (INIS)

Ruggirello, G.; Zawerucha, A.

1992-01-01

Since the beginning of the Atomic Nuclear Reactors (PHWR) Atucha I and Embalse in Argentine are employed different techniques for the knowing of the fuel bundles performances. It is detailed the facilities on post-irradiation examination. The techniques described are: online measurements, visual inspections, identifications of defective fuels and rods assemblies in spent fuel pools. This controls have made possible the feed-back to the manufactory process and the changes in the manufactory quality controls. (author)

Dangerous liaisons: Western involvement in the nuclear power industry of central and eastern Europe

International Nuclear Information System (INIS)

1992-12-01

The state of the nuclear industry in central and eastern Europe is an issue of global concern. However, despite all the political talk and corporate hype since the collapse of communist regimes in the region, this study demonstrates that little has so far been done to change the situation. Moreover, the limited level of finance and support which has been offered has tended to support the expansion of nuclear power programmes in central and eastern Europe, rather than address immediately safety concerns relating to existing nuclear reactors and develop more environmentally acceptable and economically efficient energy systems. (author)

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

International Nuclear Information System (INIS)

1984-05-01

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

Central Scientific and Research Institute of Nuclear Information as the branch centre of information on nuclear science and engineering

International Nuclear Information System (INIS)

Arkhangel'skij, I.A.; Sokolov, D.D.; Kalinin, V.F.; Nikiforov, V.S.

1982-01-01

The main tasks are considered in the scope of the Central Scientific-Research Institute for Information and Technological and Economic Studies on Nuclear Science and Technology. (TsNIIAtominform). The institute coordinates scientific research and information activity of information agencies of all the USSR organizations engaged in nuclear science and technology, excercises a centralized completion of their libraries, develops and puts into practice the most progressive methods for the information servicing. The institute is a national INIS center of the USSR. Here a system for the automatic information dissemination has been successfully elaborated and employed. Much of the institute activity is given to the estimation and analysis of information and to the determination of tendencies in the nuclear science and technology development. A conclusion is drawn to the effect that TsNIIAtominform, within 15 years of its existence, has formed as a center ensuring functioning of the system of scientific and technical information on nuclear science and technology

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

Energy Technology Data Exchange (ETDEWEB)

Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

2013-10-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

International Nuclear Information System (INIS)

Duran, Felicia Angelica; Waymire, Russell L.

2013-01-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

CARA Project: development of the advanced ULE fuel element for heavy water nuclear power plants

International Nuclear Information System (INIS)

Brasnarof, Daniel O.; Marino, Armando C.; Florido, Pablo C.; Munoz, C.; Bianchi, Daniel R.; Giorgis, Miguel A.

2006-01-01

The CARA Project (Spanish acronym of Combustible Avanzado para Reactores Argentinos) is a national fuel element technology development, compatible with our nuclear power plants (Atucha I, Embalse and Atucha II). It takes into account the experience obtained in our nuclear organisations (CNEA-CONUAR-NASA). The goal of the CARA fuel element is the performance improvement for those reactors and the enhancing of their normal operative conditions. The CARA design allows the burnup extension by using 52 rods of the same diameter. Likewise it keeps good thermo-hydraulic behaviour. The fuel bundle can be directly used in nuclear power plants with horizontal channels. By using an additional system it can be installed in the PHWR with vertical channels. The expected profits, by the use of the CARA in our reactors, broadly guaranty the recovery of the fund for its development, due to a reduction of the NPP fuels and back end cost. We estimate a reduction in the generation cost between 20 or 25 % in relation to the present one if we use 0.85 or 0.90% SEU (Slightly Enriched Uranium). The use of the CARA fuel in our reactors will also reduce the amount of spent fuel to be treated. The shortening could be between 17 to 27 % in Atucha I in relation to the present ULE (0.85%), between 38 to 46% for Embalse, and 45 to 53% for Atucha II. The mechanical behaviour and hydraulic compatibility have been verified. Several CARA prototypes were fabricated with a new design of the end plate and with new processes for the welding for the rods. We present in this paper the current status of the CARA fuel element development. (author) [es

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

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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

TRAMA TRÓFICA DE LOS PECES DEL EMBALSE LA GOLETA (PRIMAVERA 2007 EN EL ESTADO DE MÉXICO

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N. A. Navarrete-Salgado

2010-01-01

Full Text Available En este estudio se determinó la posición trófica de la ictiofauna del embalse La Goleta, Estado de México. Se realizó un muestreo en la primavera de 2007, donde se registraron los siguientes parámetros del agua, temperatura, profundidad, transparencia, turbidez, oxígeno disuelto, conductividad, pH, dureza, y alcalinidad, también se realizó la captura de peces utilizando un chinchorro charalero. El análisis del contenido estomacal se determinó con el método numérico y volumétrico. Los peces capturados pertenecen a tres especies: Menidia jordani, la cual se considera una especie zooplanctófaga generalista; Cyprinus carpio, es omnívoro muy generalista y Carassius auratus que es un pez herbívoro generalista.

Promoting global safeguards cooperation: Argentine-U.S. technical achievements

International Nuclear Information System (INIS)

Owens, L.; Smith, C.

1996-01-01

The bilateral ENREN (Argentina National Nuclear Regulatory Board)-DOE Safeguards Agreement was signed by Dr. Dan Beninson, ENREN, and Dr. Kenneth Baker, DOE, at the Peaceful Uses Conference in Bariloche in 1994. Two major activities identified for immediate cooperation were: nondestructive assay (NDA) techniques for Pilcaniyeu, and advanced containment and surveillance at Embalse. Both of these are discussed here. While the activities of the past year and a half are significant, many more opportunities remain for valuable cooperative partnering to discover more effective and efficient ways to apply safeguards. Several that have been identified by ENREN and DOE for 1996 are: (1) environmental monitoring as a safeguards technique; (2) Pilcaniyeu measurement studies and joint IAEA support program activities; (3) information management and analysis tools; (4) safeguards analytical laboratory support; (5) study of the safeguards approach for Embalse; (6) expansion of the remote monitoring system at Embalse; (7) use of ground-penetrating radar technology at Embalse; and (8) computerized material control and accounting tools for Pilcaniyeu

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

International Nuclear Information System (INIS)

Koelzer, W.

1993-05-01

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.) [de

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

International Nuclear Information System (INIS)

Rudelli, M.D.

1979-04-01

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.) [es

EFFECT OF CENTRAL MASS CONCENTRATION ON THE FORMATION OF NUCLEAR SPIRALS IN BARRED GALAXIES

International Nuclear Information System (INIS)

Thakur, Parijat; Jiang, I.-G.; Ann, H. B.

2009-01-01

We have performed smoothed particle hydrodynamics simulations to study the response of the central kiloparsec region of a gaseous disk to the imposition of nonaxisymmetric bar potentials. The model galaxies are composed of three axisymmetric components (halo, disk, and bulge) and a nonaxisymmetric bar. These components are assumed to be invariant in time in the frame corotating with the bar. The potential of spherical γ-models of Dehnen is adopted for the bulge component whose density varies as r -γ near the center and r -4 at larger radii and, hence, possesses a central density core for γ = 0 and cusps for γ>0. Since the central mass concentration of the model galaxies increases with the cusp parameter γ, we have examined here the effect of the central mass concentration by varying the cusp parameter γ on the mechanism responsible for the formation of the symmetric two-armed nuclear spirals in barred galaxies. Our simulations show that the symmetric two-armed nuclear spirals are formed by hydrodynamic spiral shocks driven by the gravitational torque of the bar for the models with γ = 0 and 0.5. On the other hand, the symmetric two-armed nuclear spirals in the models with γ = 1 and 1.5 are explained by gas density waves. Thus, we conclude that the mechanism responsible for the formation of symmetric two-armed nuclear spirals in barred galaxies changes from hydrodynamic shocks to gas density waves as the central mass concentration increases from γ = 0 to 1.5.

Un caso de estudio de impacto ambiental: el embalse de Vallfornés. Cataluña-España

Directory of Open Access Journals (Sweden)

Pinedo, Alejandro

1990-10-01

Full Text Available Environmental impact studies are used as a tool in project development to attain an adequate integration of the proposed activities in their environments so that adverse effects that are likely to affect the environmental quality can be avoided or reduced. The Vallfornés reservoir project case, whose main objective is storing water for irrigation, has al so the peculiarity of being located in the Montseny Natural Park (Catalonia, Spain thus needing not only a careful treatment of the projected works, but also the resolution of the unavoidable conflicts that can arise related to the Natural Park regulations. This paper focuses on the main aspects of the environmental Impact study of this reservoir project: Natural Park regulations that could affect the project, environmental characterization of the area, Identification, characterization and assessment of environmental impacts, and recommendations for reducing or avoiding impacts.

Los estudios de impacto ambiental surgen de la necesidad de proyectar las actividades de la forma más adecuada posible, que facilite su integración en el medio natural en que han de inscribirse para que su calidad no se vea afectada. El caso del embalse de Vallfornés, cuya finalidad principal es el abastecimiento de agua para regadío, presenta además la peculiaridad de afectar a terrenos Incluidos dentro del Parque Natural de Montseny, lo que obliga no sólo a un tratamiento cuidadoso de la obra, sino también a la resolución de conflictos inevitables con la normativa existente. En el presente artículo se pasa revista a los principales aspectos del estudio de impacto ambiental de dicho embalse: análisis de las implicaciones derivadas de su ubicación en terrenos del Parque Natural del Montseny, caracterización del medio afectado, identificación de las acciones productoras de impacto, caracterización y valoración de los mismos y recomendaciones respecto a la corrección de los impactos potenciales.

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

International Nuclear Information System (INIS)

Paulin, Ph.

2006-01-01

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)

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

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Ángel Miguel Castro

2004-07-01

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 alimentario para las truchas. La condición uniforme no es similar a las condiciones originarias de las truchas ya que la estacionalidad climática promueve una eutroficación de los hábitats mientras que la uniformidad de condiciones da como origen una disponibilidad de alimento semejante en todo el año. A través del desarrollo de este estudio se observó que la oferta  limenticia favorece los individuos de las tallas 23,2 cm a la 28,3 cm, además de que la zona litoral del embalse es la abastecedora del alimento y que son los insectos el ítem más importante dentro de su espectro

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

International Nuclear Information System (INIS)

Quilici, Domingo F.

2008-01-01

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) [es

Site of the First Spanish Nuclear Power Stations; Los Emplazamientos de las Primeras Centrales Nucleares Espanolas

Energy Technology Data Exchange (ETDEWEB)

Pascual, F.; Alonso, A.; Norena, S.; Sevilla, A. [Junta de Energia Nuclear, Madrid (Spain)

1967-09-15

The authors analyse and describe the sites of three Spanish nuclear power stations: the Zorita station (153 M W (e )) with a pressurized water reactor and single containment; the Santa Marfa de Garofia station (380 MW (e)), with a boiling water reactor and containment by steam condensation; and the Vandellos station (480 MW(e)), with a graphite-moderated gas-cooled reactor and integrated design of the EDF-4 type. The first two are located in the interior of the country and the third on the Mediterranean coast. The paper discusses the normal criteria and the safety considerations governing the choice of site, and points out the influence of Spanish orography on the transport of heavy equipment and hence its repercussions on the selection of power station sites. Reference is made to the experience acquired in transporting equipment for the Z-orita plant, and an analysis of the practical difficulties encountered in applying particular safety standards to the sites of stations of different types and designs is included. As the type of reactor and its containment system affect the practical value of applying particular standards which, moreover, have to be adapted to the special features of each country, safety standards for assessing power station sites should be applied in an appropriate and flexible manner. The paper describes the geological and meteorological features of the three sites and summarizes the studies carried out in these fields. It refers particularly to the hydrological studies carried out at Zorita and Santa Maria de Garofia and describes the weather stations set up at both sites, the diffusion experiments with neutcal-buoyancy balloons at Santa Maria de Garofia, and the results of these investigations. (author) [Spanish] Se analizan y describen los emplazamientos de tres centrales nucleares espanolas: la central de Zorita, de 153 MW(e), con reactor de agua a presion y sistema de contencion simple; la central de Santa Maria de Garofia, de 380 MW

Fenología reproductiva y dispersión de semillas del arbusto altoandino Monnina salicifolia R&P (Polygalaceae) en el embalse San Rafael La Calera - Cundinamarca

OpenAIRE

María Paola Sánchez Romero

2002-01-01

RESUMENMonnina salicifoliaR&P (Polygalaceae) se reporta como una de las tres especies más abundantesy representativa en la dispersión de semillas por aves en la zona del Embalse San Rafael, LaCalera. Es una especie que presenta fenofases reproductivas de forma simultánea y siendo am-pliamente consumida por aves, por lo que se le podría atribuir como especie clave en la regene-ración de áreas disturbadas, y considerada como pionera en los procesos de sucesión. Entreseptiembre de 2001 y agosto ...

Fenología reproductiva y dispersión de semillas del arbusto altoandino Monnina salicifolia R&P (Polygalaceae) en el embalse San Rafael La Calera - Cundinamarca

OpenAIRE

Sánchez Romero María Paola

2002-01-01

RESUMENMonnina salicifoliaR&P (Polygalaceae) se reporta como una de las tres especies más abundantesy representativa en la dispersión de semillas por aves en la zona del Embalse San Rafael, LaCalera. Es una especie que presenta fenofases reproductivas de forma simultánea y siendo am-pliamente consumida por aves, por lo que se le podría atribuir como especie clave en la regene-ración de áreas disturbadas, y considerada como pionera en los procesos de sucesión. Entreseptiembre de 2001 y ago...

El tecno-complejo del Embalse de Urrúnaga (Álava. Nuevas aportaciones al conocimiento de las sociedades del Paleolítico inferior en el norte de la Península Ibérica

Directory of Open Access Journals (Sweden)

Javier FERNÁNDEZ-ERASO

2017-01-01

Full Text Available En este trabajo se presenta una nueva colección lítica adscrita al Paleolítico inferior recuperada en el embalse de Urrúnaga (Álava, País Vasco, España. Consta de 70 artefactos que han sido estudiados conforme a los parámetros de la Tipología Analítica a partir de las estructuras de análisis; Petrológica, Modal-Morfológica, Tecnológica y Tipométrica. A partir de este estudio integral e interdisciplinar se han podido comprender los procesos de captación de materias primas y las diferentes dinámicas de talla a la hora de elaborar los diferentes artefactos. De este modo, el tecno-complejo aquí presentado, supone un nuevo aporte al conocimiento de las comunidades inferopaleoliticas en un territorio donde escasean las evidencias arqueológicas de este periodo cronológico. Además pone de manifiesto la importancia del emplazamiento en el que se sitúa el embalse como un lugar de paso obligado para la comunicación entre el interior meseteño, valle del Ebro y la costa.

Centralized operation and monitoring system for nuclear power plants

International Nuclear Information System (INIS)

Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

1988-01-01

According to the prospect of long term energy demand, in 2000, the nuclear power generation facilities in Japan are expected to take 15.9% of the total energy demand. From this fact, it is an important subject to supply nuclear power more stably, and in the field of instrumentation and control, many researches and developments and the incessant effort of improvement have been continued. In the central operation and monitoring system which is the center of the stable operation of nuclear power plants, the man-machine technology aiding operators by electronic and computer application technologies has been positively developed and applied. It is considered that hereafter, for the purpose of rationally heightening the operation reliability of the plants, the high quality man-machine system freely using the most advanced technologies such as high reliability digital technology, optical information transmission, knowledge engineering and so on is developed and applied. The technical trend of operation and monitoring system, the concept of heightening operation and monitoring capability, the upgrading of operation and monitoring system, and the latest operation, monitoring and control systems for nuclear power plants and waste treatment facilities are described. (K.I.)

Sea transport of used nuclear fuel and radiactive disposals to a Swedish central store

International Nuclear Information System (INIS)

1977-10-01

Sea transport of used nuclear fuel and radioactive disposals to a Swedish central store. A vessel for transporting used nuclear fuel and radioactive disposals from the power stations at Ringhals, Barsebaeck, Simpevarp and Forsmark to a central store has been projected. Safety aspects, technical and economical aspects have been taken into consideration with regard to the actual volume of goods to be transported. Three different types of vessels are presented and a specification is given for the main alternative. A safety study of the main alternative is shown, regarding collision safety, fire risks and fire extinguishing equipment. (author)

Central depression of the nuclear charge distribution

International Nuclear Information System (INIS)

Friedrich, J.; Voegler, N.; Reinhard, P.G.

1986-01-01

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.)

Proyecto de una nave de usos múltiples de 450 m2 para el servicio del Embalse de Requejada (Palencia) empleando tecnología BIM

OpenAIRE

Calleja Ramos, Enrique

2016-01-01

En este trabajo de fin de grado se ha desarrollado el proyecto completo de una obra de nueva construcción de una instalación industrial de 450 m2 de planta situada en la localidad de Cervera de Pisuerga (Palencia). Dicha instalación industrial estará dispuesta para usos múltiples y estará destinada a prestar servicio a las instalaciones del Embalse de la Requejada. Los estudios que se han desarrollado en dicho proyecto han sido el cálculo estructural, la distribución en planta y el cálculo d...

Formación y pronóstico del precio diario de la energía eléctrica en la cadena Nare-Guatapé-San Carlos

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Alejandro Romero

2003-01-01

Full Text Available Este trabajo plantea tres tipos de metodologías para la comprensión y pronóstico de los precios diarios de la energía eléctrica de la cadena Nare-Guatapé-San Carlos: modelo lineal multivariado, modelo autorregresivo determinístico y descomposición en series de Fourier. El precio de la energía eléctrica de una central depende no solamente del nivel del embalse y del caudal del río propio, sino también del embalse y sus respectivos afluentes aguas abajo o aguas arriba. En cuanto al pronóstico de los precios estos se pueden modelar con un proceso autorregreviso. El pronóstico sigue la tendencia y captura de los precios con aceptable precisión, especialmente para los valores máximos debido a los bajos caudales y volúmenes de embalse y teniendo en cuenta la variabilidad del precio para embalses de regulación diaria, semanal y mensual.

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

International Nuclear Information System (INIS)

Valle, Antonio Torres; Oliva, Jose de Jesus Rivero

2012-01-01

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)

Fenología reproductiva y dispersión de semillas del arbusto altoandino Monnina salicifolia R&P (Polygalaceae) en el embalse San Rafael, La Calera, Cundinamarca, Colombia

OpenAIRE

María Paola Sánchez Romero; Orlando Vargas Ríos

2004-01-01

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...

Fenología reproductiva y dispersión de semillas del arbusto altoandino Monnina salicifolia R&P (Polygalaceae) en el embalse San Rafael, La Calera, Cundinamarca, Colombia

OpenAIRE

Vargas Ríos Orlando; Sánchez Romero María Paola

2004-01-01

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 ...

Composition and concentration of soluble and particulate matter in the coolant of the reactor primary cooling system of the Embalse nuclear power plant; Composicion y concentracion del material soluble y particulado en el refrigerante del SPTC de la central nuclear Embalse

Energy Technology Data Exchange (ETDEWEB)

Chocron, Mauricio; Garcia Rodenas, Luis; La Gamma, Ana M; Villegas, Marina [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Quimica; Fernandez, Alberto N; Allemandi, Walter; Manera, Raul; Rosales, Hugo [Nucleoelectrica Argentina SA (NASA), Embalse (Argentina). Central Nuclear Embalse

2000-07-01

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)

Communication and computer technologies for teaching physics in nuclear reactors

International Nuclear Information System (INIS)

Murua, C; Chautemps, A; Odetto, J; Keil, W; Trivino, S; Rossi, F; Perez Lucero, A

2012-01-01

In order to train personnel inn order to train personnel in Embalse Nuclear Power Plant, and provided that such training given primarily on the location of such a facility, we designed a pedagogical strategy that combined the use of conventional resources with new information technologies. Since the Nuclear Reactor RA-0 is an ideal tool for teaching Reactor Physics, priority was the use of it, both locally remotely. The teaching strategy is based on four pillar: -Lectures on the Power Plant (using a virtual classroom to support); -Remote monitoring of Ra-0 Nuclear Reactor parameters while operating (RA0REMOTO); -Use, through the Internet, of the Ra-0 Nuclear Reactor Simulator (RA0SIMUL); -Made in the Nuclear Reactor RA-0 of Reactor Physics practical. The work emphasizes RA0REMOTO and RA0SIMUL systems. The RA0REMOTO system is an appendix of the Electronic Data Acquisition System (SEAD) of the Nuclear Reactor RA-0. This system acquires signals from Reactor instrumentation and sends them to a server running the software that 'publish' the reactor parameters on the internet. Students may, during the lectures, monitor any parameter of the reactor while it operates, which allows teachers to compare theory with reality. RA0SIMUL is a simulator on the RA-0, which allows students to 'operate' a reactor analyzing the underlying physics concepts (author)

Security central processing unit applications in the protection of nuclear facilities

International Nuclear Information System (INIS)

Goetzke, R.E.

1987-01-01

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

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.

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

International Nuclear Information System (INIS)

Yussup, F.; Ibrahim, M. M.; Soh, S. C.; Hasim, H.; Haris, M. F.; 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

Efectos del enriquecimiento con N y P sobre la comunidad del fitoplancton en microcosmos de un embalse tropical (La Mariposa, Venezuela

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Ernesto J. González

1998-03-01

Full Text Available Para evaluar el efecto del enriquecimiento con nutrientes sobre la comunidad del fitoplancton del embalse La Mariposa (Venezuela, se establecieron microcosmos "in situ" durante 6 días. Los microcosmos consistieron en bolsas de polietileno con 10 l de agua epilimnética filtrada del embalse, sometidos a diferentes combinaciones de enriquecimiento con fósforo y nitrógeno, para así simular un proceso de eutroficación. Se determinaron las concentraciones de clorofila 'a', la concentración de nitrógeno total y fósforo total y la proporción numérica de los diferentes grupos del fitoplancton. Como consecuencia del enriquecimiento de nutrientes, se produjo un aumento en la biomasa del fitoplancton, siendo las respuestas más pronunciadas en los tratamientos donde ambos nutrientes estaban presentes. Los grupos Cryptophyta, Euglenophyta y Pyrrophyta desaparecieron de los microcosmos fertilizados al finalizar el período de estudio, mientras que las Chlorophyta y las Cyanobacteria aumentaron sus proporciones relativas. Las diatomeas disminuyeron su proporción relativa a altas concentraciones de nitrógeno. Aunque la técnica del microcosmos tiene limitaciones en su significado ecológico, permite obtener una valiosa aproximación para entender lo que ocurre en las situaciones naturales.The effect of nutrient enrichment (N and P on the phytoplankton community of La Mariposa reservoir (Venezuela was studied. Polyethylene bags (microcosms were filled with 10 l of filtered epilimnetic water of the reservoir, and enriched with different nutrient proportions, simulating an eutrophication process. Chlorophyll 'a', total nitrogen, total phosphorus, and phytoplankton abundance were determined. There was an increase in phytoplankton abundance because of nutrient enrichment, specially when both nutrients were present. After the experiments, Cryptophyta, Euglenophyta, and Pyrrophyta dissappeared from the microcosms, whereas Chlorophyta and Cyanobacteria

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

International Nuclear Information System (INIS)

Pande, Savita

1998-01-01

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

Behavioral Determinants of Russian Nuclear State-Owned Enterprises in Central and Eastern European Region

OpenAIRE

Vlcek, Tomas; Jirusek, Martin

2015-01-01

Rosatom State Nuclear Corporation play a substantial role in the energy sector of the Central and Eastern European region and the behavioral characteristics of the company forms the basis of this article. Rosatom is positioned as the dominant provider of nuclear technology and fuel supplies to the region, in large part stemming from the Soviet legacy in CEE countries. Compounding this challenge, nuclear energy is one of the major sources of power generation in CEE. Given the long-time, near m...

Determinación de indicadores de eutrofización en el embalse Río Tercero, Córdoba (Argentina Determination of trophic indicators in Rio Tercero reservoir, Cordoba (Argentina

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Claudia Ledesma

2013-09-01

Full Text Available La eutrofización es una de las problemáticas ambientales más importantes de lagos y embalses. El embalse Río Tercero (Argentina se encuentra afectado por diversas actividades antrópicas que impactan negativamente sobre el recurso. A la hora de generar un programa de monitoreo de los sistemas acuáticos, una de las consideraciones más importante es poder definir las variables más significativas. El análisis multivariado se presenta como una herramienta alternativa. El objetivo de este trabajo fue determinar la calidad del agua y estado trófico del embalse Río Tercero, con el fin de generar bases para una adecuada gestión de los recursos hídricos. Se realizaron campañas de muestreos durante los años 2003 a 2006 donde se midieron parámetros de calidad del agua. Se determino el estado trófico del reservorio. Se realizó un análisis multivariado, generando una matriz de correlación y un análisis de componentes principales (ACP. El embalse experimentó un deterioro en su calidad, pasando desde un estado de mesotrófico a eutrófico. Se demostró que existe correlación positiva entre la clorofila- a y las variables fósforo total (r = 0.83, oxigeno disuelto (r = 0.51 y temperatura (r = 0.43. El ACP explicó el 65,6% de la variabilidad total de los datos. El análisis multivariado estableció que las variables más significativas para explicar la variabilidad en el reservorio fueron clorofila-a, fósforo total y temperatura, lo que demuestra que los florecimientos algales deberían ocurrir en las estaciones primavera-verano. Los resultados obtenidos permiten generar un programa preliminar de monitoreo y gestión extrapolable a otros recursos acuáticos.Eutrophication is one of the most important environmental problems in lakes and reservoirs. Río Tercero reservoir (Argentina is affected by various human activities that impact negatively on the system. When generating a monitoring program of aquatic systems, one of the most important

ESTUDIO AUTECOLÓGICO DE SCHROEDERIA SETIGERA EN EL EMBALSE TROPICAL RIOGRANDE II, ANTIOQUIA, COLOMBIA

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JOHN J. RAMÍREZ-RESTREPO

2015-01-01

Full Text Available El propósito de esta investigación es conocer la dinámica de Schroederia setigera en las escalas espacial y temporal, determinar cuáles son las causas próximas de su dinámica poblacional, y localizar el organismo en el sistema de Asociaciones de Reynolds y en el de Grupos Morfo-Funcionales. La investigación fue efectuada en el embalse Riogrande II (6°35'57'' - 6°28'79'' Norte, 75º32'17'' - 75° 25'85'' Oeste cuyo tiempo medio de retención es de 72.8 días. En él se muestrearon cinco estaciones a intervalos quincenales durante un año (julio 2002 a julio 2003 en las que se obtuvieron datos de tres variables climáticas, cinco físicas y 15 químicas. Para la especie se calcularon sus tasas media de crecimiento y renovación, el tiempo de generación medio, el tipo de crecimiento, y la disposición espacial y temporal. Para la relación entre las variables biológicas y las ambientales se utilizó un Análisis de Redundancia (RDA. En el tiempo el alga se ajustó a un patrón de tres 'picos' ocurridos en los periodos de menor pluviosidad en los que efectivamente los nutrientes se concentraron, el clima de luz se afectó. En las cinco estaciones la especie estuvo agrupada, y en el espacio su disposición fue aleatoria. Los primeros cuatro ejes del RDA incluyeron NO3-, SiO2, pH, SS, y %SO2, coeficiente de atenuación vertical para irradiancia descendente, Clorofila y diferentes competidores. S. setigera es un estratega tipo C que, al igual que otras clorococales, es un taxón característico de sistema eutróficos, poseedor de altas tasas de crecimiento y de cambio, tiempo de generación relativamente corto, y patrón de distribución temporal de contagio, por ende, regida por una ecología de no-equilibrio, más concentrada en los periodos de menor pluviosidad en los que efectivamente los nutrientes se concentraron y el clima de luz se afectó. En el espacio la especie mostró una distribución aleatoria debida al régimen de corrientes

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

International Nuclear Information System (INIS)

Koelzer, W.

1994-04-01

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.) [de

Modelo de Negocio Inclusivo para Producir Biogás y Abono orgánico a partir del Tratamiento Anaeróbico del Lechuguín del Embalse Daule Peripa

OpenAIRE

Espol; Cruz Cruz, Wladimir De La

2017-01-01

Esta propuesta es un intraemprendimiento para aportar a la base pirámide mediante un modelo inclusivo que impulse el desarrollo social y económico de las comunidades de la Manga del Cura. Para esto se instalará una planta piloto de biogás para la producción de abono orgánico a partir del proceso anaeróbico del lechuguín del embalse Daule Peripa y su principal objetivo son los agricultores de ástas comunidades. Guayaquil Magíster en Administración de Empresas

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)

Gortnar, O.; Stritar, A.

1999-01-01

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

Qualification of FFA treatment for the water-steam cycle as an innovative lay-up strategy for the long term outage of a CANDU-6 reactor

International Nuclear Information System (INIS)

Ramminger, Ute; Fandrich, Jörg; Sainz, Ricardo; Ovando, Luis; Herrera, Cecilia; Mendizabal, Maribel; Dumon, Adriana; Chocron, Mauricio

2014-01-01

of this plant. This work has been carried out by the refurbishment group and plant operator personnel (Central Nuclear Embalse, N.A.S.A.), AREVA GmbH and CNEA experts to implement the FFA treatment before steam generator replacement. (author)

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

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)

Getzner, M.

2003-01-01

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.)

Nuclear legislation in central and eastern europe and the NIS

International Nuclear Information System (INIS)

2003-01-01

This study presents the current state of legislation and regulations governing the peaceful uses of nuclear energy in the central and eastern European countries (CEEC) and the New Independent States (NIS). It also contains information on the national bodies responsible for the regulation and control of nuclear energy. The nuclear energy sector has not escaped from the changes that have affected the political, economic and social climates over the past fifteen years. Under the former socialist regime, activities in this field came within the sole remit of the State administration. In the legal area, it had not been deemed necessary in most of these countries to enact laws guaranteeing democratic control of electronuclear programmes and establishing a clear distinction between activities promoting this source of energy and regulatory control, while ensuring that safety imperatives take priority over all other considerations. With the arrival of new political forces came the will to remedy this situation promptly by creating new regulatory structures and drafting legislative texts based on those used in western countries. This evolution was all the more necessary given that, at the same time, the new policy of accountability had revealed safety defects in numerous nuclear installations in these countries, thus rendering international assistance indispensable. From the legal point of view, the outcome of these years of effort is remarkably positive: almost all countries of Eastern Europe pursuing electronuclear programmes have established institutions capable of exercising efficient control over nuclear power plants and other installations. Accession to the international conventions which form the backbone of nuclear law has become widespread. Modern legislation is henceforth in place in almost all of these states. (author)

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

International Nuclear Information System (INIS)

Idrisov, E.A.; Eleukenov, D.Sh.

1997-01-01

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

Operating practical experience at Argentina

International Nuclear Information System (INIS)

Quihillalt, Oscar

1997-01-01

Operating experiences of Atucha-1 and Embalse Nuclear Power Plants were discussed in this work. The technical and economic aspects, such as reliability, availability, personnel training, operating costs, prices and market, which exercise influence upon Argentina nuclear energy policy, mainly on the power electric generation by nuclear power plants were considered. Finally the current status of the nucleoelectric sector in Argentina and forecasting were analysed

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

Status of the initiative to create a nuclear-weapon-free space in Central and Eastern Europe

International Nuclear Information System (INIS)

Sychou, A.

1997-01-01

The aims of Belarus proposal for creating the nuclear-weapon-free zone in Central and Eastern Europe which has already been reflected in official documents of the 51st session of the UN General Assembly are described. This could reaffirm the intention of the European States to move towards the final goal of achieving general and complete nuclear disarmament under efficient international control

Analysis of occupational doses in radioactive and nuclear facilities

International Nuclear Information System (INIS)

Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

1996-01-01

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

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

Undergraduate teaching of nuclear medicine: a comparison between Central and Eastern Europe and European Union countries

International Nuclear Information System (INIS)

Lass, P.; Scheffler, J.; Bandurski, T.

2003-01-01

This paper overviews the curricula of nuclear medicine (NM) undergraduate training in 34 Central and Eastern European (CEE) and 37 European Union (EU) medical faculties. The data show enormous variation in the number of hours devoted to nuclear medicine, varying between 1-2 to 40 hours and highly differentiated concepts/ideas of nuclear medicine training in particular countries. In most EU countries this teaching is integrated with that of radiology or clinical modules, also with training in clinical physiology. In many CEE countries teaching and testing of NM are independent, although integration with other teaching modules is frequent. The paper discusses the differences in particular approaches to nuclear medicine teaching. (author)

Operating practical experience at Argentina; Experiencia practica operativa en la Argentina

Energy Technology Data Exchange (ETDEWEB)

Quihillalt, Oscar [Nucleoelectria Argentina S.A., Buenos Aires (Argentina)

1998-12-31

Operating experiences of Atucha-1 and Embalse Nuclear Power Plants were discussed in this work. The technical and economic aspects, such as reliability, availability, personnel training, operating costs, prices and market, which exercise influence upon Argentina nuclear energy policy, mainly on the power electric generation by nuclear power plants were considered. Finally the current status of the nucleoelectric sector in Argentina and forecasting were analysed. 3 figs., 5 tabs.

Activities for the life management of nuclear power plant in Argentina

International Nuclear Information System (INIS)

Chocron, M.; Fabbri, S.; Versaci, R.A.

2003-01-01

Since September 1994 the organisation of Argentine nuclear power activities includes the following entities: Argentine Nucleo Electric S.A (NASA) with operates two NPPs (Atucha-1 and Embalse), National Regulatory Board of Nuclear Activities (ARN), National Atomic Energy Commission Commission (CNEA) Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to NASA for NPP operation. Works on Life Management of NPPs are included in these activities. In the past, NPP Life Management in Argentina was mainly based on the corrective maintenance concept based on the replacement of damaged part detected during the periodical outages. In recent times, as a consequential of an increasing concern about ageing a Subprogram was created to take care of these subjects. The subprogram, now in the first steps, comprise several tasks: The first task involves the identification of components ageing mechanism and materials likely to age. In the area of mechanical components. a starting point is matrix involving major components such as: Reactor Pressure Vessel, Reactor Internals, Steam Generators, Pressure Tubes, Piping, etc. In this work the apply methodology for the selection of the components will be presented. (Full text)

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.

Sharing of responsibilities between central and local authorities with regard to the licensing of nuclear installations

International Nuclear Information System (INIS)

Peltzer, P.

1986-01-01

With regard to sharing of responsibility in the field of nuclear licensing between central and local authorities, the Belgian State has entered into a new phase of regionalisation since the enactment of the law of August 8, 1980. This might entail a conflict of competence in case of the licensing of nuclear power plants. A general survey of foreign legislations seems to indicate that a similar risk also exists in other countries. (CW) [de

The central dose register for the nuclear industry in Sweden

International Nuclear Information System (INIS)

Widell, C.-O.

1978-06-01

The central dose register for the nuclear industry in Sweden has been in operation since 1974. The system contains today about 18 000 persons in the register. The dose information is stored on discs on a CDC Cyber 172 computer and all information to and from the system is handled by terminals at the different nuclear sites. The terminals are connected to the computer by normal telephone lines. Most doses are recorded on TLD. The data from the TLD readers is automatically transferred to the computer via punched tape and the local computer terminal. The dose results are stored under the person's unique social security number. It is also possible to use social security number systems of other countries. The dose register system also supervises the condition of the readers and their calibration by circulation dosimeters which have been given a reference dose. The information from the system can be obtained on many different types of lists, for example, annual, quarterly, monthly, departementally, personal history, job number. (author)

Flow of ideal fluid through a central region of a nuclear reactor wire-spaced fuel subassembly

International Nuclear Information System (INIS)

Schmid, J.

1991-04-01

The results are given of calculations of the flow of an ideal fluid through the central region of a nuclear reactor wire-spaced fuel subassembly. The computer code used is briefly described. (author). 10 figs., 4 refs

Decree N0 73-322 of 15 March 1973 concerning insurance and reinsurance of exceptional and nuclear risks by the Central Reinsurance Fund

International Nuclear Information System (INIS)

1973-01-01

This Decree provides that the Central Reinsurance Fund may cover, with the State guarantee, risks for which operators of nuclear ships and installations are liable and concerning which State intervention is provided for by legislation. These operations relate in particular to goods carried, nuclear installations and property on the site of such installations. The Decree sets up an Advisory Commission for the Central Reinsurance Fund regarding security for exceptional and nuclear risks and repeals a 1967 Decree on insurance of exceptional risks. (NEA) [fr

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

International Nuclear Information System (INIS)

Canoba, A.C.; Lopez, F.O.; Bruno, H.A.

1998-01-01

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) [es

Transport of Co-60 from Argentina to abroad

International Nuclear Information System (INIS)

Cesario, R.; Pinamonti, M.

1993-01-01

The Co-60 bearing wastes from the Embalse Nuclear Power Plant, Argentina are transported to Canada, the United States and Mexico. Ocean transportation, terrestrial transportation, air transportation are applied, and the total activity in bulk material shipped reached 2.96x10 17 Bq. (J.P.N.)

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

International Nuclear Information System (INIS)

Tomik, L.; Kichev, E.

2003-01-01

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

Initial basis for agronomic countermeasure selection following a nuclear accident

International Nuclear Information System (INIS)

Bonetto, Juan P.; Kunst, Juan J.; Bruno, Hector; Jordan, Osvaldo; Hernandez, Daniel

2008-01-01

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 decision-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. (author)

Initial Basis for Agronomic Countermeasure Selection Following a Nuclear Accident

International Nuclear Information System (INIS)

Bonetto, J.P.; Kunst, J.J.; Bruno, H.A.; Jordan, O.D.; Hernandez, D.G.

2011-01-01

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)

Deformation of in-service pressure tubes

International Nuclear Information System (INIS)

Sarce, A.L.

1993-01-01

Candu type nuclear reactor pressure tubes suffer deformations during operation. This are consequences of irradiation growth and creep. By means of a computer code which takes into account the material microstructure, the above mentioned deformations are calculated, and results are compared with corresponding values measured at Embalse nuclear power plant. The calculations make explicit inclusion of intergranular stresses caused by an isotropy in the material. (author). 1 ref

El pez Trachelyopterus striatulus (Siluriformes: Auchenipteridae como herramienta de muestreo de la entomofauna en un embalse tropical

Directory of Open Access Journals (Sweden)

Alejandra Filippo Gonzalez Neves dos Santos

2009-12-01

Full Text Available El objetivo de este trabajo fue hacer un levantamiento entomofaunístico, en un embalse Tropical, utilizando como organismo indicador al pez Trachelyopterus striatulus. Fue analizada la dieta de 383 T. striatulus, muestreados desde abril de 1999 hasta marzo de 2000. La Frecuencia de presencia y el porcentaje de similitud de Schoener fueron aplicados para analizar la dieta. Para identificar variaciones de la entomofauna entre las estaciones del año y las zonas del embalse fueron aplicadas estadísticas univariadas y multivariadas. La dieta estuvo compuesta principalmente por insectos (92.14% siendo los más frecuentes (%FO: Hymenoptera (57.90%, Odonata (39.76%, Trichoptera (27.41%, Ephemeroptera (26.25% y Coleoptera (28.96%. Formicidae fue dominante en todas las estaciones del año, en especial en la primavera, mientras, Trichoptera y Ephemeroptera fueron más consumidos en las demás estaciones del año. En la zona alta, predominaron Trichoptera y Ephemeroptera, mientras en las zonas baja e intermedia predominaron Formicidae y Belostomatidae. T. striatulus presenta potencial como muestreador de la entomofauna contribuyendo para el conocimiento de la biología y ecología de los insectos y la ecología trófica de los organismos acuáticos.The fish Trachelyopterus striatulus (Siluriforms: Auchenipteridae used to sample insects in a tropical reservoir. The study of aquatic environments is sometimes difficult to do with normal sampling methods that use gears. Insectivorous fishes represent good users of these ecosystems and analyzing the aquatic organisms present in fish stomachs, is an alternative way to determine resource abundance and utilization. In this paper, the potential of Trachelyopterus striatulus as an insect sampler was examined through dietary analyses of 383 individuals caught between April 1999 and March 2000 in Lajes Reservoir, a 30 km² oligotrophic impoundment in Southeast Brazil. We estimated frequency of occurrence and

Pressure test at the reactor building of the Embalse Nuclear Power Plant (CNE)

International Nuclear Information System (INIS)

Coutsiers, E.E.; Perrino, J.; Moreno, C.; Batistic, J.A.; Lolis, R.R.; Aviles, A.

1991-01-01

Upon request by the Licensing Authority, the reactor building (RB) in a nuclear power plant must be submitted to pressure tests. One of these tests is to be performed before startup and, then, a test must be carried out every 5 years in operation. The pre-operational tests took place in August 1981, under two values of relative pressure: 1.266 kg/cm 2 and 0.422 kg/cm 2 . Operational tests must only be made at the lower pressure and their objective is to verify that the loss speed remains within the range indicated in the corresponding technical specification. The first operational test was performed in August 1989. The personnel of the CNE took care of the preparation of the Work Plan, of aligning the various systems contained in the RB, of pressurization, of monitoring localized tightedness, of depressurization and of the general and quality control of the test. The measurements were carried out by the CISME (Center of Metrology Research and Service) of the National Institute of Industrial Technology (INTI) , which did also supply the necesary instruments and the data collection system. There is also a description of the work performed before the test, of the calculation method used for assessing the loss rate, of the test sequencies and of the results obtained. (Author) [es

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)

1977-01-01

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) [fr

Domestic nuclear fuels supply: possibility of an independent technology

International Nuclear Information System (INIS)

Cirimello, R.O.

1982-01-01

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 UO 2 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: UO 2 pellets fabrication with UO 2 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.) [es

ESTABLECIMIENTO DEL NUTRIENTE LIMITANTE CON BASE EN LOS CAMBIOS DE LA ESTRUCTURA DEL ENSAMBLAJE FITOPLANCTÓNICO EN UN EMBALSE TROPICAL COLOMBIANO

Directory of Open Access Journals (Sweden)

JOHN J RAMÍREZ-R

2012-12-01

Full Text Available En un experimento de eutrofización artificial, se adicionó Nitrógeno en tres concentraciones y Fósforo en cuatro a muestras de agua de la superficie del embalse La Fe, con el fin de establecer el nutriente limitante para el ensamblaje fitoplanctónico. El agua enriquecida se colocó en bolsas plásticas transparentes de dos litros. Las colectas se llevaron a cabo quincenalmente (n = 12 durante seis meses. Se calcularon los valores de la serie de números de Hill, los de riqueza y los de equidad. Fueron construidas curvas de rango-abundancia cuya pendiente fue hallada mediante transformación lineal de las mismas. Con el fin de confirmar las hipótesis referentes a la variabilidad entre tratamientos, se usó un diseño de bloques con los tiempos de muestreo como variable de bloqueo. Los taxones encontrados correspondieron a 2 cianobacterias, 21 clorofitas, 13 diatomeas, 1 dinoflagelado y 2 criptofitas. La fertilización ocasionó que grupos como Cryptophyta, Dinophyta, Desmidiales y Zygnematales presentaran muy poca densidad y que las Euglenophyta nunca estuvieran presentes. Los cambios en la uniformidad del ensamblaje fitoplanctónico frente con la eutrofización fueron altamente significativos (α = 0.0309. La riqueza no mostró cambios significativos con el enriquecimiento (α = 0.4940. Por su parte, la velocidad de respuesta coincidió en términos generales con lo mostrado por la equidad; la significancia de los cambios en las pendientes ente tratamientos fue significativa (α = 0.0315. La respuesta general de las Chlorococcales al enriquecimiento fue la de incrementar su densidad a medida que la eutrofización prosperaba, para luego disminuir progresivamente hasta el último tratamiento; dicha respuesta fue altísimamente significativa (α = 0.0000. Aunque las cianobacterias del orden Chroococcales se comportaron en forma similar a las Chlorococales, su conducta no fue significativa entre tratamientos (α = 0.4347. Las Bacillariophyta

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

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, CS 90 046, St. Paul-lez-Durance, Cedex (France); Ambrosino, G. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); De Tommasi, G., E-mail: detommas@unina.i [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); Pironti, A. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy)

2010-07-15

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.

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

International Nuclear Information System (INIS)

Scibile, L.; Ambrosino, G.; De Tommasi, G.; Pironti, A.

2010-01-01

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.

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 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 fecales (EF por el método de filtración de membrana. Se utilizó el método estadístico de distribución log-normal y se calcularon medias logarítmicas, puntos percentiles, ratios CF:EF, Anova y coeficientes de correlación de Pearson. Resultados. Sólo dos muestras superaron los valores límites de CF en la estación del camping. Las ratios CF:EF fueron superiores (> 4 durante 2000-2002, e inferiores (< 0,7 durante 2003-2005. Sólo se observaron diferencias significativas (F = 3,41, ∝ < 0,01 para EF en el período 2000-2005. No se encontraron diferencias significativas (F = 3,395, ∝ < 0,01 en las concentraciones medias de los indicadores en ambos lugares de baño. Los recuentos CT y CF presentaron correlación significativa en El Kiosko, mientras que sólo se observó correlación significativa (t = 0,632, p < 0,05 para EF durante los años 2000, 2003 y 2005 en el camping.Conclusiones. El embalse Conde del Guadalhorce presenta condiciones higiénicas seguras para el baño. Globalmente, la calidad sanitaria del agua de baño es buena. Los indicadores CT, CF y EF cumplieron con la directiva durante 2000-2005, salvo CF en la estación del camping el año 2000. Las concentraciones CT y CF fueron frecuentemente mayores en el camping que en El Kiosko, lo que puede ser debido a la mayor influencia de bañistas y actividades recreativas. Hay una tendencia en el aumento de los niveles de EF, lo que apunta a una fuente de

Variación estacional del zooplancton del embalse Ignacio Allende, Guanajuato, México y su relación con el fitoplancton y factores ambientales

Directory of Open Access Journals (Sweden)

Eugenia López- López

1999-12-01

Full Text Available Se estudiaron las comunidades planctónicas y los factores ambientales del embalse Ignacio Allende de julio de 1990 a junio de 1991. Se presentó una proliferación de cianofíceas en el verano coincidente con el mayor nivel de agua, seguido por la dominacia de bacilariofíceas en los meses fríos, en primavera con el incremento en la temperatura las cloroficeas alcanzaron sus mayores densidades. Las dinofíceas y euglenofíceas presentaron la menor riqueza específica. La proliferación de Anabaena variabilis en el verano y la alta frecuencia de Ceratium hirundinella, Aulacosseira granulata y Fragilaria crotonensis se asocian con cuerpos de agua tropicales eutróficos. Se encontraron 39 taxones zooplanctónicos, de los cuales Diaphanosoma birgei, Bosmina longirostris, Daphnia parvula, Diaptomus (Mastigodiaptomus montezumae, Acanthocyclops vernalis, Keratella cochlearis, Polyarthra vulgaris y Asplanchna priodonta, fueron persistentes en todo el ciclo. Un análisis de correspondencias canónicas mostró las relaciones que guardan los cambios en composición del zooplancton con las características físicas y químicas del embalse.The plankton communities and environmental factors of the Ignacio Allende reservoir were surveyed from July 1990 to June 1991. A total of 57 phytoplankton species were identified. There was a blue green algae bloom in the summer, simultaneously with highest water levels, followed by the dominance of diatoms in the coldest months (February and March. Chlorophyceans became dominant in the spring, consonant with highest temperature records. Bacillariophyceans and cyanophyceans had the greater species richness, while dinophyceans and euglenophyceans had the lowest values. The summer bloom of Anabaena variabilis and the abundance of Ceratium hirundinella, Aulacosseira granulata and Fragilaria crotonensis are associated with tropical eutrophic waters. The zooplankton was composed by 39 species, from these, Diaphanosoma birgei

Estudio del impacto del cambio climático en los caudales de entrada al embalse del Río Frío

Directory of Open Access Journals (Sweden)

Mónica Tatiana Gómez Vargas

2016-01-01

Full Text Available Se evaluó cual podría ser la tendencia y la afectación en los caudales de entrada hasta el año 2100 del embalse que se tiene proyectado sobre el Río Frío para el abastecimiento de los municipios de Chía, Tenjo, Tabio, Cota y Cajicá considerando el RCP 4.5 y 8.5, los cuales describen dos caminos del forzamiento radiativo hasta el año 2100. Estos tuvieron en cuenta las series asociadas a las simulaciones realizadas en los modelos climáticos globales CCSM4, IPSL CM5A –LR y MIROC ESM y los RCP. Se realizaron análisis comparativos para saber si las demandas proyectadas hasta el año 2070 podrán cumplirse al considerar el cambio climático. Se puso en evidencia que las demandas estimadas son elevadas y tienen un crecimiento exponencial, mientras que la oferta que se estimó tiene valores pequeños que no son suficientes para satisfacer los requerimientos de abastecimiento. Los caudales de entrada se esperan que tengan disminuciones de aproximadamente un 20%.

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.

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)

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

2006-02-01

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

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

International Nuclear Information System (INIS)

Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos

2011-05-01

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

Nuclear power in eastern and central Europe. Background paper

International Nuclear Information System (INIS)

Myers, L.C.

1993-11-01

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

Nuclear power in eastern and central Europe. Background paper

Energy Technology Data Exchange (ETDEWEB)

Myers, L C [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

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.

Piping information centralized management system for nuclear plant, PIMAS

International Nuclear Information System (INIS)

Matsumoto, Masaru

1977-01-01

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.)

Pre and post garter spring repositioning ultrasonic inspection of pressure tubes

International Nuclear Information System (INIS)

Desimone, C.; Katchadjian, P.; Tacchia, Mauricio

1997-01-01

This paper present a description of the ultrasonic cracked hydride blister detections system used for pre and post inspection of pressure tubes during garter spring repositioning in CNE (Embalse Nuclear Power Station). Ultrasonic system setup configuration, transducers characteristics, blister detection head, calibration of parameters, operating procedure, records of ultrasonic inspections and evaluation. (author) [es

Measuring vibrations in fuel channels CNE

International Nuclear Information System (INIS)

Martín Ghiselli, A.; Fiori, J.; Sacchi, M.; Villabrille, G.

2013-01-01

This paper present a description of implementation and execution of vibration measurements made at the request of NUCLEOELECTRICA ARGENTINA S.A. on the ends of the reactor fuel channels of Embalse Nuclear Power Plant to explore possible differences between the dynamic behavior of empty fuel channel and with full charge of fuel elements inside. (author)

The ATC, the centralized temporary storage facility for the spanish nuclear spend fuel; El ATC, la instalación de Almacenamiento Temporal Centralizado de Combustible Nuclear Gastado Español

Energy Technology Data Exchange (ETDEWEB)

González Fernández-Conde, A.; Gónzalez Gandal, R.; Larrosa Peruga, O.; Medinilla Téllez, G.; Navarro Santos, M.

2016-07-01

The ATC, strategic project contained in the Sixth Radioactive Waste General Plan approved by the Government in 2006, is the temporary storage facility of centralized nature intended to store the spent nuclear fuel generated by Spanish NPP during their operation life, for other so-called special waste arising either from the ATC operation itself or from NPP dismantling, and for vitrified waste generated as a result of fuel reprocessing from Vandellós 1 NPP. The main functions of the ATC are the reception of transport casks, encapsulation of spent fuel, and storage of such canister in dry vaults with passive cooling by natural convection; and additionally, the temporary storage of storage casks with spent fuel, of other special waste in canisters, and finally of secondary waste generated during the operation of the facility. The facility estimated operation lifetime is 60 years, and its safety structures, systems and components are designed considering the requirements according to the Spanish nuclear regulations and using best international practices. In the detailed design, major Spanish and some foreign nuclear sector engineering companies are taking part. [Spanish] El ATC, proyecto estratégico recogido en el Sexto Plan General de Residuos Radiactivos aprobado por el Gobierno en 2006, es la instalación de almacenamiento temporal de carácter centralizado destinada para el combustible nuclear gastado generado por las centrales nucleares españolas durante su proceso de operación, así como de otros residuos denominados especiales originados por la propia operación o durante el desmantelamiento de las citadas centrales nucleares, así como los residuos vitrificados originados como consecuencia del reproceso del combustible de la central nuclear de Vandellós I. Las principales funciones del ATC son la recepción de los contenedores de transporte, encapsulado del combustible y almacenamiento de dichas cápsulas en bóvedas en seco con refrigeración pasiva por

THERMOS, district central heating nuclear reactors

International Nuclear Information System (INIS)

Patarin, L.

1981-02-01

In order to expand the penetration of uranium in the national energy balance sheet, the C.E.A. has been studying nuclear reactors for several years now, that are capable of providing heat at favourable economic conditions. In this paper the THERMOS model is introduced. After showing the attraction of direct town heating by nuclear energy, the author describes the THERMOS project, defines the potential market, notably in France, and applies the lay-out study to the Grenoble Nuclear Study Centre site with district communal heating in mind. The economic aspects of the scheme are briefly mentioned [fr

Reinforcement of planning and response to emergencies inside nuclear power plants; Refuerzo de la planificación y respuesta ante emergencias en el interior de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Cortés, M.A.; Garcés, J.M.; Bolaños, J.; Fernández, J.; Gutiérrez, C.; Pontejo, A.; Rosell, B.

2015-07-01

Fukushima Daichi nuclear accident (11th march of 2011) required a rapid and effective response of nuclear industry, in order to guarantee that current safety margins were enough to cope with events like this or even worse. In Europe, stress tests were carried out to comply with that objective, evaluating if every nuclear plant was able to succeed managing design basis accidents or even beyond. Stress-test results were satisfactory, although several areas for improvement where identified. Improvements in emergency response and management have been developed in several phases. First, increasing emergency response capacity by implementing modifications in existing equipment. Later, installing new equipment (generally portable) which would be used in even more degraded conditions. This must be held by the revision of emergency response personnel and their training. Finally, external support has been reinforced to help in longstanding emergencies, with the establishment of CAE (Regional Center), and collaboration protocols with the Army. These actions, supervised and approved by the Regulator Body (CSN) will lead to increase plants safety margins and their emergency response capacities in order to reduce probability and consequences of a nuclear accident to the minimum. [Spanish] El accidente nuclear ocurrido el 11 de marzo de 2011 en Fukushima Daichi requirió de una pronta y efectiva respuesta de la industria nuclear, que garantizase que los márgenes de seguridad eran los adecuados para hacer frente a sucesos de estas características o incluso peores. Con ese objetivo se planteó, a nivel europeo, la realización de unas pruebas de resistencia que valorasen si las centrales podían hacer frente con garantías a una serie de accidentes dentro y más allá de las bases de diseño. Los resultados fueron satisfactorios, si bien se identificaron varios aspectos de mejora. La mejora en la respuesta y gestión de emergencias de las centrales nucleares se ha planteado en

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

International Nuclear Information System (INIS)

Chocron, Mauricio; La Gamma, Ana M.; Fernandez, Narciso; Moyano, Ricardo; Schiersmann, Christian; Ovando, Luis E.; Sainz, Ricardo A.; Keitelman, Alberto

2003-01-01

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)

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.

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)

Safeguards evolution towards unattended c/s (containment and surveillance) systems

International Nuclear Information System (INIS)

Valentino, Lucia I.; Saavedra, Analia D.; Castro, Laura B.; Maceiras, Elena; Llacer, Carlos D.; Vicens, Hugo E.; Mairal, Maria L.; Fernandez Moreno, Sonia

2000-01-01

This paper shows the development and evolution of safeguards towards the use of different containment and surveillance (C/S) systems, which involve the possibility of working unattended. They are designed to transmit safeguards relevant data remotely. It is believed that they would increase safeguards efficiency while maintaining or even enhancing their effectiveness. At present, unattended C/S systems with or without remote transmission are in place at several installations. In addition, some other possible applications are being tested. One of these is the Remote Monitoring Systems (RMS) field trial at Embalse nuclear power plant to cover the transfers of spent fuel from the ponds to the dry storage. Some of the matters to be addressed are of general nature (i.e. applicable to any unattended/remote system) while others depend on the specific application in a nuclear installation. Among others, the following are particularly important: -) Sharing of data with the SSAC; -) Impact of a failure of the RMS on the operator, IAEA and the SSAC; -) Provision of relevant operational and accounting information; -) Review of the current safeguard approach for the selected installation; -) RMS cost-effectiveness assessment. This paper describes the status of the RMS field trial as well as the current C/S system in place at Embalse nuclear power plant. (authors)

A report on recent progress of Central Analytical Laboratory (NRI Rez plc.) for upgrading capabilities for identification of illicit nuclear materials

International Nuclear Information System (INIS)

Malek, Z.; Sus, F.

2002-01-01

Full text: In the first half of the 90's, the State Office for Nuclear Safety (SONS) -- in close co-operation with other state organizations and following the IAEA's extended safeguards system - strengthened its attention to the development of procedures for the characterization of unknown nuclear materials. This problem become important in the context of increasing danger of illicit trafficking of nuclear material which emerged with the political changes in former 'Comecon' countries during late 80's and 90's. Particular attention has been drawn to the upgrade of the counter-potential in possible transit countries situated in Central Europe. The Central Analytical Laboratory as the main Czech institution working in the field of nuclear material analytical chemistry participated in the development and upgrading of analytical procedures for detailed identification and characterization of nuclear material samples. The special methods for the determination of uranium content, isotopic composition, swipe sample analysis, determination of age and long-lived radioisotopes were developed. In second half of the 90's within the IAEA Project entitled 'Special Analytical Methods for Determination of Traces Radioactivity and Detection of Undeclared Nuclear Activities' basic procedures were prepared for the determination of: - selected isotopes of the natural disintegration series in the samples of water, sediments and technological waste solutions after termination of the uranium ores mining, - age of uranium and plutonium materials based on the 230 Th/ 234 Th, 226 Ra/ 234 U and 241 Am/ 241 Pu pairs, studies on the application of the 231 Pa/ 235 U pair were started. In 1998 PHARE PH5.01/95 project, 'Assistance in setting up special analytical services including a data bank for analysis of radioactive substances and nuclear materials of unknown origin' was started. The project was funded from the European Commission's PHARE Programme. The activities were performed at the

CENTRAL NUCLEAR ELECTRIC, A FUTURE OF ROMANIAN ENERGY

Directory of Open Access Journals (Sweden)

Gabriel I. NĂSTASE

2010-05-01

Full Text Available Official statistics show the year increasing the share of electricity produced in nuclear power plants. The most developed nuclear energy programs are: the United States, France, Japan, Germany and Canada. Although Romania was among the first countries in Eastern Europe that had a nuclear research program, switching to nuclear power reactors has been extremely difficult and slow. The implications of this decisionmaking process were the first political and then economic. There were a series of oscillations between Wer system offered by the USSR and the CANDU-PHWR supplied by Canada. Considering nuclear reactors Wer insufficiently protected against a nuclear accident, and the total requested by the former Soviet Union on the nuclear fuel cycle, the decision of us have opted for CANDU reactor, fueled with natural uranium, moderated and cooled with heavy water.

International remote monitoring project Argentina Nuclear Power Station Spent Fuel Transfer Remote Monitoring System

International Nuclear Information System (INIS)

Schneider, S.; Lucero, R.; Glidewell, D.

1997-01-01

The Autoridad Regulataria Nuclear (ARN) and the United States Department of Energy (DOE) are cooperating on the development of a Remote Monitoring System for nuclear nonproliferation efforts. A Remote Monitoring System for spent fuel transfer will be installed at the Argentina Nuclear Power Station in Embalse, Argentina. The system has been designed by Sandia National Laboratories (SNL), with Los Alamos National Laboratory (LANL) and Oak Ridge National Laboratory (ORNL) providing gamma and neutron sensors. This project will test and evaluate the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguards efficiency. This paper provides a description of the monitoring system and its functions. The Remote Monitoring System consists of gamma and neutron radiation sensors, RF systems, and video systems integrated into a coherent functioning whole. All sensor data communicate over an Echelon LonWorks Network to a single data logger. The Neumann DCM 14 video module is integrated into the Remote Monitoring System. All sensor and image data are stored on a Data Acquisition System (DAS) and archived and reviewed on a Data and Image Review Station (DIRS). Conventional phone lines are used as the telecommunications link to transmit on-site collected data and images to remote locations. The data and images are authenticated before transmission. Data review stations will be installed at ARN in Buenos Aires, Argentina, ABACC in Rio De Janeiro, IAEA Headquarters in Vienna, and Sandia National Laboratories in Albuquerque, New Mexico. 2 refs., 2 figs

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

International Nuclear Information System (INIS)

Gustafsson, M.; Webb, G.A.M.; )

1998-01-01

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.)

Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador

Energy Technology Data Exchange (ETDEWEB)

Olivieri, Luis E; Zanni, Pablo A [Nucleoelectrica Argentina SA (NASA), Lima (Argentina). Central Nuclear Atucha 1

2000-07-01

reduction (46 tubes). The exchanger has 1049 tubes. Personnel involved in the repair works came from different areas: Atucha I/II nuclear power plants, SPC Department, Embalse nuclear power plant, NASA Headquarters, CNEA and INVAP specialists. (author)

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

International Nuclear Information System (INIS)

Bendarag, A.

1999-01-01

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)

Quantification of aquifer properties with surface nuclear magnetic resonance in the Platte River valley, central Nebraska, using a novel inversion method

Science.gov (United States)

Irons, Trevor P.; Hobza, Christopher M.; Steele, Gregory V.; Abraham, Jared D.; Cannia, James C.; Woodward, Duane D.

2012-01-01

Surface nuclear magnetic resonance, a noninvasive geophysical method, measures a signal directly related to the amount of water in the subsurface. This allows for low-cost quantitative estimates of hydraulic parameters. In practice, however, additional factors influence the signal, complicating interpretation. The U.S. Geological Survey, in cooperation with the Central Platte Natural Resources District, evaluated whether hydraulic parameters derived from surface nuclear magnetic resonance data could provide valuable input into groundwater models used for evaluating water-management practices. Two calibration sites in Dawson County, Nebraska, were chosen based on previous detailed hydrogeologic and geophysical investigations. At both sites, surface nuclear magnetic resonance data were collected, and derived parameters were compared with results from four constant-discharge aquifer tests previously conducted at those same sites. Additionally, borehole electromagnetic-induction flowmeter data were analyzed as a less-expensive surrogate for traditional aquifer tests. Building on recent work, a novel surface nuclear magnetic resonance modeling and inversion method was developed that incorporates electrical conductivity and effects due to magnetic-field inhomogeneities, both of which can have a substantial impact on the data. After comparing surface nuclear magnetic resonance inversions at the two calibration sites, the nuclear magnetic-resonance-derived parameters were compared with previously performed aquifer tests in the Central Platte Natural Resources District. This comparison served as a blind test for the developed method. The nuclear magnetic-resonance-derived aquifer parameters were in agreement with results of aquifer tests where the environmental noise allowed data collection and the aquifer test zones overlapped with the surface nuclear magnetic resonance testing. In some cases, the previously performed aquifer tests were not designed fully to characterize

Cooperation in peaceful uses of nuclear energy among Turkey, Caucasian and Central Asian countries

International Nuclear Information System (INIS)

Zafer, A.

2006-01-01

Full text: On the first call 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 became the member of the International Atomic Energy Agency (IAEA) established in 1957 by the United Nations for spreading the use of nuclear energy to contribute peace, health and prosperity throughout the world, in the same year. 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 other countries and international organizations. In the late 1990's, TAEK, besides building cooperation with various countries, has involved in cooperating with related institutes of Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan for establishment of bilateral and multilateral scientific and technical cooperation in peaceful use of nuclear energy and signed protocols with Academy of Science of Azerbaijan, Nuclear Physics Institute of Kazakhstan, National Academy of Science of Kyrgyzstan and Institute of Nuclear Physics of Uzbekistan Academy of Science. Turkey is a candidate state to join the European Union and has already signed Custom Union Agreement, also part of the Eurasia Region. So, there are significant developments in the cultural, social, technical, economical and trade relations owing to our common historical and cultural values with the countries in the region and Central Asia. 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. The joint activities carried out mainly are given as follows: Eurasia Conference on Nuclear Science and Its Application - First Conference organized in the year 2000 in Turkey, Second Conference at Almaty? in

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

International Nuclear Information System (INIS)

Hendricks, J.R.

1996-01-01

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

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

International Nuclear Information System (INIS)

Ventura, M.

2006-01-01

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)

Artificial intelligence application to diagnosis and supervision of nuclear power plants. Aplicacion de la inteligencia artificial a la supervision y diagnostico de plantas nucleares de potencia

Energy Technology Data Exchange (ETDEWEB)

Corvalan, P J

1991-06-01

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).

Central Bureau for Nuclear Measurements

International Nuclear Information System (INIS)

1991-01-01

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 252 Cf 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 235 U, 233 U and 239 Pu, were finalised. The dependence of the experimental weighting function of C 6 D 6 detectors on thickness of several 56 Fe 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 9 Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192 Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO 2 ), 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. 10 B and 6 Li 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

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.

Artificial intelligence application to diagnosis and supervision of nuclear power plants

International Nuclear Information System (INIS)

Corvalan, P.J.

1991-06-01

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) [es

Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

International Nuclear Information System (INIS)

Wati, Nurokhim

2008-01-01

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)

Centralized digital computer control of a research nuclear reactor

International Nuclear Information System (INIS)

Crawford, K.C.

1987-01-01

A hardware and software design for the centralized control of a research nuclear reactor by a digital computer are presented, as well as an investigation of automatic-feedback control. Current reactor-control philosophies including redundancy, inherent safety in failure, and conservative-yet-operational scram initiation were used as the bases of the design. The control philosophies were applied to the power-monitoring system, the fuel-temperature monitoring system, the area-radiation monitoring system, and the overall system interaction. Unlike the single-function analog computers currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control-rod movements to conform with operator requests, automatically log the required physical parameters during reactor operation, perform the required system tests, and monitor facility safety and security. Reactor power control is based on signals received from ion chambers located near the reactor core. Absorber-rod movements are made to control the rate of power increase or decrease during power changes and to control the power level during steady-state operation. Additionally, the system incorporates a rudimentary level of artificial intelligence

Commercial nuclear power 1989

International Nuclear Information System (INIS)

1989-01-01

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

Root cause analysis of relevant events

International Nuclear Information System (INIS)

Perez, Silvia S.; Vidal, Patricia G.

2000-01-01

During 1998 the research work followed more specific guidelines, which entailed focusing exclusively on the two selected methods (ASSET and HPIP) and incorporating some additional human behaviour elements based on the documents of reference. Once resident inspectors were incorporated in the project (and trained accordingly), events occurring in Argentine nuclear power plants were analysed. Some events were analysed (all of them from Atucha I and Embalse nuclear power plant), concluding that the systematic methodology used allows us to investigate also minor events that were precursors of the events selected. (author)

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

International Nuclear Information System (INIS)

Kubota, Ryuji; Satoh, Hiroyuki; Sasajima, Katsuhiro; Kawano, Ryutaro; Shibuya Shinya

1999-01-01

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)

Current experience with central-station nuclear cogeneration plants

International Nuclear Information System (INIS)

1981-10-01

In considering the potential of the HTGR for nuclear cogeneration, a logical element for investigation is the recent history of nuclear cogeneration experience. Little is found in recent literature; however, the twin nuclear cogeneration plant at Midland is nearing completion and this milestone will no doubt be the basis for a number of reports on the unique cogeneration facility and operating experiences with it. Less well known in the US is the Bruce Nuclear Power Development in Ontario, Canada. Originally designed to cogenerate steam for heavy water production, the Bruce facility is the focus of a major initiative to create an energy park on the shores of Lake Huron. To obtain an improved understanding of the status and implications of current nuclear cogeneration experience, GCRA representatives visited the Ontario Hydro offices in Toronto and subsequently toured the Midland site near Midland, Michigan. The primary purpose of this report is to summarize the results of those visits and to develop a series of conclusions regarding the implications for HTGR cogeneration concepts

Chinese nuclear insurance and Chinese nuclear insurance pool

International Nuclear Information System (INIS)

Gong Zhiqi

2000-01-01

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

Change in CNE boiler control level and stepback to overcome strong grid transients

International Nuclear Information System (INIS)

Lorenzetti, J.; Sablic, J.C.

1991-01-01

In Argentina the grid distribution is organized in such a way that the Embalse Power Plant is located in a place where power is produced. The most important places of power consumption are located near Buenos Aires city. Just one line connects Embalse with the consumption places. As a result of that condition the power is flowing through the interconnection line in such a way that every time a disturb cuts the line a strong power transient affects the Nuclear Power Plant. The changes in the boiler level control were done in order to avoid reactor trip, reactor stepback or turbine trip based on boiler level upsets. After several years of operation it was possible to verify that the new algorithm reduces the chances of plant outage increasing the confidence in the plant to overcome with success such transient. Every transient in the plant is analyzed in order to improve the control algorithm

Spent fuel management of NPPs in Argentina

International Nuclear Information System (INIS)

Alvarez, D.E.; Lee Gonzalez, H.M.

2010-01-01

There are two Nuclear Power Plants in operation in Argentina: 'Atucha I' (unique PHWR design) in operation since 1974, and 'Embalse' (typical Candu reactor) which started operation in 1984. Both NPPs are operated by 'Nucleoelectrica Argentina S.A' which is responsible for the management and interim storage of spent fuel till the end of the operative life of the plants. A third NPP, 'Atucha II' is under construction, with a similar design of Atucha I. The legislative framework establishes that after final shutdown of a NPP the spent fuel will be transferred to the 'National Atomic Energy Commission', which is also responsible for the decommissioning of the Plants. In Atucha I, the spent fuel is stored underwater, until another option is implemented meanwhile in Embalse the spent fuel is stored during six years in pools and then it is moved to a dry storage. A decision about the fuel cycle back-end strategy will be taken before year 2030. (authors)

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.

Multiplicity Fluctuations in Central Nuclear Reaction of Pb + AgBr Events at 158A GeV

Directory of Open Access Journals (Sweden)

Mohammad Ayaz Ahmad

2017-12-01

Full Text Available In the present articles an attempt has been made for the study of multiplicity fluctuations of the secondary charged particles produced in central relativistic nuclear collisions of (Pb+AgBr at an energy 158A GeV, to find the first-order phase transition (QGP to hadron phase state. This study has been carried out for the experimental data along with the theoretical prediction of FRITIOF simulation program and Monte-Carlo (RanMC simulation. The theoretical model predictions were found in good agreements.

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

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, 13 - St. Paul lez Durance (France); Ambrosino, G.; De Tommasi, G.; Pironti, A. [Euratom-ENEA-CREATE, Universita di Napoli Federico II, Napoli (Italy)

2009-07-01

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)

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)

L’ambientalista nucleare Alternative al cambiamento climatico

CERN Document Server

Gómez Cadenas, Juan José

2012-01-01

Che cosa emette più radioattività nell'atmosfera: una centrale nucleare o una centrale termica? Una centrale termica. Che cosa comporta maggior rischio: vivere nei pressi di una centrale nucleare o fumare una sigaretta? Fumare una sola sigaretta equivale al rischio di vivere due anni vicino a una centrale nucleare. Che cosa si fa in un'ora di punta di richiesta energetica se non soffia il vento? Si ricorre a impianti di pompaggio o centrali a gas di riserva. L'energia elettrica non può essere immagazzinata. Quanti aerogeneratori servono per sostituire una centrale nucleare? Circa duemila, dell'ultima generazione. Separati tra di loro dei cinquecento metri necessari perché siano efficienti, la fila dei mulini si estenderebbe da Barcellona a Ginevra, attraversando l'intera Francia. È un errore contrapporre tra loro le energie alternative, sarebbe molto più sensato considerarle alleate nella grande battaglia contro un Signore Oscuro ogni giorno più potente: il cambiamento climatico, che potrebbe benissimo...

Diseño y evaluación de un procedimiento on-line para la biorremediación de aguas radiactivas en centrales nucleares

OpenAIRE

Belinchón Vergara, Julio Angel

2016-01-01

Recientemente se ha demostrado la existencia de microorganismos en las piscinas de almacenamiento de combustible nuclear gastado en las centrales nucleares utilizando técnicas convencionales de cultivo en el laboratorio. Estudios posteriores han puesto de manifiesto que los microorganismos presentes eran capaces de colonizar las paredes de acero inoxidable de las piscinas formando biopelículas. Adicionalmente se ha observado la capacidad de estas biopelículas de retener radionúclidos, lo que ...

Nuclear energy in central and eastern Europe

International Nuclear Information System (INIS)

Cognet, G.; Billaud, E.; Battista, L.; Pascal, J.

2010-01-01

Bulgaria, Hungary, Czech Republic, Romania, Slovakia and Slovenia have all nuclear power plants on their soil, their entry to the European Union has counter-balanced the number of member states that are not in favour of nuclear energy. All these countries committed themselves to upgrade their installations to European safety standards. This work is going on and new programs for service life extension and for construction of new units have been launched. All these countries have a strong culture and know-how in nuclear engineering inherited from soviet era. They stay very active in this field, for instance the ALLEGRO project that is carried out by a collaboration between Hungarian, Slovak, Czech research institutes and western partners aims at building the first demonstration plant of the future fourth generation reactor: a fast reactor cooled by gas. The situation of each country plus Croatia (that is a candidate to full E.U. membership) is reviewed. (A.C.)

The Centralized Reliability Data Organization (CREDO); an advanced nuclear reactor reliability, availability, and maintainability data bank and data analysis center

International Nuclear Information System (INIS)

Knee, H.E.

1991-01-01

The Centralized Reliability Data Organization (CREDO) is a data bank and data analysis center, which since 1985 has been jointly sponsored by the US Department of Energy's (US DOE's) Office of Technology Support Programs and Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC). It focuses on reliability, availability and maintainability (RAM) data for components (e.g. valves, pumps, etc.) operating in advanced nuclear reactor facilities. As originally intended, the purpose of the CREDO system was to provide a centralized source of accurate, up-to-date data and information for use in RAM analyses necessary for meeting DOE's data needs in the areas of advanced reactor safety assessments, design and licensing. In particular, creation of the CREDO system was considered an essential element needed to fulfill the DOE Breeder Reactor Safety Program's commitment of 'identifying and exploiting areas in which probabilistic methods can be developed and used in making reactor safety Research and Development choices and optimizing designs of safety systems'. CREDO and its operation are explained. (author)

Professional practices: a short introduction of national nuclear activities to university students; Practicas profesionales: breve incursion laboral de alumnos universitarios en las actividades nucleares

Energy Technology Data Exchange (ETDEWEB)

Martin, Hugo R [Comision Nacional de Energia Atomica, Cordoba(Argentina). Regional Centro

2005-07-01

tiene a cargo la produccion del Oxido de Uranio para el combustible de las centrales nucleares en Atucha 1 y Embalse; las cuestiones relacionadas con la opinion publica han sido una constante preocupacion para la institucion. Por tal motivo, a partir de junio de 2003 se comenzo a desarrollar un Programa de Apertura Institucional (PAI), con la intencion de poner al alcance de la sociedad cordobesa un conocimiento mas profundo sobre las actividades que se desarrollan en el lugar. Entre las multiples acciones implementadas se encuentra el desarrollo de relaciones institucionales con las universidades locales, con el objeto de permitir a alumnos, docentes e investigadores, segun los intereses de cada uno, un acercamiento a la realidad del sector nuclear nacional. A partir de entonces la CNEA ha comenzado a participar activamente de las actividades de la comunidad universitaria local, tanto como miembro permanente en comisiones evaluadoras para el otorgamiento de becas y subsidios del sistema cientifico local, como en consejos asesores del gobierno provincial y otras instancias similares. De las actividades desarrolladas, la que ha mostrado ser muy efectiva para los objetivos propuestos y que motiva estas lineas, ha sido la realizacion de Practicas Profesionales de alumnos del ultimo anio de distintas carreras universitarias en instalaciones de la institucion. (autor)

Nuclear regulation in transition

International Nuclear Information System (INIS)

Tomain, J.P.

1986-01-01

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)

Nuclear regulation in transition

Energy Technology Data Exchange (ETDEWEB)

Tomain, J.P. (Cincinnati Univ., OH, US. Coll. of Law)

1986-01-01

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.

Temperature and density of nuclear matter in central CC interactions at P=4.2 GeV/c per nucleon

International Nuclear Information System (INIS)

Didenko, L.A.; Grishin, V.G.; Kowalski, M.; Kuznetsov, A.A.

1984-01-01

An estimation of the temperature and density of nuclear matter in central carbon-carbon interactions at P/A=4.2 GeV/c is presented. It is shown that at energies of about 4 GeV per nucleon it is possible to reach the transitional region between hadronic matter and quark-gluon plasma. The results could be however more convincing if one uses heavier ions than carbon

Comparative analysis of C A R A fuel element in argentinean PHWR Argentinas

International Nuclear Information System (INIS)

Brasnarof D; Marino, A. C; Florido, P. C; Daverio, H

2006-01-01

This paper presents an analysis of the thermal mechanical behaviour, fuel consumption and economical estimations of the CARA fuel element in the Atucha and Embalse nuclear power plants, compared with the present fuel performance.The present results show that the expect profit by the use of the CARA fuel element in our reactor guaranties the recovery of fund for its development. Likewise it reduces the number of spent fuel to be storage and treated [es

I and C upgrades resulting from the systematic evaluation program carried out at the Central Nuclear Jose Cabrera

International Nuclear Information System (INIS)

Humphrey, J.C.

1985-01-01

Central Nuclear Jose Cabrera, also known as Zorita, is a 160 MWe nuclear power plant owned and operated by UNION ELECTRICA-FENOSA, S.A. The plant was supplied by Westinghouse Electric Corporation and commissioned in 1968. It features a unique one loop Pressurized Water Reactor design. The Spanish Licensing Authorities requested C.N. Jose Cabrera to carry out a review of their plant. The main objectives were to reassess the safety adequacy of the operating systems, provide a documented comparison of the plant design versus present day criteria and establish a rationale for departures. Another important objective was to provide prompt identification of any significant deficiency. The review known as phase 1 of the C.N. Jose Cabrera Systematic Evaluation Program, was completed and documented by April 1980

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)

Gillen, V.

1993-12-01

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

Energy situation in Latin America and nuclear power

International Nuclear Information System (INIS)

Jinchuk, D.; Deluchi, F.

2006-01-01

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

Nuclear safety organisation in France

International Nuclear Information System (INIS)

1979-12-01

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

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)

Development of a simulator for personnel training on nuclear power plants. The authors` experience in the Federal Republic of Germany; Desarrollo de un simulador para entrenamiento de personal de centrales nucleares. Experiencia de los autores en la Republica Federal de Alemania

Energy Technology Data Exchange (ETDEWEB)

Hacker, P; Kogan, A; Garzon, D

1991-12-31

This work describes the stages necessary to carry out the development of a full scope simulator for personnel training on nuclear power plants operation. (Author). [Espanol] Este trabajo describe los pasos o etapas necesarios para llevar adelante el desarrollo de un simulador de amplio alcance (full scope simulator) para entrenamiento de personal de operacion de centrales nucleares. (Autor).

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.

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

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

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

2000-08-01

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

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.

Radiological protection in nuclear power plants; La proteccion radiologica en las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Zorrilla R, S. [CFE. Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

2008-12-15

This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h{sup -1}, the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

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)

2007-01-01

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

The Three Gorges Dam Project in China:History and consequences

OpenAIRE

López-Pujol, Jordi; Ponseti, Marta

2006-01-01

[ES] Tras varias décadas de planificación y deliberaciones, el embalse de las Tres Gargantas (Sanxia Daba, ), en el curso alto del río Yangtzé (China Central), está cerca de su conclusión. De esta enorme presa, que contará con la mayor central hidroeléctrica del mundo, se espera que pueda contribuir al control de las inundaciones en el curso medio y bajo del Yangtzé, solvente la escasez energética de la región, y mejore la navegabilidad del río. Su construcción, sin embargo, tambi...

Safety performance indicators program

International Nuclear Information System (INIS)

Vidal, Patricia G.

2004-01-01

In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

Adequacy features of Nucleoelectrica Argentina Safety Management

Energy Technology Data Exchange (ETDEWEB)

Rapoport, H [Nucleoelectrica Argentina S.A., Buenso Aires (Argentina)

1997-12-01

The Argentine Nuclear Power Plants (NPP) ATUCHA I (357 Mw, SIEMENS) and EMBALSE (648 Mw, CANDU), both of PHWR type, were owned and operated until August 94 by the Comision Nacional de Energia Atomica (CNEA). Until that date, CNEA, the national agency for nuclear R and D, concentrated three activities or roles: Research, Nuclear Regulations and NPP Operation. Since August 1994 NPP`s are owned and operated by a state electrical company (Nucleoelectrica Argentina S.A.) the nuclear utility supplying 15% of the national electrical generation demand. NASA is going to be privatized according to a recent national law regulating nuclear activities. The transition from a research agency to a commercial company requires the introduction of changes in the management of activities. Mention of these changes is limited to those relating to Safety.

Adequacy features of Nucleoelectrica Argentina Safety Management

International Nuclear Information System (INIS)

Rapoport, H.

1997-01-01

The Argentine Nuclear Power Plants (NPP) ATUCHA I (357 Mw, SIEMENS) and EMBALSE (648 Mw, CANDU), both of PHWR type, were owned and operated until August 94 by the Comision Nacional de Energia Atomica (CNEA). Until that date, CNEA, the national agency for nuclear R and D, concentrated three activities or roles: Research, Nuclear Regulations and NPP Operation. Since August 1994 NPP's are owned and operated by a state electrical company (Nucleoelectrica Argentina S.A.) the nuclear utility supplying 15% of the national electrical generation demand. NASA is going to be privatized according to a recent national law regulating nuclear activities. The transition from a research agency to a commercial company requires the introduction of changes in the management of activities. Mention of these changes is limited to those relating to Safety

Instruction of 27 March 1973 concerning implementation of Decree No 73-278 of 13 March 1973 setting up a Higher Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

International Nuclear Information System (INIS)

1973-01-01

This Instruction specifies, on the basis of the 1973 Decree, the duties, in particular regarding licensing, of the Central Service for the Safety of Nuclear Installations. The Service is assisted in its work by the Atomic Energy Commission (CEA) and advisory groups.(NEA) [fr

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

International Nuclear Information System (INIS)

Amato, N.M.; Arata, N.; Maldonado, R.H.C.

1987-01-01

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

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.

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.

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

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

Diffusion tensor analysis with nuclear magnetic resonance in human central nervous system

International Nuclear Information System (INIS)

Nakayama, Naoki

1998-01-01

Nuclear magnetic resonance has been used to measure the diffusivity of water molecules. In central nervous system, anisotropic diffusion, which is characterized by apparent diffusion tensor D app ξ , is thought to be related to neuronal fiber tract orientation. For precise observation of anisotropic diffusion, it is needed to determine the diagonal and off-diagonal elements of D app ξ . Once D app ξ is estimated from a series of diffusion weighted images, a tissue's orthotropic principal axes and diffusivity of each direction are determined from eigenvalues and eigenvectors of D app ξ . There are several methods to represent anisotropic diffusion with D app ξ . Examples are diffusion ellipsoids constructed in each voxel depicting both these principal axes and the mean diffusion length in these directions, trace invariant values and its mapping image, largest eigenvalue, and ratio of largest eigenvalue to the other eigenvalue. In this study, the author investigated practical procedure to analyze diffusion tensor D app ξ using both of spin-echo end echo-planer diffusion weighted imagings with 3-tesla magnetic resonance machine in human brain. The ellipsoid representation provided particularly useful information about microanatomy including neuronal fiber tract orientation and molecular mobility reflective of microstructure. Furthermore, in the lesion of Wallerian degeneration, the loss of anisotropy of local apparent diffusion was observed. It is suggested that the function of axons can be observed via degree of anisotropy of apparent diffusion. Consequently, diffusion tensor analysis is expected to be a powerful, noninvasive method capable of quantitative and functional evaluation of the central nervous system. (author)

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)

Ferguston, C.D.; Ouagrham, S.B.

2002-01-01

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

Transient signal analysis in power reactors by means of the wavelet technique

International Nuclear Information System (INIS)

Wentzeis, Luis

1999-01-01

The application of the wavelet technique, had enabled to study the time evolution of the properties (amplitude and frequency content) of a signals set, measured in the Embalse nuclear power plant (CANDU 600 M we), in the low frequency range and for different operating conditions. Particularly, by means of this technique, we studied the time evolution of the signals in the non-stationary state of the reactor (during a raise in power), where the Fourier analysis results inadequate. (author)

Relación entre las formas solubles de hierro y manganeso y la presencia de bacterias oxidadoras de ambos elementos en el embalse Riogrande II- Don Matías (Antioquia, Colombia

Directory of Open Access Journals (Sweden)

Yamilet Arcos Arango

2010-01-01

Full Text Available Entre agosto de 2006 y marzo de 2008 se determinó la presencia de bacterias asociadas a la oxidación de hierro y manganeso en el límite de zona fótica (LZF y en el fondo del hipolimnio (FH en siete estaciones del Embalse Riogrande II en función de la disponibilidad de estos metales. Se realizaron mediciones in situ de temperatura del agua, oxígeno disuelto, pH, potencial redox y conductividad eléctrica. En el fondo del hipolimnio con niveles de oxígeno disuelto ≤ 4mgL-1 solo se encontró presencia de las bacterias oxidantes de hierro compatibles con Gallionella sp, Sphaerotilus sp, Beggiatoa sp y estructuras compatibles con bacterias prostecadas. El mayor número de estas bacterias se observó en el brazo de Río Grande (E4 en donde los niveles de hierro soluble fueron superiores a 1,4 mgL-1 . No se encontró presencia de bacterias dependientes de la oxidación del manganeso.

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)

Cradduck, T.D.; Driedger, A.A.

1981-01-01

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)

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

Energy Technology Data Exchange (ETDEWEB)

Ek, P.; Andersson, Sarmite [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Wredberg, L. [ILG Consultant Ltd., Vienna (Austria)

2000-06-15

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

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

International Nuclear Information System (INIS)

Ek, P.; Andersson, Sarmite; Wredberg, L.

2000-06-01

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

A study on the role adjustment between central and local government II

International Nuclear Information System (INIS)

Yuk, D. I.; Ahn, S. K.

2004-01-01

The goal of this research is to construct new system and feasible action plans by seeking solutions for more effective redistribution of the nuclear regulatory roles between central and local governments. From 1995 on, since local autonomy system has been reimplemented in Korea, it is imperative to develop reformative alternatives for the decentralization of powers between central and local governments. The core devolution is to redistribute administrative roles and functions which have been centralized, toward both self-governing bodies and communities including NGO. The level of devolution in nuclear regulatory system depends on how to redistribute nuclear related roles and functions among central/local government with KINS. Therefore, it is very important to examine general principles criteria and type of domestic/foreign role adjustment for effective/rational/democratic nuclear regulation. Based on previous model and system proposed, role adjustment action plans are reviewed taking account of the nuclear environmental changes in the localization era. In the long run, the result of this research will be expected to utilize the optimal and democratic regulatory system in Korea

A study on the role adjustment between central and local government II

Energy Technology Data Exchange (ETDEWEB)

Yuk, D. I. [Chungnam National University, Taejon (Korea, Republic of); Ahn, S. K. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

2004-07-01

The goal of this research is to construct new system and feasible action plans by seeking solutions for more effective redistribution of the nuclear regulatory roles between central and local governments. From 1995 on, since local autonomy system has been reimplemented in Korea, it is imperative to develop reformative alternatives for the decentralization of powers between central and local governments. The core devolution is to redistribute administrative roles and functions which have been centralized, toward both self-governing bodies and communities including NGO. The level of devolution in nuclear regulatory system depends on how to redistribute nuclear related roles and functions among central/local government with KINS. Therefore, it is very important to examine general principles criteria and type of domestic/foreign role adjustment for effective/rational/democratic nuclear regulation. Based on previous model and system proposed, role adjustment action plans are reviewed taking account of the nuclear environmental changes in the localization era. In the long run, the result of this research will be expected to utilize the optimal and democratic regulatory system in Korea.

National independence and nonproliferation in the new states of Central Asia

Energy Technology Data Exchange (ETDEWEB)

Gleason, G.

1993-12-01

Five independent states emerged in Central Asia from the breakup of the USSR. One of these states, Kazakhstan, possesses nuclear weapons. The other four of these states, Kyrgyzstan, Tajikistan, Turkmenistan, and Uzbekistan, are not known to possess nuclear weapons, however they occupy a geostrategic position which makes them important to non-proliferation efforts. The present report profiles the capabilities and intentions of these four Central Asian states. The analysis of capabilities suggests that none of these states has the capability to develop a usable nuclear weapon. However, all of these countries-- especially Uzbekistan--have components of the old Soviet nuclear weapons complex which are now orphans. They have no use for these facilities and must either re-profile them, destroy them, or transfer them. The analysis of intentions suggests that the dynamics of national independence have created a situation in which Uzbekistan has hegemonic designs in the region. Implications for retarding nuclear proliferation in the Central Asian region are examined. Opportunities for outside influence are assessed.

Pulsed nuclear power plant

International Nuclear Information System (INIS)

David, C.V.

1986-01-01

This patent describes a nuclear power plant. This power plant consists of: 1.) a cavity; 2.) a detonatable nuclear device in a central region of the cavity; 3.) a working fluid inside of the cavity; 4.) a method to denote a nuclear device inside of the cavity; 5.) a mechanical projection from an interior wall of the cavity for recoiling to absorb a shock wave produced by the detonation of the nuclear device and thereby protecting the cavity from damage. A plurality of segments defines a shell within the cavity and a plurality of shock absorbers, each connecting a corresponding segment to a corresponding location on the wall of the cavity. Each of these shock absorbers regulate the recoil action of the segments; and 6.) means for permitting controlled extraction of a quantity of hot gases from the cavity produced by the vaporization of the working fluid upon detonation of the nuclear device. A method of generating power is also described. This method consists of: 1.) introducing a quantity of water in an underground cavity; 2.) heating the water in the cavity to form saturated steam; 3.) detonating a nuclear device at a central location inside the cavity; 4.) recoiling plate-like elements inside the cavity away from the central location in a mechanically regulated and controlled manner to absorb a shock wave produced by the nuclear device detonation and thereby protect the underground cavity against damage; 5.) extracting a quantity of superheated steam produced by the detonation of the nuclear device; and 6.) Converting the energy in the extracted superheated steam into electrical power

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.

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

Science.gov (United States)

Raupach, Michael J; Astrin, Jonas J; Hannig, Karsten; Peters, Marcell K; Stoeckle, Mark Y; Wägele, Johann-Wolfgang

2010-09-13

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. 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. 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.

Collective phenomena in non-central nuclear collisions

International Nuclear Information System (INIS)

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

2008-01-01

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

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.

Design and construction of a basic principle simulator: an experiment

International Nuclear Information System (INIS)

Fernandez, O.; Galdoz, E.; Flury, C.; Fontanini, H.; Maciel, F.; Rovere, L.; Carpio, R.

1992-01-01

This paper describes activities developed over design and building of a Basic Principle Simulator for nuclear power plants. This simulator has been developed in Process Control Division of Bariloche Atomic Center, Argentina. This project was sponsored jointly by CNEA and Atomic Energy International Organization, through the United Nations Program for Development. The paper specially emphasizes aspects like: architecture design methodology of real time simulators; graphic environment and interfaces design for users and instructor interaction, and for display information; test and validation of the used models; and human resources formation. Finally describes the actual implementation of the simulator to be used in Embalse Nuclear Power Plant. (author)

The nuclear contribution

International Nuclear Information System (INIS)

Jones, P.M.S.

1984-01-01

The subject is discussed under the headings: background; nuclear reactors (reactor types; reactor choices; the present position; the future); reprocessing and waste management; uranium resources and the potential for thermal fission reactors; the fast reactor; thorium; other applications (than the central generation of electricity) of nuclear power; fusion; conclusion. (U.K.)

Temporal and vertical variations in phythoplankton community structure and its relation to some morphometric parameters of four Colombian reservoirs Temporal and vertical variations in phythoplankton community structure and its relation to some morphometric parameters of four Colombian reservoirs

Directory of Open Access Journals (Sweden)

Ramírez R. John J.

2000-07-01

Full Text Available Phytoplankton samples were taken at three depths within the photie zone of eaeh of four reservoirs, Punehiná, Las Playas, El Peñol and San Lorenzo loeated in Antioquia department, Colombia. A total of 77 taxa were identified in the four reservoirs. Diatoms were not included. In all reservoirs, Chlorophyta was the dominant group. Botryococcus braunii was the dominant species at Punchiná, Las Playas and El Peñol reservoirs; Cosmarium sp. was the dominant at San Lorenzo. Temporal variation in phytoplankton showed two peaks of abundance, apparently related to precipitation. Taxonomic composition among samples from the same reservoir showed little variation. Community structure at different depths showed significant differences only at San Lorenzo reservoir. The inverse of β-diversity showed small values indicating high similarity among the reservoirs. Diversitv showed no significant assoeiation with any morphometric factor evaluated (area, retention time, altitude and age.Se efectuaron muestreos de fitoplaneton en tres profundidades de la zona fótica de los embalses Punchiná, Las Playas, El Peñol y San Lorenzo, localizados en el departamento de Antioquia, Colombia. Se identificaron un total de 77 taxones en los cuatro embalses. Las diatomeas no fueron incluídas. En todos los casos las Cholorophyta fueron el grupo dominante. Botryococcus braunii fue el taxón de mayor densidad en los embalses Punchiná, Las Playas y El Peñol; y Cosmarium sp. en el embalse San Lorenzo. La comunidad fitoplanctónica mostró dos picos de abundancia aparentemente relacionados con la precipitación. En cada embalse, la composición de taxones entre muestreos varió poco. La estructura de la comunidad a diferentes profundidades mostró diferencias significativas únicamente en el embalse San Lorenzo. El inverso de la β-diversidad presentó valores bajos que muestran la alta similaridad entre embalses. La diversidad no mostró asociación significativa con

Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

Energy Technology Data Exchange (ETDEWEB)

Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

1966-02-15

matieres nucleaires ne se limite pas S de simples travaux d'inventaire mais sert de base a beaucoup d'autres activites qui font partie integrante du programme d'operations de tout reacteur, par exemple les expeditions de combustible irradie, le traitement chimique du combustible epuise et la comptabilite du combustible recupere et des matieres produites au cours du fonctionnement du reacteur, et l'institution et l'application d'un regime d'assurance satisfaisant. (author) [Spanish] Combustible relativamente nuevo y sumamente valioso para la produccion de energia electrica, el uranio requiere un control muy minucioso desde el momento en que la direccion de una central asume la responsabilidad financiera inherente a su posesion hasta que como combustible parcialmente agotado se transfiere a otra instalacion en la que se recupera la parte que no se ha consumido. Antes de que se descubriera la posibilidad de emplear la energia nuclear para producir electricidad, la mayor parte de las empresas que actualmente explotan centrales nucleares explotaban centrales alimentadas con combustibles fosiles y hablan establecido sistemas de control relativamente completos y adecuados para los combustibles de ese tipo. Los responsables de las centrales nucleoelectricas deben disponer de sistemas no menos adecuados para controlar los materiales nucleares especiales que utilizan. La explotacion de los reactores de potencia no es una ciencia antigua, pero durante el tiempo relativamente corto que ha transcurrido desde que se inicio su empleo los ingenieros y hombres de ciencia han mejorado continuamente el diseflo del equipo y los metodos de trabajo con objeto de disminuir los costos de produccion y de lograr que las centrales nucleares puedan competir en el plano economico con las centrales clasicas. La administracion de los materiales nucleares debe efectuarse con metodos modernos y eficientes a fin de que los adelantos tecnologicos que han permitido reducir los costos no resulten inutiles

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

International Nuclear Information System (INIS)

Ritch, J.

2006-01-01

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

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)

Souza, C.A.F. de; Pessoa, M.A.R.; Utchitel, S.

1988-01-01

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) [pt

Activities of nuclear human resource development in nuclear industry

International Nuclear Information System (INIS)

Tsujikura, Yonezo

2010-01-01

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)

Elecnuc. Nuclear power plants worldwide; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

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

Central Safety Department. Annual report 1986

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1987-03-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Central Safety Department. 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 r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. The report gives details of the different duties, indicates the results of 1986 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Safety Regulations in organizations and enterprises under supervision of Federal environmental, industrial and nuclear supervision service of Russia (Rostechnadzor), Central Region. Short overview of sites which potentially are dangerous for terrorist threat

International Nuclear Information System (INIS)

Gasselblat, A.D.

2010-01-01

Full text: Federal environmental, industrial and nuclear supervision service of Russia carries out inspections over safety of atomic energy sites on the territory of Russian Federation, which are used for peaceful purposes. Currently under control of Supervision Service on the whole territory of Russia 2000 (2179) (1.) organizations (enterprises), business entities in the field of atomic energy use (industry, medicine, scientific research, agriculture, geological survey, education and etc.) using in their activity radionuclide sources. Approximately 6000 (5955) territorially separated or technologically independent radiation-dangerous sites are counted in their structure, which are dealing with radionuclides. The total number of sealed radionuclide sources is more than 1000 pieces. More than thousands radiation-dangerous entities are dealing with unsealed radionuclide sources and radioactive wastes. At such scales of activity, when evident dynamic of source movement is observed, it is very important for regulatory authority to update information on source location, condition, safe use and security, as well as physical protection and prevention of its use in terrorist purposes. In its structure industrial and nuclear supervision service of Russia has 7 big subdivisions (according to directions regulation in the field of atomic energy use) - inter regional territory administrations on control over nuclear and radiation safety, ensuring control over whole territory of Russian Federation, each in within its border of Federal region of Russian Federation. Central inter regional territory administration on control over nuclear and radiation safety is the biggest according to its personnel and number of controlled sites by territorial subdivision of Federal environmental, industrial and nuclear supervision service of Russia (in the field of atomic energy use, according to Federal Law dated 21.11.1995, №170-Federal Low On atomic energy use) and carries out its activity

A study on the role adjustment between central and local government

Energy Technology Data Exchange (ETDEWEB)

Yook, Dong Il; Ji, Min Gu; Yun, Yo Il; Kim, Yong Cheon; Lee, Sang In; Lee, Chan Won [Chunnam National Univ., Taejon (Korea, Republic of)

2003-02-15

The goal of this study is to develop new model and feasible alternatives by seeking solutions for rational redistribution of the nuclear regulatory roles between central and local governments. Since local autonomy system has been reimplemented in Korea, It is imperative to improve reform measures for the decentralization of power between central and local governments. The core of decentralization is to redistribute administrative authorities and roles which have been centralized, toward both self-governing body and communities. The level of decentralization depends on how to redistribute roles and functions between central and local government. Therefore, it is necessary to examine principle and type of domestic foreign role adjustment for effective nuclear regulation. Based on three prerequisite studies, role adjustment model for more effective nuclear regulation is made taking account of the current domestic environments and conditions. In the long run, the outcomes of this study will be expected to improve the optimal and democratic regulatory system in Korea.

A study on the role adjustment between central and local government

International Nuclear Information System (INIS)

Ahn, S. K.; Yook, D. R.

2003-01-01

The goal of this study is to develop new model and feasible alternatives by seeking solutions for national redistribution of the nuclear regulatory roles between central and local governments. Since local autonomy system has been reimplemented in Korea, it is imperative to improve reform measures for the decentralization of powers between central and local governments. The core of decentralization is to redistribute administrative authorities and roles which have been centralized, toward both self-governing body and communities. The level of decentralization depends on how to redistribute roles and functions between central and local government. Therefore, it is necessary to examine principle and type of domestic foreign role adjustment for effective nuclear regulation. Based on three prerequisite studies, role adjustment model for more effective nuclear regulation is made taking account of the current domestic environments and conditions. In the long run, the outcomes of this study will be expected to improve the optimal and democratic regulatory system in Korea

The nuclear power decisions

International Nuclear Information System (INIS)

Williams, R.

1980-01-01

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)

Nuclear Law Bulletin : Index Nbs. 1 to 55

International Nuclear Information System (INIS)

Anon.

1995-01-01

In this book are given the laws concerning the following subjects : the field of application of the Nuclear Conventions, international conventions relating to radioactive marine pollution, international co-operation in the field of radioactive transfrontier pollution, compensation for nuclear damage in OECD Member Countries, spent fuel and radioactive waste management issues, the regulation of food irradiation, the accident at Chernobyl-economic damage and its compensation in Western Europe, development and harmonization of intervention levels in case of a nuclear accident, three negotiations concerning nuclear law, potential liability of contractors working on nuclear safety improvement projects in Central and Eastern Europe, overview of nuclear legislation in Central and Eastern Europe countries, problems raised by the application of the Nuclear Third Party Liability Conventions to radioactive waste repositories. (O.L.)

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)

Leak-before-break concept for evaluation of flows detected in pressure tubes in a Candu type reactor

International Nuclear Information System (INIS)

Crespi, J.C.

1992-01-01

This paper reviews the role of the Leak-Before-Break concept for evaluation of flaws detected in cold-worked Zr 2.5% Nb pressure tubes in a CANDU type reactors. The acceptance criteria are intended to prevent failure by brittle fracture, plastic collapse of the ligament and delayed hydride cracking. The methodology developed here was of great help in order to establish the operative conditions for fuel channel garter springs repositioning by means of the SLA Rette tool at Embalse Nuclear Generating Station, Cordoba, Argentina. (author)

Jose Cabrera NPP; Central Nuclear Jose Cabrera

Energy Technology Data Exchange (ETDEWEB)

Diez, P.

2004-07-01

During 2003, the Jose Cabrera nuclear power plant (JCNPP) operated without any incidents involving an undue risk to the population or environment. The year 2003 was the Plant's 35th year of operation, and during that time it has provided 33.209 million kilowatt-hours to the electric grid. The Plant set a record for continuous operation with 386 days of uninterrupted operation. The Plant had an outage for the 27th refueling and for equipment and systems maintenance, inspection and testing activities. The Plant reported nine events to the Administration that were classified as zero on the International Nuclear Event Scale (INES) and another event classified as level 1. AENOR performance the audit for renewing certificate UNE-EN ISO-9001, and for tracking environmental management systems as per UNE-EN ISO 14001, with satisfactory results. The dose around the Plant caused by plant operation has been insignificant. For the first time in the Spanish industry, the Plant has implemented an integrated safety system that encompasses all the plant's safety-related activities.

77 FR 59679 - Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving...

Science.gov (United States)

2012-09-28

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0044; Docket No. 50-423] Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving Application Regarding Corporate Restructuring and Conforming Amendment I Dominion Nuclear Connecticut, Inc. (DNC), Central Vermont Public Service...

Ground beetles (Coleoptera, Carabidae) of the Hanford Nuclear Site in south-central Washington State.

Science.gov (United States)

Looney, Chris; Zack, Richard S; Labonte, James R

2014-01-01

Carabidae) collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site), which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte), and Stenolophus lineola (Fabricius). Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

Ndos: nuclear data online services

International Nuclear Information System (INIS)

Fan, T.S.; Guo, Z.Y.; Ye, W.G.; Liu, W.L.; Feng, Y.Q.; Song, X.X.; Huang, G.; Liu, T.J.; Hong, Y.J.; Liu, C.; Chen, J.X.; Tang, G.Y.; Shi, Z.M.; Huang, X.L.; Chen, J.E.

2004-01-01

A Nuclear Data Online Services, Ndos software, has been developed to extract and present nuclear data from various available libraries. Using relational databases the present web-based software offers online data services of a centralized repository of data including eight major international nuclear data libraries for nuclear reaction data, nuclear structure and decay data. A data plotting software package, NDVS (Nuclear Data Viewing Software), which is included in NDOS, facilitates the visualization and manipulation of nuclear data. The NDOS is developed on the Linux implementation of PHP and the MySQL software. The relational nuclear databases and data services are platform independent in a wide sense

Ndos: nuclear data online services

Energy Technology Data Exchange (ETDEWEB)

Fan, T.S. E-mail: tsfan@nst.pku.edu.cn; Guo, Z.Y.; Ye, W.G.; Liu, W.L.; Feng, Y.Q.; Song, X.X.; Huang, G.; Liu, T.J.; Hong, Y.J.; Liu, C.; Chen, J.X.; Tang, G.Y.; Shi, Z.M.; Huang, X.L.; Chen, J.E

2004-07-01

A Nuclear Data Online Services, Ndos software, has been developed to extract and present nuclear data from various available libraries. Using relational databases the present web-based software offers online data services of a centralized repository of data including eight major international nuclear data libraries for nuclear reaction data, nuclear structure and decay data. A data plotting software package, NDVS (Nuclear Data Viewing Software), which is included in NDOS, facilitates the visualization and manipulation of nuclear data. The NDOS is developed on the Linux implementation of PHP and the MySQL software. The relational nuclear databases and data services are platform independent in a wide sense.

Reflections on Britain's nuclear history: a conversation with Lord Hinton

International Nuclear Information System (INIS)

Lowry, D.

1984-09-01

This record of a discussion with Lord Hinton, who was in charge of the industrial side of the U.K. atomic energy project, and later Chairman of the Central Electricity Generating Board, covers the following topics: history of the development and construction of reactors for the production of plutonium and, later, nuclear power; secrecy; early relations between Central Electricity Authority (and later, CEGB), the Government, and Atomic Energy Authority; Government policy on the nuclear power programme; decision making in the area of nuclear power; economics of nuclear power; the nuclear industry; safety, insurance, National Nuclear Inspectorate; support research and development in CEGB; Sizewell-B proposed PWR. (U.K.)

Nuclear security and law

International Nuclear Information System (INIS)

Gozal, Y.

1999-01-01

The aim of this study is to show that the classical distinction between the military nuclear law and the civil nuclear law is outdated. The technologies are dual and might be misused from a pacific to a military goal. The central element of the nuclear law is thus the integration of the safety rules: the nuclear risk being universal, it has created an universal law (first part) that reflects our scientific knowledge and might thus evaluate. This universal law has been a factor of nuclear security (part 2), as in 50 years, there had been only one major nuclear accident and no nuclear conflict. The horizontal proliferation has been limited and the international community has understood that time had come to reduce our arsenals. (author)

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)

Spectrophotometric determination of uranium traces in zircaloy-4 and zirconium sponge

International Nuclear Information System (INIS)

Correia, R.J.; Weber de D'Alessio, Ana; Zucal, R.H.

1980-01-01

The uranium contents of the zircaloy-4 which is used for the fabrication of the fuel cans for the PHWR Atucha and Embalse nuclear power stations must not exceed 3.ppM. A method was developed for performing that control, involving the separation of the uranium from its matrix by partition chromatography and its determination by spectrophotometry with Arsenazo (III). This method is applied within the range of 0.2 to 10 ppM, obtaining a relative standard deviation of 6% for U contents of 3 ppm. (M.E.L.) [es

The Next Nuclear Gamble. Transportation and storage of nuclear waste

International Nuclear Information System (INIS)

Resnikoff, M.

1985-01-01

The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

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)

National Frederic Joliot-Curie Research Institute for Radiobiology and Radiohygiene

2007-01-01

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.)

Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector; Etude complete du mouvement collectif de la matiere nucleaire dans les collisions centrales d'ions lourds avec le detecteur FOPI

Energy Technology Data Exchange (ETDEWEB)

Bendarag, A

1999-07-09

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)

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: 3.820, year: 2016

Nuclear energy

International Nuclear Information System (INIS)

Rippon, S.

1984-01-01

Do we need nuclear energy. Is it safe. What are the risks. Will it lead to proliferation. The questions are endless, the answers often confused. In the vigorous debates that surround the siting and operation of nuclear power plants, it is all too easy to lose sight of the central issues amid the mass of arguments and counter-arguments put forward. And there remains the doubt, who do we believe. This book presents the facts, simply, straightforwardly, and comprehensibly. It describes the different types of nuclear reactor, how they work, how energy is produced and transformed into usable power, how nuclear waste is handled, what safeguards are built in to prevent accident, contamination and misuse. More important, it does this in the context of the real world, examining the benefits as well as the dangers of a nuclear power programme, quantifying the risks, and providing an authoritative account of the nuclear industry worldwide. Technically complex and politically controversial, the contribution of nuclear energy to our future energy requirements is a crucial topic of our time. (author)

Nonstrategic Nuclear Weapons

Science.gov (United States)

2017-02-21

of their nonstrategic nuclear weapons and eliminate many of them. These 1991 announcements, coming after the abortive coup in Moscow in July 1991...of these weapons. The abortive coup in Moscow in August 1991 had also caused alarms about the strength of central control over nuclear weapons...assure other allies of the U.S. commitment to their security, but these assurances do not necessarily include legally binding commitments to retaliate

AP1000, a nuclear central of advanced design

International Nuclear Information System (INIS)

Hernandez M, N.; Viais J, J.

2005-01-01

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)

Nuclear imaging in pediatrics

International Nuclear Information System (INIS)

Siddiqui, A.R.

1985-01-01

The author's intent is to familiarize practicing radiologists with the technical aspects and interpretation of nuclear medicine procedures in children and to illustrate the indications for nuclear medicine procedures in pediatric problems. Pediatric doses, dosimetry, sedation, and injection techniques, organ systems, oncology and infection, testicular scanning and nuclear crystography, pediatric endocrine and skeletal systems, ventilation and perfusion imaging of both congenital and acquired pediatric disorders, cardiovascular problems, gastrointestinal, hepatobiliary, reticuloendothelial studies, and central nervous system are all topics which are included and discussed

The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

Energy Technology Data Exchange (ETDEWEB)

Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

1963-10-15

.), responsible for maintenance of all mechanical equipment; and (5) Service maintainers: responsible for a wide variety of less skilled tasks requiring lower qualifications. In addition to these general categories a few specialists are required, such as chemists and radiation protection officers. Organization of the NPD staff and training for future nuclear-power needs will be discussed. (author) [French] La centrale nucleaire de demonstration canadienne (NPD), creee par un organisme federal, l'Atomic Energy of Canada Limited, est exploitee par une compagnie provinciale de distribution d'electricite, la Hydro-Electric Power Commission of Ontario, qui pourvoit aussi aux besoins en personnel. Le recrutement et la formation du personnel de la centrale ont ete difficiles du fait que, recemment encore, la plupart des besoins en electricite de l'Ontario pouvaient etre satisfaits par les abondantes ressources hydro-electriques de cette province. La multiplication des centrales thermiques, depuis 1950, a cree une enorme demande de personnel. Pour faire face a cette situation, on a organise la formation de personnel pour les centrales nucleaires de la maniere suivante: a) un groupe initial d'ingenieurs a ete selectionne parmi des specialistes ayant une vaste experience des travaux dans le domaine nucleaire de l 'exploitation des centrales thermiques et de la production d'electricite; b) on a selectionne un autre groupe d'operateurs et d'agents des services d'entretien hautement qualifies; c) ces groupes ont recu une formation systematique comprenant l'exploitation de centrales nucleaires et de centrales thermiques a charbon, un enseignement theorique et pratique et des instructions donnees par les specialistes qui ont concu les plans de NPD ; d) un centre de formation nucleaire a ete cree et charge de la selection et de la formation du personnel supplementaire ainsi que de l 'organisation des examens officiels; il doit s'assurer, d'une maniere generale, de la competence du personnel

Nuclear energy in central and eastern Europe; L'energie nucleaire en Europe centrale et orientale

Energy Technology Data Exchange (ETDEWEB)

Cognet, G.; Billaud, E.; Battista, L.; Pascal, J. [CEA/Ambassade de France a Budapest (Hungary)

2010-07-15

Bulgaria, Hungary, Czech Republic, Romania, Slovakia and Slovenia have all nuclear power plants on their soil, their entry to the European Union has counter-balanced the number of member states that are not in favour of nuclear energy. All these countries committed themselves to upgrade their installations to European safety standards. This work is going on and new programs for service life extension and for construction of new units have been launched. All these countries have a strong culture and know-how in nuclear engineering inherited from soviet era. They stay very active in this field, for instance the ALLEGRO project that is carried out by a collaboration between Hungarian, Slovak, Czech research institutes and western partners aims at building the first demonstration plant of the future fourth generation reactor: a fast reactor cooled by gas. The situation of each country plus Croatia (that is a candidate to full E.U. membership) is reviewed. (A.C.)

Status of the nuclear sector in Spain Situación del sector nuclear en España

Directory of Open Access Journals (Sweden)

Antonio González Jiménez

2010-12-01

ó a desarrollarse en los años sesenta, como consecuencia de la decisión de construir las centrales nucleares de José Cabrera, Santa María de Garoña y Vandellós I. En la siguiente etapa, en la década de los años setenta, se construyeron las centrales de Almaraz, Ascó y Cofrentes. Durante la tercera etapa, en la década de los años ochenta, se construyeron las centrales de Vandellós II y Trillo I. Actualmente, la industria nuclear española, experta y eficaz, es garantía de que la tecnología nuclear se conserva en España no solo para apoyar a las centrales nucleares en operación, sino para atender un mercado nuclear reactivado a nivel internacional. España dispone de la infraestructura necesaria, la capacidad técnica, los recursos financieros y la voluntad de las empresas en el empeño común de proporcionar a los españoles una energía eléctrica fiable, barata y sostenible, con respeto al medio ambiente y seguridad para los ciudadanos. La energía nuclear es, en definitiva, una pieza clave hoy y lo será en el futuro.

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

International Nuclear Information System (INIS)

Amato, N.M.; Arata, N.; Maldonado, R.H.C.

1986-01-01

A cosmic-ray induced nuclear event detected in the emulsion chamber is described. The event consists of 217 shower cores with ΣEγ = 1,275 TeV. In log 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 the radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and non-isotropic azimuthal distribution. This event indicates a possibility that phenomena of large transverse momentum could happen to produce a strong concentration of energy and particles in the very forward direction. (Authors) [pt

The nuclear case book

International Nuclear Information System (INIS)

Stephenson, M.; Hearn, R.

1983-01-01

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.)

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

Energy Technology Data Exchange (ETDEWEB)

Esteban, G.

2014-10-01

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

Ground beetles (Coleoptera, Carabidae of the Hanford Nuclear Site in south-central Washington State

Directory of Open Access Journals (Sweden)

Chris Looney

2014-04-01

Full Text Available In this paper we report on ground beetles (Coleoptera: Carabidae collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site, which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte, and Stenolophus lineola (Fabricius. Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

Workers doses in central European PWR NPPs

International Nuclear Information System (INIS)

Janzekovic, H.; Krizman, M.

2003-01-01

As is stated, the ISOE database which was established in 1992 forms an excellent basis for studies and comparisons of occupational exposure data between nuclear power plants. In the year 2001, 69% of all participating reactors were pressurised water reactors. The ISOE database presents workers' exposure from 213 participating pressurised reactors (PWR) from 27 countries in that year. Among these 32 PWRs belong to six Central European Countries. The analysis of the exposure of workers based on radiation protection performance indicators (collective dose, average dose etc.) in these PWRs could be related to some nuclear safety performance indicators for recent years using ISOE database. The comparison is made to ISOE world - wide data. In the six Central European Countries altogether 32 PWR operated in the year 2001.The international databases of performance indicators related to radiation protection as for example the ISOE or the UNSCEAR database can be use as an efficient tool in the management of radiation protection of workers in a nuclear facilities and regulatory bodies. The databases enable the study of performance trends and the improvement of radiation protection. (authors)

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

International Nuclear Information System (INIS)

Mendoza L, A.; Flores C, E.; Lopez G, C.P.F.

1995-01-01

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)

The Staffing of Central Electricity Generating Board Nuclear Power Stations; Organigramme des centrales nucleaires du central electricity generating board; Politika v oblasti kadrov na atomnykh ehlektrostantsiyakh CEGB; El personal de las plantas nucleoelectricas de la central electricity generating board.

Energy Technology Data Exchange (ETDEWEB)

Bartlett, J. S.; Shepherd, G. T. [Central Electricity Generating Board, Western Division, Bristol (United Kingdom)

1963-10-15

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) [French] Le memoire donne un apercu de l'organigramme d'une centrale nucleaire du CEGB et des conditions auxquelles doit satisfaire le personnel (formation, qualifications requises pour la fonction d'operateur). Il rend compte egalement de l'experience acquise a ce jour quant a l'interet qu'il y a a former le personnel au prealable et a etablir des plans d'operation detailles. (author) [Spanish] La memoria informa sobre la organizacion de las centrales nucleoelectricas de la CEGB y sobre la plantilla de personal que estas requieren. Discute la formacion del personal y los requisitos para obtener la licencia de operador de reactores. Describe la experiencia adquirida hasta el presente en materia de formacion previa del personal y de organizacion detallada de las operaciones. (author) [Russian] Daetsya otchet o trebovaniyakh, pred{sup y}avlyaemykh k personalu, i organizatsiya nabora personala na atomnykh ehlektrostantsiyakh Tsentral'nogo upravleniya proizvodstva ehlektroehnergii (CEGB). Obsuzhdayutsya voprosy podgotovki personala i normativnykh trebovanij, pred{sup y}avlyaemykh k ehkspluatatsionnomu personalu. Izlagaetsya opyt, nakoplennyj k nastoyashchemu vremeni v rezul'tate osushchestvleniya predehkspluatatsionnoj podgotovki i podrobnogo planirovaniya v usloviyakh ehkspluatatsii. (author)

Central depression of the charge density distributions in lead isotopes

International Nuclear Information System (INIS)

Haddad, S.

2008-01-01

The central-depression parameters is determined by fitting the charge density distributions in lead isotopes to a three-parameter Fermi distribution. The central-depression parameter increases with the number of neutrons due to the isovector coupling channel of the nuclear interaction and its dependency on density. (author)

Central depression of the charge density distributions in lead isotopes

International Nuclear Information System (INIS)

Haddad, S.

2007-01-01

The central-depression parameter is determined by fitting the charge density distributions in lead isotopes to a three-parameter Fermi distribution. The central-depression parameter increases with the number of neutrons due to the isovector coupling channel of the nuclear interaction and its dependency on density. (author)

Nuclear power in the developing countries

International Nuclear Information System (INIS)

Perera, J.

1984-01-01

The subject is covered in chapters, entitled: the general energy situation (including nuclear power); the nuclear fuel cycle; the history of nuclear power in the third world; economic considerations; environmental considerations (including general environmental effects of power generation; radiation; normal fuel cycle operation; nuclear waste management; accidents; sabotage; health and safety regulations); political considerations (nuclear weapons proliferation; technology transfer; energy independence and national prestige); the suppliers (mainly USA, France, West Germany, Canada, UK, USSR); Sub-Saharan Africa; the Arab World and Israel; Central Asia; South and East Asia; Latin America; conclusions. (U.K.)

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.)

Description of the PIE facility for research reactors irradiated fuels in CNEA

International Nuclear Information System (INIS)

Bisca, A.; Coronel, R.; Homberger, V.; Quinteros, A.; Ratner, M.

2002-01-01

The PIE Facility (LAPEP), located at the Ezeiza Atomic Center (CAE), was designed to carry out destructive and non-destructive post-irradiation examinations (PIE) on research and power reactor spent fuels, reactor internals and other irradiated materials, and to perform studies related with: Station lifetime extension; Fuel performance; Development of new fuels; and Failures and determination of their causes. LAPEP is a relevant facility where research and development can be carried out. It is worth mentioning that in this facility the PIE corresponding to the Surveillance Program for the Atucha I Nuclear Power Plant (CNA-1) were successfully performed. Materials testing during the CNA-1 repair and the study of failures in fuel element plugs of the Embalse Nuclear Power Plant (CNE) were also performed. (author)

Second School of Nuclear Energetics

International Nuclear Information System (INIS)

2009-01-01

At 3-5 Nov 2009 Institute of Nuclear Energy POLATOM, Association of Polish Electrical Engineers (SEP) and Polish Nuclear Society have organized Second School of Nuclear Energetics. 165 participants have arrived from all Poland and represented both different central institutions (e.g. ministries) and local institutions (e.g. Office of Technical Inspection, The Voivodship Presidential Offices, several societies, consulting firms or energetic enterprises). Students from the Warsaw Technical University and Gdansk Technical University, as well as the PhD students from the Institute of Nuclear Chemistry and Technology (Warsaw) attended the School. 20 invited lectures presented by eminent Polish specialists concerned basic problems of nuclear energetics, nuclear fuel cycle and different problems of the NPP construction in Poland. [pl

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

1986-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is presented in an appendix. The report provides documentation of the US nuclear capacity and generation projections through 1995. Projections for US nuclear capacity and generation through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982 and are used to produce the projections of fuel cycle requirements and spent fuel discharges

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.

14th German nuclear law symposium

International Nuclear Information System (INIS)

Burgi, Martin

2013-01-01

Nuclear law is still relevant and topical. The nuclear power phase-out in response to the nuclear accident of Fukushima and the turnaround in German energy policy raise new legal issues. In several lectures of practioners and scientists the 14th German Nuclear Law Symposium examined questions regarding the retrofitting of nuclear power plants, their decommissioning and disposal, the current developements in the European nuclear and radiation protection law and the search for a final nuclear waste repository. The nuclear law provides examples for central challenges of administrative law, such as the independence of authorities and the protection of third parties. The discussions between the almost 150 participants are documented in several reports.

Panorama of the nuclear physics

International Nuclear Information System (INIS)

Aragones, J.M.

1981-01-01

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) [es

Report of the State Office for Nuclear Safety on state supervision of nuclear safety of nuclear facilities and radiation protection in 1998

International Nuclear Information System (INIS)

1999-05-01

The legislative basis of the authority of the State Office for Nuclear Safety as the Czech national regulatory body is outlined, its organizational scheme is presented, and the responsibilities of the various departments are highlighted. The operation of major Czech nuclear facilities, including the Dukovany NPP which is in operation and the Temelin NPP which is under construction, is described with respect to nuclear safety. Since the Office's responsibilities also cover radiation protection in the Czech Republic, a survey of ionizing radiation sources and their supervision is given. Other topics include, among other things, nuclear material transport, the state system for nuclear materials accountancy and control, central registries for radiation protection, nuclear waste management, the National Radiation Monitoring Network, personnel qualification and training, emergency planning, legislative activities, international cooperation, and public information. (P.A.)

Nuclear reactor instrumentation power monitor

International Nuclear Information System (INIS)

Suzuki, Shigeru.

1989-01-01

The present invention concerns a nuclear reactor instrumentation power monitor that can be used in, for example, BWR type nuclear power plants. Signals from multi-channel detectors disposed on field units are converted respectively by LPRM signal circuits. Then, the converted signals are further converted by a multiplexer into digital signals and transmitted as serial data to a central monitor unit. The thus transmitted serial data are converted into parallel data in the signal processing section of the central monitor unit. Then, LPRM signals are taken out from each of channel detectors to conduct mathematical processing such as trip judgment or averaging. Accordingly, the field unit and the central monitor unit can be connected by way of only one data transmission cable thereby enabling to reduce the number of cables. Further, since the data are transmitted on digital form, it less undergoes effect of noises. (I.S.)

Centralization and decentralization in energy systems and associated risks

International Nuclear Information System (INIS)

Rehm, W.; Schinner, F.; Kromp, W.

1998-01-01

Full text of publication follows: the concept of centralization/decentralization is - considering its widespread use - surprisingly ill-defined. Within the SERF-program (Socio Economic Research on Fusion) an attempt is made to clarify the complex issue of centralization/decentralization and to analyze its expected interaction with electricity production system in the case of nuclear fusion. Fusion research at the time is a multinational, highly centralized undertaking. As a result of this, and due to the expected large energy production units, it is generally expected that fusion will be embedded in a highly centralized, international energy supply system. The degree of centralization of an energy supply system, however, is believed to have for reaching consequences on the stability of the system, and beyond that, on decision making processes in energy policy, as well as democratic structures on the national or even international level. Internationalization might require control instruments that do not exist so far. Amongst other reservations, it is the possibly unwanted consequences of such a highly centralized, international energy supply system that limit acceptance of the fusion technology in the public. Therefore, centralization and decentralization trends of energy supply systems over the years are being looked at, to study their influence on the political and social systems (and vice-versa). In a first step, an attempt is made to classify centralization. Careful analyses and evaluation of available literature revealed a broad spectrum of different forms and degrees of centralization. Various parameters describing energy production and distribution are used. A differentiation of centralization on a technical and on an organizational level seems necessary, although they are not fully independent of each other. Beyond this, the choice of parameters must depend on the questions to be addressed. A new approach defining different levels and degrees of

Centralization and decentralization in energy systems and associated risks

Energy Technology Data Exchange (ETDEWEB)

Rehm, W.; Schinner, F.; Kromp, W. [Vienna Univ., Institute of Risk Research, IRR (Austria)

1998-07-01

Full text of publication follows: the concept of centralization/decentralization is - considering its widespread use - surprisingly ill-defined. Within the SERF-program (Socio Economic Research on Fusion) an attempt is made to clarify the complex issue of centralization/decentralization and to analyze its expected interaction with electricity production system in the case of nuclear fusion. Fusion research at the time is a multinational, highly centralized undertaking. As a result of this, and due to the expected large energy production units, it is generally expected that fusion will be embedded in a highly centralized, international energy supply system. The degree of centralization of an energy supply system, however, is believed to have for reaching consequences on the stability of the system, and beyond that, on decision making processes in energy policy, as well as democratic structures on the national or even international level. Internationalization might require control instruments that do not exist so far. Amongst other reservations, it is the possibly unwanted consequences of such a highly centralized, international energy supply system that limit acceptance of the fusion technology in the public. Therefore, centralization and decentralization trends of energy supply systems over the years are being looked at, to study their influence on the political and social systems (and vice-versa). In a first step, an attempt is made to classify centralization. Careful analyses and evaluation of available literature revealed a broad spectrum of different forms and degrees of centralization. Various parameters describing energy production and distribution are used. A differentiation of centralization on a technical and on an organizational level seems necessary, although they are not fully independent of each other. Beyond this, the choice of parameters must depend on the questions to be addressed. A new approach defining different levels and degrees of

US central station nuclear electric generating units: significant milestones

International Nuclear Information System (INIS)

1979-09-01

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

Material integrity verification radar

International Nuclear Information System (INIS)

Koppenjan, S.K.

1999-01-01

The International Atomic Energy Agency (IAEA) has the need for verification of 'as-built' spent fuel-dry storage containers and other concrete structures. The IAEA has tasked the Special Technologies Laboratory (STL) to fabricate, test, and deploy a stepped-frequency Material Integrity Verification Radar (MIVR) system to nondestructively verify the internal construction of these containers. The MIVR system is based on previously deployed high-frequency, ground penetrating radar (GPR) systems that have been developed by STL for the U.S. Department of Energy (DOE). Whereas GPR technology utilizes microwave radio frequency energy to create subsurface images, MTVR is a variation for which the medium is concrete instead of soil. The purpose is to nondestructively verify the placement of concrete-reinforcing materials, pipes, inner liners, and other attributes of the internal construction. The MIVR system underwent an initial field test on CANDU reactor spent fuel storage canisters at Atomic Energy of Canada Limited (AECL), Chalk River Laboratories, Ontario, Canada, in October 1995. A second field test at the Embalse Nuclear Power Plant in Embalse, Argentina, was completed in May 1996. The DOE GPR also was demonstrated at the site. Data collection and analysis were performed for the Argentine National Board of Nuclear Regulation (ENREN). IAEA and the Brazilian-Argentine Agency for the Control and Accounting of Nuclear Material (ABACC) personnel were present as observers during the test. Reinforcing materials were evident in the color, two-dimensional images produced by the MIVR system. A continuous pattern of reinforcing bars was evident and accurate estimates on the spacing, depth, and size were made. The potential uses for safeguard applications were jointly discussed. The MIVR system, as successfully demonstrated in the two field tests, can be used as a design verification tool for IAEA safeguards. A deployment of MIVR for Design Information Questionnaire (DIQ

Nuclear power in Europe

International Nuclear Information System (INIS)

Perera, J.

2000-01-01

Currently nuclear power accounts for more than 25% of total electricity production in Europe (including Eastern Europe and the former Soviet Union) However, significant new construction is planned in Central and Eastern Europe only, apart from some in France and, possibly in Finland. Many countries in Western Europe have put nuclear construction plans on hold and several have cancelled their nuclear programs. This report looks at the history of nuclear power and its current status in both Eastern and Western Europe. It provides an outline of nuclear fuel cycle facilities, from uranium procurement to final waste disposal. Economic and environmental issues are discussed, as well as the prospect of increased East-West trade and cooperation in the new poso-cold war world. Detailed profiles are provided of all the countries in Western Europe with significant nuclear power programs, as well as profiles of major energy and nuclear companies

Situación del sector nuclear en España

Directory of Open Access Journals (Sweden)

Antonio González Jiménez

2010-12-01

Full Text Available España comenzó a interesarse por la energía nuclear a finales de los años cuarenta. En el año 1964 se aprobó la Ley de Energía Nuclear, y en el año 1972 se desarrolló el Reglamento de Instalaciones Nucleares y Radiactivas. Las actividades de seguridad y regulación se encomendaron al Consejo de Seguridad Nuclear, creado en 1980, y la investigación y gestión de los residuos radiactivos a la Empresa Nacional de Residuos Radiactivos (ENRESA, creada en 1985. La estructura industrial nuclear en España comenzó a desarrollarse en los años sesenta, como consecuencia de la decisión de construir las centrales nucleares de José Cabrera, Santa María de Garoña y Vandellós I. En la siguiente etapa, en la década de los años setenta, se construyeron las centrales de Almaraz, Ascó y Cofrentes. Durante la tercera etapa, en la década de los años ochenta, se construyeron las centrales de Vandellós II y Trillo I.Actualmente, la industria nuclear española, experta y eficaz, es garantía de que la tecnología nuclear se conserva en España no solo para apoyar a las centrales nucleares en operación, sino para atender un mercado nuclear reactivado a nivel internacional. España dispone de la infraestructura necesaria, la capacidad técnica, los recursos financieros y la voluntad de las empresas en el empeño común de proporcionar a los españoles una energía eléctrica fiable, barata y sostenible, con respeto al medio ambiente y seguridad para los ciudadanos. La energía nuclear es, en definitiva, una pieza clave hoy y lo será en el futuro.

Regional comparison of nuclear and fossil electric power generation costs

International Nuclear Information System (INIS)

Bowers, H.I.

1984-01-01

Nuclear's main disadvantages are its high capital investment cost and uncertainty in schedule compared with alternatives. Nuclear plant costs continue to rise whereas coal plant investment costs are staying relative steady. Based on average experience, nuclear capital investment costs are nearly double those of coal-fired generation plants. The capital investment cost disadvantage of nuclear is balanced by its fuel cost advantages. New base load nuclear power plants were projected to be competitive with coal-fired plants in most regions of the country. Nuclear power costs wre projected to be significantly less (10% or more) than coal-fired power costs in the South Atlantic region. Coal-fired plants were projected to have a significant economic advantage over nuclear plants in the Central and North Central regions. In the remaining seven regions, the levelized cost of power from either option was projected to be within 10%. Uncertainties in future costs of materials, services, and financing affect the relative economics of the nuclear and coal options significantly. 10 figures

Climatologia no Entorno da Central Nuclear de Angra dos Reis, RJ

Directory of Open Access Journals (Sweden)

João Batista Araujo Figueiredo

Full Text Available Resumo Este trabalho tem por objetivo caracterizar os ciclos diurno e sazonal médios no entorno da Central Nuclear de Angra dos Reis. As condições médias são derivadas de dados horários, do período de janeiro de 2005 a dezembro de 2012. O local conta com quatro torres A, B, C e D. A Torre A mede vento e temperatura do ar a 10, 60 e 100 m e também precipitação, enquanto as demais torres medem somente vento a 15 m de altura. A atmosfera apresenta condições predominantemente estáveis ao longo do dia, com redução a partir das 6 e 7 h, sendo que condições instáveis predominam entre às 8 e 16 h no verão e primavera. Os ventos da região são predominantemente fracos, a maior frequência ocorre nas intensidades entre 1,5 e 2 m/s. O mínimo de intensidade dos ventos a 10 m ocorre no momento da entrada da brisa marítima, às 9 h. Os ventos catabáticos produzem um forte cisalhamento vertical dos ventos na região. Nas demais torres a máxima intensidade ocorre entre 13 e 15 h local. Ventos mais intensos e chuvas mais intensas foram registrados no outono (MAM, o que sugere ser este o período de tempestades mais intensas.

Aplicación de la metodología de Análisis Probabilístico de la Seguridad al procedimiento de evaluación de las Funciones Clave de Seguridad en parada de una central nuclear de agua a presión

OpenAIRE

Viñals Atienza, Òscar

2008-01-01

El Proyecto Final de Carrera “Aplicación de la metodología de Análisis Probabilístico de la Seguridad al procedimiento de evaluación de las Funciones Clave de Seguridad en parada de una central nuclear de agua a presión” se enmarca en un convenio de colaboración entre el Departament de Física i Enginyeria Nuclear y una central nuclear para la investigación y aplicación de los APS en decisiones basadas en el riesgo. El hilo conductor de este proyecto ha sido la petición por parte del depart...

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)

Portius, U.

2007-01-01

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.)

Behind the UK nuclear flip-flop

International Nuclear Information System (INIS)

Anon.

1990-01-01

Because it failed to attract commercial investors on acceptable terms, the British government has exempted the nation's nuclear powerplants from privatization, lopping off about 8,000 MW from National Power - the larger of the two successors to the broken-up Central Electricity Generating Board - and whipping up an antiprivatization political storm in the process. A new state company - to be called the Nuclear Electric Co - will be set up to control nuclear powerplants

Control of the hafnium content in Co samples by SSMS

International Nuclear Information System (INIS)

Lukaszew, R.A.; Cretella, R.F.

1989-01-01

The production of 60 Co requires a strict control of the chemical composition of the cobalt before irradiation in order to avoid the activation of some undesirable elements and to constrain the presence of slow neutron poisons. A methodology by SSMS for the survey analysis of metallic Co prior to its irradiation in the nuclear reactor at Embalse (Cdba., Argentina) is described. The low detection limit attained for Hf (below 0.5 ppm) is outlined. The results obtained for some other impurities without a standard reference are compared with atomic emission spectrographic data and show satisfactory agreement. (orig.)

Preliminary study for the microstructural characterization of Zr-2.5Nb pressure pipes by electron microscopy

International Nuclear Information System (INIS)

Saumell M, Lani; Oroza Z E, Celiz; Bozzano, P.B; Versaci, R.A

2012-01-01

The Embalse Nuclear Power Station (CNE) is a CANadian Deuterium Uranium (CANDU) Reactor. One of the acceptance criteria for the Zr-2,5Nb alloy pressure tubes of the CNE is based on the width of the α-Zr phase. This width is manually measured, using image processing software. The first part of this paper is oriented to weigh the human factor of these measures and find a proper image treatment to minimize this error. In the second part an automatic procedure is proposed, in order to measure the width of the α-Zr phase and become independent on the human factor (author)

A study on the nuclear foreign policy

International Nuclear Information System (INIS)

Lee, Byungwook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Noh, B. C.

2008-12-01

This study addresses four arenas to effectively assist national nuclear foreign policies under international nuclear nonproliferation regimes and organizations. Firstly, this study analyzes the trends 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. Secondly, this study analyzes the trends of international nuclear organizations, which include the IAEA as a central body of international nuclear diplomacy and technical cooperation and the OECD/NEA as a intergovernmental organization to consist of nuclear advanced countries. Thirdly, this study predicts the nuclear foreign policy of Obama Administration and reviews U. S.-India nuclear cooperation. Lastly, this study analyzes the nuclear issues of North Korea and current issues for regulation of nuclear materials.

Experience gained in enhancing operational safety at ComEd's nuclear power plants

International Nuclear Information System (INIS)

Elias, D.

1997-01-01

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

Diffraction in nuclear scattering

International Nuclear Information System (INIS)

Wojciechowski, H.

1986-01-01

The elastic scattering amplitudes for charged and neutral particles have been decomposed into diffractive and refractive parts by splitting the nuclear elastic scattering matrix elements into components responsible for these effects. It has been shown that the pure geometrical diffractive effect which carries no information about the nuclear interaction is always predominant at forward angle of elastic angular distributions. This fact suggests that for strongly absorbed particles only elastic cross section at backward angles, i.e. the refractive cross section, can give us basic information about the central nuclear potential. 12 refs., 4 figs., 1 tab. (author)

Improved nuclear fuel element

International Nuclear Information System (INIS)

Klepfer, H.H.

1974-01-01

A nuclear fuel element is described which comprises: 1) an elongated clad container, 2) a layer of high lubricity material being disposed in and adjacent to the clad container, 3) a low neutron capture cross section metal liner being disposed in the clad container and adjacent to the layer, 4) a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, 5) an enclosure integrally secured and sealed at each end of the container, and a nuclear fuel material retaining means positioned in the cavity. (author)

Nuclear Waste Fund management

International Nuclear Information System (INIS)

Mills, L.

1984-01-01

The Nuclear Waste Policy Acts requires that DOE enter into contracts with nuclear utilities and others to accept their nuclear wastes at some unspecified date, at some unspecified rate, hopefully starting in 1998. Contracts between DOE and the states, and with civilian and other government agencies must be sufficiently detailed to secure competitive bids on definable chunks of work at a fixed-cost basis with incentives. The need is stressed for a strong central program for the selection of contractors on the basis of competitive bidding on a fixed price basis to perform the task with defined deliverables

Advances in nuclear physics

CERN Document Server

Vogt, Erich

1975-01-01

Review articles on three topics of considerable current interest make up the present volume. The first, on A-hypernuclei, was solicited by the editors in order to provide nuclear physicists with a general description of the most recent developments in a field which this audience has largely neglected or, perhaps, viewed as a novelty in which a bizarre nuclear system gave some information about the lambda-nuclear intersection. That view was never valid. The very recent developments reviewed here-particularly those pertaining to hypernuclear excitations and the strangeness exchange reactions-emphasize that this field provides important information about the models and central ideas of nuclear physics. The off-shell behavior of the nucleon-nucleon interaction is a topic which was at first received with some embarrassment, abuse, and neglect, but it has recently gained proper attention in many nuclear problems. Interest was first focused on it in nuclear many-body theory, but it threatened nuclear physicists'comf...

A comprehensive centralized control system for radiation waste treatment facility

International Nuclear Information System (INIS)

Kong Jinsong

2014-01-01

A comprehensive centralized control system is designed for the radiation waste treatment facility that lacking of coordinated operational mechanism for the radiation waste treatment. The centralized control and alarm linkage of various systems is implemented to ensure effectively the safety of nuclear facility and materials, improve the integral control ability through advanced informatization ways. (author)

Nuclear waste: Status of DOE's nuclear waste site characterization activities

International Nuclear Information System (INIS)

1987-01-01

Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

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)

Central Accountability System (CLAS)

International Nuclear Information System (INIS)

Hairston, L.A.

1991-01-01

The Central Accountability System (CLAS) is a high level accountability system that consolidates data from the site's 39 material balance areas (MBA) for reporting to Westinghouse Savannah River Company (WSRC) management, Department of Energy (DOE) and the Nuclear Materials Management and Safeguards System (NMMSS) in Oak Ridge, TN. Development of the system began in 1989 and became operational in April, 1991. The CLAS system enhances data accuracy and accountability records, resulting in increased productivity and time and cost savings. This paper reports that the system is in compliance with DOE Orders and meets NMMSS reporting requirements. WSRC management is provided with the overall status of the site's nuclear material inventory. CLAS gives WSRC a leading edge in accounting technology and enhances good accounting practices

Meeting of socialist conntries' representatives on problems of nuclear materials analyses

International Nuclear Information System (INIS)

Pacak, P.; Moravec, J.; Krtil, J.; Sus, F.

1982-01-01

A meeting of representatives of the socialist countries was held in Prague from May 18 to 22, 1981, to discuss cooperation in the field of analytical control of nuclear materials. The Czechoslovak delegation informed the participants of the extent and results of the work of the Central Control Laboratory of the Nuclear Research Institute in Rez. A brief survey is given of the nondestructive methods of measuring the physical parameters of nuclear fuel, the methods of destructive determination of uranium and plutonium and the methods of preparation of standard materials for mass spectrometry which the Central Control Laboratory has introduced and verified for securing analytical control of nuclear materials. (B.S.)

DTN and international cooperation of the Spanish Nuclear Sector in nuclear technology development processes

International Nuclear Information System (INIS)

Acero, M.

1995-01-01

The Spanish electrical utilities with interests in the Nuclear Sector-IBERDROLA, ENDESA,FUERZAS ELECTRICAS DE CATALU=A5A (FECSA), UNION ELECTRICA FENOSA S.A., COMPA=A5IA SEVILLANA DE ELECTRICIDAD S.A., AND HIDROELECTRICA DEL CANTABRICO S.A.-created on September 26, 1994 the ''Agrupacion Electrica para el Desarrollo Tecnologico Nuclear, A.I.E. (DTN)'' (Electrical Society for Nuclear technology Development A.I.E.) for the purpose of promoting and managing Nuclear Nechnology Development, and integrating and coordinating the efforts of the Nuclear Electrical Sector with industrial companies and other related institutions in spain and abroad. This mission is primarily accomplished by establinhing a common strategy for the Nuclear Electrical Sector in the different areas of responsibility of DTN, centralizing actions by implementing a clear and coherent policy, and ensuring the presence of the entire Electrical Sector in all those fora deemed to be strategic to the Nuclear Sector

Energy/war: breaking the nuclear link

International Nuclear Information System (INIS)

Lovins, A.B.; Lovins, L.H.

1980-01-01

Policies to control the spread of nuclear weapons have assumed that the rapid worldwide spread of nuclear power is essential to replace oil, is both economically desirable and inevitable, and that the international political order must remain inherently discriminatory and dominated by the nuclear arms race. These assumptions are challenged as contrary to economic fact and market behavior. The authors feel that the link between nuclear reactors and nuclear bombs is inextricable, making proliferation inevitable and nuclear power a dangerous and costly alternative to oil. Instead, they suggest that nuclear power will collapse in response to market forces because only a few centrally-planned economies can override economic pressures. Acknowledgement of this collapse should be encouraged and the benefits of nuclear power accepted as illusory, according to the authors. 349 references, 2 figures

Aprovechamiento hidroeléctrico del río Eume

Directory of Open Access Journals (Sweden)

Yordi de Carricarte, Luciano

1960-02-01

Full Text Available En la provincia de La Coruña, junto a la desembocadura del río Eume, y en las proximidades del pueblo de Puentedeume, se ha realizado el aprovechamiento hidroeléctrico de dicho río, formado, en cuestión, por tres elementos básicos: una presa de embalse de doble curvatura, de 103 m de altura; una conducción forzada, integrada por un túnel de 2.839 m de longitud y dos tuberías de 310; y una central, equipada con dos grupos de 75.000 CV.

INTERNET and information about nuclear sciences. The world wide web virtual library: nuclear sciences

International Nuclear Information System (INIS)

Kuruc, J.

1999-01-01

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

Sector activities related to spent nuclear fuel in the spanish nuclear power plants; Actuaciones sectoriales en relaci@n con el combustible nuclear gastado en las centrales nucleares espa@olas.

Energy Technology Data Exchange (ETDEWEB)

Francia, L.

2016-07-01

Royal Decree 102/2014 of February 21 defines spent nuclear fuel as the irradiated nuclear fuel in the reactor core that is permanently removed from it. Spent nuclear fuel can be considered either as a usable resource that can be reprocessed, or else as a radioactive waste destined for final disposal. Likewise, spent nuclear fuel management refers to all the activities related to handling, temporary storage, reprocessing and final storage. The article presents all the plans and actions taken by the nuclear power plants, which can be divided into the following two categories: Actions taken by the plants themselves to not only maintain the fuel in stable, safe conditions, but also to characterize and process it for the subsequent management routes established by the current General Radioactive Waste Plan. Activities undertaken under the UNESA umbrella to help implement the above mentioned management routes.

Perspectives in high energy nuclear collisions

International Nuclear Information System (INIS)

Rafelski, J.

1983-08-01

This report gives an overview of some aspects of hadronic physics relevant for the conception of a research facility devoted to the study of high energy nuclear collisions. Several concepts to be studied in nuclear collisions are selected, with emphasis placed on the properties and nature of the quark-gluon plasma, the formation of the plasma state in the central region and its anticipated lifetime, and the observability, through strangeness content of this new form of nuclear matter. (orig.)

Pro-Nuclear Environmentalism: Should We Learn to Stop Worrying and Love Nuclear Energy?

Science.gov (United States)

van Munster, Rens; Sylvest, Casper

2015-10-01

In light of repeated failures to reach political agreement on effective policies to combat climate change, pro-nuclear environmentalists have set out to reverse the traditionally anti-nuclear inclinations of environmentalists. This essay examines the ideological commitments and assumptions of pro-nuclear environmentalism by performing a critical, historical analysis of the nuclear-environment nexus through the prism of documentary film. We focus on the work and career of documentary filmmaker Rob Stone, whose most recent production, Pandora's Promise (PP) (2013), has emerged as a central statement of this creed. PP actively forges a new political imaginary that replaces the apocalyptic image of nuclear fallout with that of catastrophic climate change. In terms of its rhetorical and visual strategies, however, PP also reveals that pro-nuclear environmentalist arguments have a long lineage. A close study of such continuities reveals a number of political implications that call for reflection as well as caution.

Commercial nuclear power 1988: Prospects for the United States and the world

International Nuclear Information System (INIS)

1988-01-01

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. This report presents three different nuclear supply scenarios. The Optimistic-case scenario, included in previous issues of this report, has been deleted. 7 figs; 36 tabs

Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

Energy Technology Data Exchange (ETDEWEB)

Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

1965-10-15

In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Ueberwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [French] En Allemagne, on construit actuellement des generatrices nucleaires dans lesquelles les bouilleurs sont installes a l'interieur du caisson etanche du reacteur. Il s'ensuit que les reparations des tubes des bouilleurs sont tres difficiles et provoquent de longs arrets des centrales nucleaires. On sait que de nombreuses perturbations du fonctionnement des centrales classiques sont dues a des dommages dans les tubes des bouilleurs. C'est en grande partie en raison du prix de revient eleve de ces reacteurs qu'il est necessaire de construire les bouilleurs notamment de sorte que le facteur d'utilisation de la centrale soit aussi eleve que possible. C'est le ' Technischer Ueberwachungs

Nuclear training and experience feedback in Sweden

International Nuclear Information System (INIS)

Olofsson, B.G.

1987-01-01

There are several different ways of educating and training the personnel at the Swedish nuclear power plants: centralized training in full-scale and part-task simulators; centralized education in the form of technical academic courses where computerized teaching is also used; extensive decentralized training out at the nuclear power plants, where compact simulators are also used; and experience feedback forms an important part of the training. Five performance indicators will be identified and the results will be presented. The excellent results are a good indication of the fact that well-executed education and training and smoothly functioning experience feedback give results

1989 annual report of the Rossendorf Central Institute of Nuclear Research

International Nuclear Information System (INIS)

Fromm, W.; Kaun, K.H.; Moeller, K.; Naehring, F.; Schulz, H.; Winter, G.; Heidel, I.; Breiter, S.

1990-01-01

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) [de

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.)

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

Mayes, F.; Gielecki, M.; Diedrich, R.; Hewlett, J.; Murphy, T.

1985-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is also presented. The report provides documentation of the US middle-case nuclear capacity and generation projections through 1995 that are presented in the Annual Energy Outlook 1984. Additionally, US nuclear capacity and generation projections through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982. The projections for foreign nuclear capacity through 1990 supplant the preliminary foreign WOCA projections presented in the Annual Energy Outlook 1984 and are supplemented by WOCA country-specific projections through the year 2000

Nuclear DNA content variation among central European Koeleria taxa

Czech Academy of Sciences Publication Activity Database

Pečinka, A.; Suchánková, Pavla; Lysák, Martin; Trávníček, B.; Doležel, Jaroslav

2006-01-01

Roč. 98, - (2006), s. 117-122 ISSN 0305-7364 R&D Projects: GA MŠk(CZ) LC06004 Institutional research plan: CEZ:AV0Z50380511 Keywords : Chromosome number * nuclear DNA content * flow cytometry Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 2.448, year: 2006

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)

Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

International Nuclear Information System (INIS)

Warenmo, G.

1979-01-01

Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

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

Science.gov (United States)

2010-03-03

.... civil nuclear industry. Increasing energy demands, dependence on Russian fossil fuels, and a small but aging fleet of Russian reactor technologies is colliding with pressure from the EU to meet stricter..., language included in the Czech Republic's nuclear tender allows for the awarded company to have the...

Seismotectonic model of Central Europe

International Nuclear Information System (INIS)

Prochazkova, D.; Roth, Z.

1994-01-01

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

1981 Annual status report. Nuclear measurements

International Nuclear Information System (INIS)

1982-01-01

The Nuclear Measurements programme is divided into two main projects, Nuclear Data on the one hand and Nuclear Reference Materials and Techniques on the other. In the former the JRC actions form part of world-wide sets of actions to establish reliable, and in many cases very precise, figures for important nuclear parameters - e.g. neutron interaction cross-sections, radio-nuclide half lives. In this work the Central Bureau for Nuclear Measurements (CBNM) pays particular attention to the specific needs of the Community and to complement similar actions undertaken in the laboratories belonging to the Member States. Concerning Nuclear Reference Materials and Techniques the actions are to provide materials to which analytical and other measurements carried out in the nuclear industry or by the nuclear community can be referred. The basic aim of the Nuclear measurement programme is therefore to develop nuclear metrology with special orientation towards satisfying the demands for basic nuclear data and for materials and methods or reference

Nuclear Power in South-Central Brazil

International Nuclear Information System (INIS)

Cintra do Prado, L.

1966-01-01

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''

Experience gained in enhancing operational safety at ComEd`s nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Elias, D [Commonwealth Edison Co. (United States)

1997-09-01

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.

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)

Chiripus, Vlad-Ionut

2004-01-01

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

A Study on the Nuclear Foreign Policy

International Nuclear Information System (INIS)

Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S.

2007-12-01

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

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.

Nuclear energy: a world of service to humanity. 27th annual conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society/Canadian Nuclear Association student conference

International Nuclear Information System (INIS)

2006-01-01

The 27th Annual conference of the Canadian Nuclear Society was held on June 11-14, 2006 in Toronto, Ontario, Canada. The conference gathered close to 400 scientists, engineers, technologists and students interested in all aspects and applications of energy from the atom. The central objective of this conference was to provide a forum for exchange of views on how this technical enterprise can best serve the needs of humanity, now and in the future. The plenary sessions addressed broad industrial and commercial developments in the field. Over eighty papers were presented in 15 technical sessions on the following topics: safety analysis; plant refurbishment; control room operation; nuclear chemistry and materials; advanced reactor design; plant operation; reactor physics; safety analysis; nuclear instrumentation; and, nuclear general topics. Embedded in the conference was the 30th student conference, sponsored by the Canadian Nuclear Society and the Canadian Nuclear Association. Over thirty-five papers were presented in five sessions on the following topics: corrosion processes; control systems / physics / modelling; and, chemistry / chemical engineering

Nuclear power: tomorrow's energy source

International Nuclear Information System (INIS)

2002-01-01

In France, 76% of electricity is produced by nuclear power. The industry's pricing levels are among the most competitive in Europe. Thanks to its 58 nuclear reactors France enjoys almost 50% energy autonomy thus ensuring a highly stable supply. Equally, as a non-producer of greenhouse gases, the nuclear sector can rightfully claim to have an environmentally friendly impact. Against a background to increasing global demand with predictions that fossil fuels will run out and global warming a central issue, it is important to use production methods which face up to problems of this nature. There is no question that nuclear energy has a vital role to play alongside other energy sources. (authors)

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; Diozcora Vargas Trevino, Aurora; 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

2016-03-25

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.

The nuclear waste primer: A handbook for citizens

International Nuclear Information System (INIS)

Anon.

1987-01-01

A sourcebook of facts about the production of nuclear waste and radioactive materials, this volume looks at the debate over safe storage, transportation, and disposal of hazardous radioactive materials. Addressing such concerns as the dangers of nuclear waste, protecting the public, and affecting the decision-making process at all levels of government, this book explores the issues central to the handling and disposal of nuclear waste

First Conference on African Youth Nuclear Summit 2017: Nuclear for a Sustainable Future

International Nuclear Information System (INIS)

2017-03-01

Kenyan Young Generation in Nuclear (KYGN) hosted the inaugural African Youth Nuclear Summit, dubbed AYNS2017 that took place on the 27th to 30th March, 2017, Nairobi, Kenya. The participants were drawn from academia, research and development institutes, radiation services providers, health institutions, nuclear facilities and regulatory bodies. They shared experiences, exchanged ideas and built networks on issues related to safe application of nuclear science and technology. The theme of the summit was ''Nuclear for a Sustainable future'', which centered on three thematic areas: Nuclear powering Africa, Radiation Protection and safety culture; and application of nuclear science and technology for a sustainable future. The Director General, World Nuclear Association who pointed out that nuclear energy had made a major contribution to world energy output and was set to increase by two and half time by 2040. The importance of nuclear science and technology for a sustainable socio-economic development in Africa shared and highlight on many areas IAEA has helped member states in improving the life of its populations. The main activities of project 60 whose focus is to strengthen the nuclear security culture in East and Central Africa through improved regulation, training, capacity and awareness were highlighted

Turbine model for the Laguna Verde nucleo electric central based in the RELAP code; Modelo de turbina para la Central nucleoelectrica de Laguna Verde basado en el codigo RELAP

Energy Technology Data Exchange (ETDEWEB)

Cortes M, F.S.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [Facultad de Ingenieria, Division de Estudios de Posgrado, Grupo de Ingenieria Nuclear, UNAM (Mexico)]. e-mail: cchavez2@cableonline.com.mx

2003-07-01

The Nuclear Power stations as Laguna Verde occupy at the present time a place every time but important as non pollutant alternative, economic and trusty to generate electricity. It is for it that the Group of Nuclear Engineering of the Engineering Faculty (GrlNFI) of the National Autonomous University of Mexico (UNAM) it develops investigation projects applied to Nuclear Centrals. One of the projects in process is the development of a Classroom simulator, which it can configures to consent to diverse models of nuclear systems with training purposes in normal operation, or, to consent to specialized nuclear codes for the analysis of transitory events and have a severe accident. This work describes the development, implementation and it proves of a simplified model of the Main turbine to be integrated to the group of models of the Classroom simulator. It is part of the current effort of GrlNFI guided to obtain a representation of all the dynamic models necessary to simulate the Plant Balance of the Laguna Verde Central. It is included the development of the unfolding graphic which represent the modeling of the Main turbine, and of the control interface that allows the user to manipulate in simple way, direct and interactive this device during the training or the analysis. With this work it is wanted to contribute to the training of new technicians and to support the operation personnel of the Centrals. Also, the developed infrastructure is guided to contribute in the design and analysis of new Nuclear Power stations with the contribution of new computational tools for the visualization, simulation and process control. (Author)

Nuclear fuels accounting interface: River Bend experience

International Nuclear Information System (INIS)

Barry, J.E.

1986-01-01

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

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

Progress of laser nuclear fusion research

International Nuclear Information System (INIS)

Shiraga, Hiroyuki

2017-01-01

This paper describes the principle and features of nuclear fusion using laser, as well as its basic concepts such as high-temperature / high-density implosion system and fast ignition of fuel. At present, researches aiming at nuclear fusion ignition have been developing. As the current state of researches, this paper reviews the situations of FIREX (Fast Ignition Realization Experiment) project of Japan focusing on direct irradiation implosion and fast ignition system, as well as NIF (National Ignition Facility) project of the U.S. aiming at ignition combustion based on indirect irradiation implosion and central ignition system. In collaboration with the National Institute for Fusion Science, Osaka University started FIREX-1 project in 2003. It built a heating laser LFEX of 10 kJ/1 to 10ps, and started an implosion/heating integration experiment in 2009. Currently, it is developing experiment to achieve heating to 5 keV. At NIF, the self-heating of central sparks via energy of α particles generated in the nuclear fusion reaction has been realized. This paper also overviews R and D issues surrounding the lasers for reactors for use in laser nuclear fusion power generators. (A.O.)

Nuclear Law Bulletin: Index + supplement no.56

International Nuclear Information System (INIS)

Anon.

1995-01-01

This book deals with the status of legislation governing the peaceful uses of nuclear energy in Central and Eastern European Countries. Readers are informed about regulatory and institutional developments in these countries. The Supplement to this Bulletin reproduces the Ukraine fundamental nuclear law of the 8 february 1995 on the use of nuclear energy and radiation safety. It shall establish the priority of human and environmental safety and the rights and responsibilities of citizens with regard to the use of nuclear energy, it shall regulate activities connected with the use of nuclear installations and ionizing radiation sources, and, as well, establish the legal basis for Ukraine's international commitments with respect to the use of nuclear energy. (authors). 71 refs

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

International Nuclear Information System (INIS)

Murata, Takashi

1999-01-01

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)

Nuclear electric power and the proliferation of nuclear weapon states

International Nuclear Information System (INIS)

Walske, C.

1977-01-01

Control and elimination of the strategic nuclear weapons held by the nuclear weapon states remains the central problem in the arms control and disarmament field. Whether the proliferation of nations with nuclear weapons can be stopped is dubious. A sovereign nation will launch a nuclear weapons program if it has the motivation and resource. Motivation depends on military and political considerations. The necessary resources are economic and technological. Conditions in some sovereign states explain this issue. A survey of commercial nuclear power programs outside the USA lists 45 countries using or planning to use nuclear reactors for power generation. There are currently 112 reactors now operating outside the United States, 117 more under construction, 60 on order, and 180 planned. The U. S. as of December 1976 has 64 operating reactors, 72 under construction, 84 on order, and 8 planned. Nuclear trade and export policies are discussed. In this article, Mr. Walske says that American industry is convinced that the need for nuclear energy abroad is more urgent than in the United States; that in the long run, the breeder reactor must be developed to enable the supply of nuclear fuel to last for centuries; and that the experience of American industry abroad has convinced it that emphasis on restrictive, denial type policies will almost certainly fail--a collapse of what has been gained through the test ban treaty and the nonproliferation treaty

Environmental radiation monitoring system in nuclear power station

International Nuclear Information System (INIS)

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

1983-01-01

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

Insectos acuáticos y calidad del agua en la cuenca y embalse del río Peñas Blancas, Costa Rica

Directory of Open Access Journals (Sweden)

Meyer Guevara Mora

2011-06-01

Full Text Available La población de insectos acuáticos y la calidad del agua fueron caracterizadas tomando en cuenta las alteraciones humanas y naturales en el área de estudio. Durante los muestreos mensuales, el pH, OD, temperatura, nivel del agua, DBO, PO4 y NO3 fueron medidos. Los índices biológicos (abundancia, riqueza de especies y el BMWP-CR se evaluaron para determinar la calidad del agua. No se detectaron relaciones entre las variables ambientales y los insectos acuáticos, pero las diferencias espaciales y temporales en la abundancia y riqueza fueron asociadas con las crecidas del río (temporal y a la presencia del embalse Peñas Blancas (espacial. En el futuro las investigaciones en la cuenca Peñas Blancas deben de ser dirigidas a determinar la magnitud de la influencia de los caudales, liberación de sedimentos y la posible degradación de la calidad del agua por efluentes de aguas servidas que se lleguen a ubicar en la cuenca.Aquatic insects and water quality in Peñas Blancas watershed and reservoir. The aquatic insects have been used to evaluate water quality of aquatic environments. The population of aquatic insects and the water quality of the area were characterized according to the natural and human alterations present in the study site. During the monthly-survey, pH, DO, temperature, water level, DBO, PO4 and NO3 were measured. Biological indexes (abundance, species richness and the BMWP-CR were used to evaluate the water quality. No relation between environmental and aquatic insects was detected. Temporal and spatial differences attributed to the flow events (temporal and the presence of Peñas Blancas reservoir (spatial. In the future, the investigations in Peñas Blancas watershed need to be focused on determining the real influence of the flows, sediment release and the possible water quality degradation because of agriculture activities. Rev. Biol. Trop. 59 (2: 635-654. Epub 2011 June 01.

CANDU senior regulators 2005 annual report

International Nuclear Information System (INIS)

Calvo, Jorge C.; Navarro, Norberto R.

2006-01-01

On June 8th, 2005, Embalse nuclear power plant was operating normally at full power after the fuelling machine (F/M) 'A' was replaced, and while it was being prepared to operate again, a heavy water spilling within the reactor building occurred. The actuation of the safety system was not demanded and Embalse nuclear power plant did not run out of service. The maintenance activities performed to prepare the F/M 'A' included, among others, its calibration, functions check, and heavy water level restitution. When the F/M calibration was concluded, the snout plug was stored in the magazine and the D 2 O supply pumps were stopped. Under this condition the involved maintenance personnel required to normalize the F/M 'A'. Finally, the F/M 'A' was coupled to the new fuel port, the snout plug restored and it was filled up with heavy water again. When this operation had been performed the operator opened the F/M 'A' discharge valve (35230 MV37) without lifting the drainage port, and so, when the D 2 O supply pumps started, a D 2 O spilling into room R 104 occurred. The main actions taken to control the incidental situation were: to stop the D 2 O supply pumps and close both the D 2 O feed valves and the corresponding discharge valve. Besides, it was foreseen to improve the operational procedure by giving more relevance to automatic operation. The incident was attributed to a human error during F/M 'A' operation that enabled the spilling of 113 kg of D 2 O to the R104 room floor. (author)

Uranium to Electricity: The Chemistry of the Nuclear Fuel Cycle

Science.gov (United States)

Settle, Frank A.

2009-01-01

The nuclear fuel cycle consists of a series of industrial processes that produce fuel for the production of electricity in nuclear reactors, use the fuel to generate electricity, and subsequently manage the spent reactor fuel. While the physics and engineering of controlled fission are central to the generation of nuclear power, chemistry…

La sostenibilidad y el debate nuclear

Directory of Open Access Journals (Sweden)

Amparo Vilches

2008-01-01

Full Text Available Las centrales nucleares están siendo presentadas como “solución verde” al problema energético, debido a que no conllevan emisiones de CO2. En este artículo se pretende poner de manifiesto que, sin embargo, esta indudable ventaja va acompañada de muy serios inconvenientes que obligan a rechazar la opción nuclear.

French nuclear harvest: abundant energy or bitter fruit

International Nuclear Information System (INIS)

Bupp, I.C.

1980-01-01

In France, the nuclear-development program is a high-priority objective of a strong, centralized government. The administrators responsible for its success can draw on concentrated fiscal and technical resources and are free to take decisive action. A major pillar of the entire French nuclear-development effort is the expectation of significant long-term export markets on all fronts: for nuclear power plants, uranium enrichment, and fuel reprocessing

Nuclear Weapons Security Crisis: What Does History Teach?

Science.gov (United States)

2013-07-01

or tempo - rary storage.” It was uncertain if the Chinese would keep nuclear warheads stored at launch bases or in a central stockpile, then...activities. His account can be considered the most complete and credible of all available ones. Other accounts have small variations . See, for example...the National Journal article “Nuclear Negligence,” by Jeffrey Goldberg and Marc Ambinder, who reported that nuclear materials in Paki- stan were

Nuclear energy - overview of development trends

International Nuclear Information System (INIS)

1985-01-01

Proceeding from the organizational structure of the IAEA selected activities of the IAEA in connection with power reactor safety are dealt with. Based on the IAEA's computerized Power Reactor Information System (PRIS) a survey is presented of the most recent statistical data concerning status and trends of nuclear power plant development throughout the world. The central role of the IAEA in assisting Member States in the utilization of nuclear energy for peaceful purposes is underscored. Finally, a brief account of the state-of-the-art of the USSR's nuclear power programme is given

Movies about nuclear disasters

International Nuclear Information System (INIS)

Portelli, A.; Guarnieri, F.; Martin, C.

2014-01-01

'The China Syndrome' by J.Bridges is the most famous film about nuclear energy, it was released in 1979 and tells the story of a television reporter who discovers safety cover-ups in the Ventana nuclear power plant. In the film 'Mount Fuji in red' a part of 'Akira Kurosawa's dreams' film released in 1990, the eruption of the Mount Fuji triggered a series of accidents in Japanese nuclear plants which sent millions of people fleeing in terror and blocked by the ocean. More recent films are 'Land of Oblivion' by M.Boganim - 2012, 'The land of hope' by S.Sion - 2012 or 'Grand Central' by R. Zlotowski - 2013. All this list of films depicting nuclear disasters and their dramatic consequences on the daily life of people contribute to build a frightening picture of nuclear energy in the mind of people. Although any film is fictional it can influence people but also open people's eyes on society issues like sub-contracting, unemployment, risk assessment... (A.C.)

Integrative structure and functional anatomy of a nuclear pore complex

Science.gov (United States)

Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D.; Hogan, Joanna A.; Upla, Paula; Chemmama, Ilan E.; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S.; Wang, Junjie; Williams, Rosemary; Unruh, Jay R.; Greenberg, Charles H.; Jacobs, Erica Y.; Yu, Zhiheng; de La Cruz, M. Jason; Mironska, Roxana; Stokes, David L.; Aitchison, John D.; Jarrold, Martin F.; Gerton, Jennifer L.; Ludtke, Steven J.; Akey, Christopher W.; Chait, Brian T.; Sali, Andrej; Rout, Michael P.

2018-03-01

Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

Integrative structure and functional anatomy of a nuclear pore complex.

Science.gov (United States)

Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D; Hogan, Joanna A; Upla, Paula; Chemmama, Ilan E; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S; Wang, Junjie; Williams, Rosemary; Unruh, Jay R; Greenberg, Charles H; Jacobs, Erica Y; Yu, Zhiheng; de la Cruz, M Jason; Mironska, Roxana; Stokes, David L; Aitchison, John D; Jarrold, Martin F; Gerton, Jennifer L; Ludtke, Steven J; Akey, Christopher W; Chait, Brian T; Sali, Andrej; Rout, Michael P

2018-03-22

Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

International nuclear material safeguards

International Nuclear Information System (INIS)

Syed Azmi Syed Ali

1985-01-01

History can be a very dull subject if it relates to events which have long since lost their relevance. The factors which led to the creation of the International Atomic Energy Agency (IAEA), however, are as important and relevant today as they were when the Agency was first created. Without understanding these factors it is impossible to realise how important the Agency is in the present world or to understand some of the controversies surrounding its future. Central to these controversies is the question of how best to promote the international transfer of nuclear technology without contributing further to the problem of proliferating nuclear explosives or explosive capabilities. One effective means is to subject nuclear materials (see accompanying article in box), which forms the basic link between the manufacture of nuclear explosives and nuclear power generation, to international safeguards. This was realized very early in the development of nuclear power and was given greater emphasis following the deployment of the first two atomic bombs towards the end of World War II. (author)

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)

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

International Nuclear Information System (INIS)

Peltzer, P.

1983-01-01

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) [fr

Nuclear magnetic resonance imaging of the central nervous system

International Nuclear Information System (INIS)

Knaap, M.S. van der; Valk, J.

1989-01-01

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

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).

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)

1992-12-31

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).

Kazakhstan innovation projects in nuclear technologies field

International Nuclear Information System (INIS)

Shkol'nik, V.S.; Tukhvatulin, Sh.T.

2005-01-01

At present in the Republic of Kazakhstan in preparation and realization stage there are several innovation projects related with use of advanced nuclear technologies. Projects are as follows: 'Implementation of Kazakhstan thermonuclear reactor tokamak (KTM)'; 'Implementation at the L.N. Gumilev Eurasian National University the inter-disciplinary research complex on the heavy ions accelerator base'; 'Development of the Technological Park 'Nuclear Technologies Center in Kurchatov city'; 'Development the first in the Central-Asian region Center of Nuclear Medicine and Biophysics'. The initiator and principal operator of these projects is the National Nuclear Center of the Republic of Kazakhstan

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Poland

International Nuclear Information System (INIS)

2015-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment (Licensing; Registration and monitoring of nuclear materials and radioactive sources; High activity sources); 4. Nuclear facilities (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiological protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (The President of the National Atomic Energy Agency - Prezes Panstwowej Agencji Atomistyki (President of the PAA); Minister of Health; Minister of the Environment); 2. Advisory bodies (Council for Nuclear Safety and Radiological Protection); 3. Public and semi-public bodies (Radioactive Waste Management Plant); 4. Research institutes (Central Laboratory for Radiological Protection; National Centre for Nuclear Research; Institute of Nuclear Physics; Institute of Nuclear Chemistry and Technology; Institute of Plasma Physics and Laser Microfusion)

Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant. Simulacao do sistema nuclear de geracao de vapor de uma central PWR

Energy Technology Data Exchange (ETDEWEB)

Reis Martins Junior, L.L. dos.

1980-01-01

The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author).

Determinación de plaguicidas en la cuenca de Salto Grande : Incidencia de los procesos de potabilización sobre los niveles residuales

OpenAIRE

Williman, Celia

2015-01-01

Los problemas de calidad de agua en los lagos y embalses de Argentina se han incrementado por las actividades agrícolas, deforestación, explotación forestal, cría de animales, actividades mineras, escurrimiento urbano y descargas de aguas residuales no tratadas. La región aledaña al embalse Salto Grande, presenta un importante desarrollo agrícola, donde se utilizan numerosos tipos de plaguicidas. Estos compuestos generan contaminación ambiental, ya sea por deriva y/o acumulación en ...

Theoretical nuclear and subnuclear physics

CERN Document Server

Walecka, John Dirk

1995-01-01

This comprehensive text expertly details the numerous theoretical techniques central to the discipline of nuclear physics. It is based on lecture notes from a three-lecture series given at CEBAF (the Continuous Electron Beam Accelerator Facility), where John Dirk Walecka at the time was Scientific Director: "Graduate Quantum Mechanics", "Advanced Quantum Mechanics and Field Theory" and "Special Topics in Nuclear Physics". The primary goal of this text is pedagogical; providing a clear, logical, in-depth, and unifying treatment of many diverse aspects of modern nuclear theory ranging from the non-relativistic many-body problem to the standard model of the strong, electromagnetic, and weak interactions. Four key topics are emphasised in this text: basic nuclear structure, the relativistic nuclear many-body problem, strong-coupling QCD, and electroweak interactions with nuclei. The text is designed to provide graduate students with a basic level of understanding of modern nuclear physics so that they in turn can...

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

International Nuclear Information System (INIS)

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

2012-01-01

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

Annual report 1988 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1989-04-01

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 r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1988 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 the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

Annual report 1991 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.

1992-04-01

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, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 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 the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Annual report 1990 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1991-04-01

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, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 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 the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Development Of Data Acquisition Software For Centralized Radiation Monitoring System

International Nuclear Information System (INIS)

Nolida Yussup; Maslina Mohd Ibrahim; Mohd Fauzi Haris; Syirrazie Che Soh; Harzawardi Hasim; Azraf Azman; Mohd Ashhar Khalid

2014-01-01

Nowadays, with the growth of technology, many devices and equipment's can be connected to the network and internet to enable online data acquisition. Centralized radiation monitoring system utilizes a Local Area Network (LAN) as a communication media for data acquisition of the area radiation levels from radiation detectors in Malaysian Nuclear Agency (Nuclear Malaysia). The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software development on the system server that is responsible to acquire and record the area radiation readings from the detectors. Then the recorded readings are called in a web programming to be displayed on a web site. The readings with the time stamp are stored in the system database for query. Besides acquiring the area radiation levels in Nuclear Malaysia centrally, additional features such as data conversion from mR to μSv and line chart display are developed in the software for effective radiation level trend observation and studies. (author)

Reports submitted by participants from central and eastern european countries and the new independent states

International Nuclear Information System (INIS)

Nersesyan, V.; Rozdyalovskaya, L.; Yatsevich, V.; Soljan, V.; Valcic, I.; Saar, J.; Abraitis, M.; Bieliauskas, V.; Szkultecka, E.; Cutoiu, D.; Chirica, M.T.; Karasev, A.V.; Pospisil, M.; Zlatnansky, J.; Kot, Y.; Shvytai, V.

2000-01-01

In this communication are grouped the reports submitted by participants from central and eastern European countries and the new independent states, concerning their government legislation relative to the nuclear liability in the event of a nuclear accident. (N.C.)

Nuclear at Niagara. 32nd Annual Canadian Nuclear Society conference and 35th CNS/CNA student conference

International Nuclear Information System (INIS)

2011-01-01

The 32nd Annual Canadian Nuclear Society Conference and 35th CNS/CNA Student Conference was held in Niagara Falls, Ontario, Canada on June 5-8, 2011. The theme of the conference, 'Nuclear at Niagara', brought together scientists, engineers, technologists, senior management, government officials, and students interested in all aspects of nuclear science and technology and its applications, including nuclear power generation, fuel production, uranium mining and refining, management of radioactive wastes and used fuel. Other topics include medical and industrial uses of radionuclides, occupational and environmental radiation protection, the science and technology of nuclear fusion, and associated activities in research and development. and applications of energy from the atom. The central objective of this conference was to exchange views on how nuclear science and technology can best serve the needs of humanity, now and in the future. Over 400 delegates from across Canada and other nuclear countries were in attendance.

Cybersecurity: new challenge for nuclear power plants; Ciberseguridad: nuevo reto para las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Mirambel Boquera, J.

2011-07-01

The purpose of this protective strategy is to ensure ability to detect, contain, respond and recover digital systems for monitoring, control and protection and thus ensure business continuity. A defensive strategy that consists of multiple levels is implemented to protect digital systems from unauthorized access, modification erroneous, misuse or any threat that could pose a risk to the Nuclear Security, Physical Security of people and the Radiological Protection, and the Environment.

Nuclear power in the Soviet Bloc

International Nuclear Information System (INIS)

Davey, W.G.

1982-03-01

The growth of Soviet Bloc nuclear power generation to the end of the century is evaluated on the basis of policy statements of objectives, past and current nuclear power plant construction, and trends in the potential for future construction. Central to this study is a detailed examination of individual reactor construction and site development that provides specific performance data not given elsewhere. A major commitment to nuclear power is abundantly clear and an expansion of ten times in nuclear electric generation is estimated between 1980 and 2000. This rate of growth is likely to have significant impact upon the total energy economy of the Soviet Bloc including lessening demands for use of coal, oil, and gas for electricity generation

Nuclear power in the Soviet Bloc

Energy Technology Data Exchange (ETDEWEB)

Davey, W.G.

1982-03-01

The growth of Soviet Bloc nuclear power generation to the end of the century is evaluated on the basis of policy statements of objectives, past and current nuclear power plant construction, and trends in the potential for future construction. Central to this study is a detailed examination of individual reactor construction and site development that provides specific performance data not given elsewhere. A major commitment to nuclear power is abundantly clear and an expansion of ten times in nuclear electric generation is estimated between 1980 and 2000. This rate of growth is likely to have significant impact upon the total energy economy of the Soviet Bloc including lessening demands for use of coal, oil, and gas for electricity generation.

Decree No 82-1050 of 13 December 1982 creating a Central Service for repression of illicit trading in weapons, munitions, explosive products and nuclear, biological and chemical materials

International Nuclear Information System (INIS)

1982-01-01

The Central Service was set up within the Ministry of the Interior and is responsible for the protection of the State and the national territory against criminal attempts, conspiracies and acts of terrorism and is vested with the necessary powers to discharge its duties. It co-operates with the other departments concerned in the study of measures to prevent unlawful use of weapons and nuclear materials. (NEA) [fr

Analysis of the phenomena associated with structural damage using real time vibration analysis

International Nuclear Information System (INIS)

Garcia Peyrano, O; Cismondi, L; Damiani, H; Torres, E

2004-01-01

It is of interest to have analytical methodologies available for the dynamic behavior of large mechanical structures like those in thermal cycle systems of nuclear power plants or in transport systems during the experimental stage prior to their construction, as happens in aeronautics, where prototypes are tested in experimental banks on a scale of 1 to 1. The same does not occur with systems for the generation of electrical energy such as a nuclear power plant or in ships, competition automobiles, railway systems, etc. Not because of the technical impossibility but because of the high costs involved. This work aims to implement a technology based on the analysis of the vibrations to obtain a profile of the modal dynamic response and its influence on the critical components of the mechanisms with the particularity of detecting the preventive location of the component that may suffer a potential damage. The Vibrations Analysis Laboratory has resolved different cases in the Embalse Nuclear Plant, in the Atucha Nuclear Plant, in the Heavy Water Industrial Plant, in the automobile industry and in other industrial areas (CW)

Operation control device for nuclear power plants

International Nuclear Information System (INIS)

Suto, Osamu.

1982-01-01

Purpose: To render the controlling functions of a central control console more centralized by constituting the operation controls for a nuclear power plant with computer systems having substantially independent functions such as those of plant monitor controls, reactor monitor management and CRT display and decreasing interactions between each of the systems. Constitution: An input/output device for the input of process data for a nuclear power plant and indication data for a plant control console is connected to a plant supervisory and control computer system and a display computer system, the plant supervisory control computer system and a reactor and management computer system are connected with a CRT display control device, a printer and a CRT display input/output device, and the display computer system is connected with the CRT display control device and the CRT display unit on the central control console, whereby process input can be processed and displayed at high speed. (Yoshino, Y.)

Nuclear Power Plants (Rev.)

Energy Technology Data Exchange (ETDEWEB)

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

1973-01-01

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

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition); Seguridad de las centrales nucleares: Diseno. Requisitos de seguridad especificos

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Proceedings of the International Conference Nuclear Energy for New Europe 2005

Energy Technology Data Exchange (ETDEWEB)

Mavko, B; Kljenak, I [Nuclear Society of Slovenia (Slovenia)

2005-07-01

International Conference Nuclear Energy for New Europe is an annual meeting of the Nuclear Society of Slovenia. This Cd-Rom is the collection of the 139 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region presented at the title conference. Topics are: reactor physics, nuclear fusion, radiation monitoring, research and training reactors, fluid dynamics, heat and mass transfer, thermal hydraulics, safety analyses, severe accidents, nuclear materials, probabilistic safety assessment, nuclear power plant operation and monitoring, nuclear waste, public safety and environmental issues, nuclear knowledge, education and training, nuclear energy and society, advances in nuclear technology and other topics.

Proceedings of the International Conference Nuclear Energy for New Europe 2005

International Nuclear Information System (INIS)

Mavko, B.; Kljenak, I.

2005-01-01

International Conference Nuclear Energy for New Europe is an annual meeting of the Nuclear Society of Slovenia. This Cd-Rom is the collection of the 139 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region presented at the title conference. Topics are: reactor physics, nuclear fusion, radiation monitoring, research and training reactors, fluid dynamics, heat and mass transfer, thermal hydraulics, safety analyses, severe accidents, nuclear materials, probabilistic safety assessment, nuclear power plant operation and monitoring, nuclear waste, public safety and environmental issues, nuclear knowledge, education and training, nuclear energy and society, advances in nuclear technology and other topics

A central spent fuel storage in Sweden

International Nuclear Information System (INIS)

Gustafsson, B.; Hagberth, R.

1978-01-01

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)

Carl Friedrich von Weizsaecker - a physicist and philosopher in the shade of the nuclear bomb. A conversation on nuclear weapons and the responsibility of nuclear scientists

International Nuclear Information System (INIS)

Schaaf, M.

1996-06-01

The 50th anniversary of the first nuclear explosion (16th July 1945) prompted the editor of this collection to look again at the part played by German physicists in the nuclear weapons issue. Carl Friedrich von Weizsaecker, one of the last surviving witnesses of this period, kindly agreed to give a comprehensive interview on the German nuclear programme and the responsibility of physicists. The interview is published here for the first time and forms the central part of this brochure. It is complemented by two statements by Edward Teller and two historical letters. The author, in preparing this compilation, had in mind to contribute towards science-historical discussion and to give younger colleagues a graphic idea of the conflict surrounding nuclear research. (orig.) [de

Nuclear energy at the turning point

Energy Technology Data Exchange (ETDEWEB)

Weinberg, A.M.

1977-07-01

In deciding the future course of nuclear energy, it is necessary to re-examine man's long-term energy options, in particular solar energy and the breeder reactor. Both systems pose difficultiies: energy from the sun is likely to be expensive as well as limited, whereas a massive world-wide deployment of nuclear breeders will create problems of safety and of proliferation. Nuclear energy's long-term success depends on resolving both of these problems. Collocation of nuclear facilities with a system of resident inspectors are measures that ought to help increase the proliferation-resistance as well as the safety of a large-scale, long-term nuclear system based on breeders. In such a long-term system a strengthened International Atomic Energy Agency (IAEA) is viewed as playing a central role.

Nuclear power in perspective

International Nuclear Information System (INIS)

Ringwood, A.E.

1980-01-01

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

SKODA Nuclear Machinery - tradition and expertise in nuclear power industry

International Nuclear Information System (INIS)

Svitak, F.

1997-01-01

The SKODA Nuclear Machinery company is a major manufacturer of nuclear reactor assemblies and supplier of WWER type primary coolant circuits. In the past, the company was nearly a monopolistic manufacturer of WWER reactor assemblies supplied to the Central and East European countries (except the USSR) grouped in the former Council of Mutual Economic Assistance. Over the 1980-1993 period, 21 units of the WWER-440 type and 3 units of the WWER-1000 type were manufactured. The company keeps abreast of technological progress and has been switching to new manufacturing areas, such as compact storage racks for spent fuel pools, hermetic cable bushings, spent fuel storage and transport casks, and cooperation in the manufacture of neutron flux measuring channels. Technological services provided to nuclear power plants constitute another important field of the company's business. The company's combined expertise in Soviet and Western designed PWRs is a considerable asset. (P.A.)

Directory of nuclear power plants in the world, 1985

International Nuclear Information System (INIS)

Fujii, Haruo

1985-01-01

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

Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Mostaza, J. M.

2011-07-01

Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

Nuclear at Niagara. 32nd Annual Canadian Nuclear Society conference and 35th CNS/CNA student conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

The 32nd Annual Canadian Nuclear Society Conference and 35th CNS/CNA Student Conference was held in Niagara Falls, Ontario, Canada on June 5-8, 2011. The theme of the conference, 'Nuclear at Niagara', brought together scientists, engineers, technologists, senior management, government officials, and students interested in all aspects of nuclear science and technology and its applications, including nuclear power generation, fuel production, uranium mining and refining, management of radioactive wastes and used fuel. Other topics include medical and industrial uses of radionuclides, occupational and environmental radiation protection, the science and technology of nuclear fusion, and associated activities in research and development. and applications of energy from the atom. The central objective of this conference was to exchange views on how nuclear science and technology can best serve the needs of humanity, now and in the future. Over 400 delegates from across Canada and other nuclear countries were in attendance.