WorldWideScience

Sample records for central nuclear almirante

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  3. 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

  4. Critérios de estabilidade atmosférica para a região da Central Nuclear Almirante Álvaro Alberto, Angra dos Reis - RJ Criteria of atmospheric stability for the region around the nuclear power plant Almirante Álvaro Alberto, Angra dos Reis - RJ

    Directory of Open Access Journals (Sweden)

    José Francisco De Oliveira Júnior

    2010-06-01

    Full Text Available Realizaram-se avaliações climatológicas, sazonais e diárias, da estabilidade atmosférica na região da Central Nuclear Almirante Álvaro Alberto (CNAAA, Angra dos Reis - RJ. A climatológica foi baseada no critério de Pasquill-Gifford (P-G para um período de 26 anos (1980-2006 e a sazonal-diária pelos números de Richardson Global (RiB e de Froude (Fr - estudo de caso (2002-05. O Fr foi usado na caracterização do escoamento da região. O critério de P-G mostrou que as classes predominantes foram D, E e F (no período noturno e diurno. Avaliaram-se as classes predominantes com a direção e velocidade do vento, os setores mais freqüentes foram S, SSW, SSE no período diurno e N, NNE, NNW e E no noturno. Quanto à velocidade verificou-se que a classe D foi mais veloz, e as classes E e F menos velozes, em qualquer período. As maiores velocidades foram coincidentes com a brisa marítima. Baseado no RiB, a condição estaticamente estável prevaleceu em comparação às demais, sendo de 79%, seguida da instável (17% e neutra (4%. O Fr indicou que o escoamento na CNAAA foi caracterizado por regime de vento fraco, com forte estabilidade e ar estagnado. A maior parte das ocorrências (63% foi para Fr inferior a 0,1, seguida de poucas ocorrências nas categorias Fr igual a 1,0 (8% e superior a 1,7 (12%. Os critérios utilizados na caracterização da estabilidade na região e na análise do regime de escoamento indicaram a baixa capacidade da atmosfera para a dispersão de poluentes, devido à predominância da condição estável e do regime de bloqueio.The atmospheric stability over the nuclear power plant Almirante Álvaro Alberto (CNAAA, Angra dos Reis - RJ, Brazil, was analyzed at climatological, seasonal, and daily scales. The climatologic analysis was based on the Pasquill-Gifford (P-G for a long-term series of 26 years (1980 - 2006, while the seasonal/daily was performed using the Global Richardson number, RiB, and the Froude number

  5. An experience of marine macrofouling control in Angra 1 - Almirante Alvaro Alberto nuclear power plant

    International Nuclear Information System (INIS)

    One of the greatest problems at the Power Plants that use sea water in the circulating water system, is the development of fouling in its sections. In Central Nuclear Almirante Alvaro Alberto - Angra 1, this fouling is represented by barnacles. These barnacles have contributed significantly to the damaging in the condenser tubes, resulting in the changing from cooper alloy tubes to Titanium ones. To help the understanding of the development and control of fouling, some researches and observations have been made using techniques adequated to Angra 1. The low-level continuous chlorination, the water flux variation and the continuous cleaning tubes system (AMERTAP) combined and used in circulation water sistem, showed satisfactory preliminar results in fouling control. (Author)

  6. Measurement of the meteorological parameters in Almirante Alvaro Alberto nuclear power plant using captive balloon

    International Nuclear Information System (INIS)

    A methodology to obtain the meteorological parameters in the vicinity of the Almirante Alvaro Alberto nuclear power plant is presented. The study of the atmospheric dispersion is done by the analysis of the results and it is a complement of the meteorological operation of Angra-1 and pre-operation of Angra-2 and 3 program. (M.C.K.)

  7. Influence of marine sediments in the distribution of the main radionuclides of the effluent from the nuclear power plant Almirante Alvaro Alberto (Unit 1)

    International Nuclear Information System (INIS)

    This study aimed to: 1) Characterize bottom sediments of the Angra dos Reis region, in the dispersion area of the effluent of the central Almirante Nuclear Alvaro Alberto, Unit 1. 2) Determining the adsorption capacity of these sediments to the long half-life and mean radionuclides to be released in the reactor effluent in a higher concentration. 3) Estimate the fraction of the different studied radionuclides that will be immobilized in sediments. 4) Identify critical radionuclides available for food chain

  8. Emission of {sup 14}C by the Almirante Alvaro Alberto Nuclear Power Plant 1 and 2 and their local effects on the environmental levels; Emissao de {sup 14}C pelas unidades 1 e 2 da Central Nuclear Almirante Alvaro Alberto (CNAAA) e seu efeito local nos niveis ambientais

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Cintia Melazo

    2006-07-01

    {sup 14}C is a is a long-lived beta-emitting nuclide (T{sub 1/2} = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable {sup 14}N({sup 14}N(n,p){sup 14}C). Although in a lesser extent, nuclear power plants produce {sup 14}C as well during their routine operation. Since it is converted in {sup 14}CO{sub 2} and mixed throughout the atmosphere, it is incorporated into plant tissues, via photosynthesis process, and hence in food chain. Because of the biological importance of {sup 14}C and long half-life, it is of interest to quantify the amounts released by nuclear industry. The Brazilian nuclear central named Nuclear Central Admiral Alvaro Alberto (CNAAA) has two nuclear reactors of PWR type in operation, Angra I (657 MWe) and Angra II (1350 MWe), and one under construction, Angra III (1309 MWe PWR). The aim of this study was to determine the strength of the sources and the {sup 14}C content in the environment through analyses of air, vegetation and soils taken within 5 km (the influenced area) of CNAAA. The thesis consists of an extensive review about the subject (part one) and of four papers (part two). The first paper is about the determination of {sup 14}C concentrations released by reactors (source strength). For Angra I, a device was developed in order to sample the gaseous effluents and for Angra II, a commercial monitoring system had already been implemented since its initial operation (2001). The {sup 14}C can be emitted as hydrocarbons, CO or CO{sub 2}, depending on the type of reactor. For PWRs, the main chemical form released is hydrocarbons (80 %). The monitoring system of Angra I was planned to determine both CO{sub 2} and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO{sub 2} by using a Pd/Al{sub 2}O{sub 3} catalyst at 450 deg C. The liquid scintillation was the method employed to measure the samples. The second one concerns the atmospheric dispersion of the released

  9. Occupational exposure analysis at the unit 1 of Almirante Alvaro Alberto nuclear power plant

    International Nuclear Information System (INIS)

    In order to obtain a complete knowledge of occupational conditions in a PWR nuclear power station, the individual and collective dose distributions are being analysed during the Angra I (Rio de Janeiro - Brazil) station activities. Work conditions with identification of critical areas and groups as well as classification of tasks related to reactor maintenance and startup periods are also studied. This paper analyses radiological data measured at different power levels of the reactor and during maintenance and repair services as well as the refueling operation. (author)

  10. Safety probabilistic study of Almirante Alvaro Alberto nuclear power plant-Unit I

    International Nuclear Information System (INIS)

    The phase A of probabilistic safety study of Angra I nuclear power plant is presented, to be used by CNEN and FURNAS Centrais Eletricas S.A. as standard model in operational and safety analysis. The methodology applied is a modernization of WASH 1400/2.11/ study. Angra I safety systems are described. The selection and qualification of initiating sequence accident events which can damage the reactor core are done. The accident scenes are developed using the method of event trees. The reactor in subcritical condition (pressure, fuel temperature within limits and controlled level of reactor vessel) is studied during 24 hours. The uncertainness in failure probabilities of systems and in the determination of sequence frequencies for core danification are evaluated. Total frequency of sequences which cause the fusion of reactor core are presented. (M.C.K.)

  11. Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

    International Nuclear Information System (INIS)

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams

  12. Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

    International Nuclear Information System (INIS)

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

  13. Determination of concentration factors for Chromium cesium, iron and cobalt in corvine and shrimp in the vicinities of Almirante Alvaro Alberto Nuclear Power Plant

    International Nuclear Information System (INIS)

    In order to verify if the concentration factors for dose calculations in critical population recommended by the International Atomic Energy (IAEA), on the Safety Series 57, are in agreement with local factors, studies were carried out at Piraquara de Dentro bay, a region in the vicinities of the Almirante Alvaro Alberto Nuclear Power Plant (CNAAA). Chromium, caesium, iron and cobalt concentration factors for corvine and shrimp were determined using the activation analysis method by neutrons, taking into account the same behaviour between radioactive and stable from the same physicochemical form. This study has evidenced that: The local values of cesium, iron and cobalt concentration factors for corvine (fish) are in the same order of magnitude of the IAEA recommended values; The chromium, caesium and cobalt concentration factor values determined for shrimp for Piraquara de Dentro bay are in the same order of magnitude or smaller than those proposed by IAEA, while the concentration factor value for ion is one order of magnitude higher than the IAEA recommended value. (author)

  14. Variações na estrutura da comunidade zooplanctônica próxima a usina I da Central Nuclear Almirante Álvaro Alberto (C.N.A.A.A.) - (Angra Dos Reis-R.J.-Brasil) - Ciclo 1980/81 E 1991/93

    OpenAIRE

    Cristina de Oliveira Dias; Sérgio L.C Bonecker; Catarina R. Nogueira

    1999-01-01

    During the years of 1980/80 was performed a ecological study in Ribeira Bay (Angra dos Reis-R.J.-Brazil) in order to provide informations about of the planktonic community in pre-operational conditions, in the region of the Admiral Álvaro Aberto Nuclear Power Plant (C.N.A.A.A.). After 10 years of activities of the Nuclear Power Plant the zooplankton material was obtained in vertical hauls with a net of 150 μm at two fixed points (Piraquara de Fora Cove and Itaorna Beach) in order to stud...

  15. Zooplankton as an environmental monitoring tool in the area under Almirante Alvaro Alberto nuclear power plant influence

    International Nuclear Information System (INIS)

    Available as short communication only. Angra nuclear power plant refrigeration systems uses sea water collected in Itaorna and discharged in Piraquara de Fora, with an increase in temperature. Besides this, chlorine is added to avoid fouling in the circulation system. Zooplankton, small and generally microscope organism is very sensible to environmental changes. This work describes the methodology to evaluate the influence of Angra nuclear power plant liquid effluents in zooplankton organisms describing results and verifying impacts in this area. (author). 4 refs, 4 figs

  16. Emission of 14C by the Almirante Alvaro Alberto Nuclear Power Plant 1 and 2 and their local effects on the environmental levels

    International Nuclear Information System (INIS)

    14C is a is a long-lived beta-emitting nuclide (T1/2 = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable 14N(14N(n,p)14C). Although in a lesser extent, nuclear power plants produce 14C as well during their routine operation. Since it is converted in 14CO2 and mixed throughout the atmosphere, it is incorporated into plant tissues, via photosynthesis process, and hence in food chain. Because of the biological importance of 14C and long half-life, it is of interest to quantify the amounts released by nuclear industry. The Brazilian nuclear central named Nuclear Central Admiral Alvaro Alberto (CNAAA) has two nuclear reactors of PWR type in operation, Angra I (657 MWe) and Angra II (1350 MWe), and one under construction, Angra III (1309 MWe PWR). The aim of this study was to determine the strength of the sources and the 14C content in the environment through analyses of air, vegetation and soils taken within 5 km (the influenced area) of CNAAA. The thesis consists of an extensive review about the subject (part one) and of four papers (part two). The first paper is about the determination of 14C concentrations released by reactors (source strength). For Angra I, a device was developed in order to sample the gaseous effluents and for Angra II, a commercial monitoring system had already been implemented since its initial operation (2001). The 14C can be emitted as hydrocarbons, CO or CO2, depending on the type of reactor. For PWRs, the main chemical form released is hydrocarbons (80 %). The monitoring system of Angra I was planned to determine both CO2 and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO2 by using a Pd/Al2O3 catalyst at 450 deg C. The liquid scintillation was the method employed to measure the samples. The second one concerns the atmospheric dispersion of the released radiocarbon through measurements of air samples taken with 3 km from power plants, in five different wind

  17. Study of the influencies of Angra-1 nuclear power plant construction in Angra dos Reis

    International Nuclear Information System (INIS)

    The report presents a comprehensive evaluation of the influence caused by Angra-1 Nuclear Power Plants (Central Nuclear Almirante Alvaro Alberto) construction on the Angra dos Reis City - Rio de Janeiro - Brazil. The analysis performed adopts a multi-dimensional methodology with four analysis dimensions: political-institutional, physical-territorial, social-economic and temporal. (author)

  18. Study on the marine fouling communities near Central Nuclear Almirante Alvaro Alberto (CNAAA), Angra dos Reis, R.J. (Brazil)

    International Nuclear Information System (INIS)

    The effects of chemical and thermal effluents from CNAAA (Angra 1 Reactor) on local biota are studied. The seasonal variations and the ecologic aspects are presented and the biota is used as pollution indicator. The biota taxonomic study is desctibed. (M.A.C.)

  19. WIND DIRECTION, pH and other data from ALMIRANTE CAMARA and ALMIRANTE SALDANHA from 1979-01-07 to 1979-12-11 (NODC Accession 8100468)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Water depth and other station data collected from ALMIRANTE CAMARA, ALMIRANTE SALDANHA and other Platforms for one year. The data was collected between January 7,...

  20. Nuclear Energy in Central Europe 98, Proceedings

    International Nuclear Information System (INIS)

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

  1. Nuclear insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  3. Filosofia schopenhaueriana e literatura machadiana: em torno do conto "Noite de almirante" Schopenhauerian philosophy and Machadian literature: around the short story "Noite de almirante"

    Directory of Open Access Journals (Sweden)

    Jair Lopes Barboza

    2000-01-01

    Full Text Available Trata-se neste artigo de mostrar como se dá a recepção de alguns elementos da filosofia schopenhaueriana, como a oposição entre intelecto e vontade, na literatura de Machado de Assis. Com efeito, examinado o conto "Noite de almirante", pode-se dizer que a personagem Genoveva faz as vezes da vontade, ao passo que Deolindo é guiado pelo intelecto.This paper deals with the reception of some elements of Schopenhauerian philosophy, such as the oposition between intellect and will, in the literature of Machado de Assis. Indeed, if we examine the short story "Noite de almirante", we can see that the character Genoveva represents the will, while Deolindo is guided by the intellect.

  4. Central Bureau for Nuclear Measurements

    International Nuclear Information System (INIS)

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

  5. Nuclear energy options for Central Asia

    International Nuclear Information System (INIS)

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

  6. Central depression of nuclear charge density distribution

    International Nuclear Information System (INIS)

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

  7. Nuclear Safety in Central and Eastern Europe

    International Nuclear Information System (INIS)

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

  8. Towards Quantum Transport for Central Nuclear Reactions

    CERN Document Server

    Danielewicz, Pawel; Barker, Brent

    2016-01-01

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

  9. Central depression of the nuclear charge distribution

    International Nuclear Information System (INIS)

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

  10. Zooplankton data collected using net casts from the ALMIRANTE SALDANHA in the Northeast Atlantic Ocean from 05 November 1958 to 15 January 1959 (NODC Accession 0000942)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Zooplankton data were collected using net casts in the Northeast Atlantic Ocean from ALMIRANTE SALDANHA. Data were collected from 05 November 1958 to 15 January...

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  13. Central Institute of Nuclear Research Rossendorf 25 years old

    International Nuclear Information System (INIS)

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

  14. Environmental monitoring program of the uranium enrichment facility Almirante Alvaro Alberto

    International Nuclear Information System (INIS)

    In this report, the Environmental Monitoring Program of the Uranium Enrichment Facility Almirante Alvaro Alberto is outlined and the results obtained during the preoperational period are presented. Information concerning the population distribution, the use of water and land, the local agricultural production and the local meteorology are also available. In order to evaluate the levels of the background radiation, sample of water, air and biological and terrestrial indicators were analysed. Measurements were performed of natural gamma emitters concentrations levels and of uranium in air, surface water, precipitation, groundwater, river sediment, soil, grass, vegetation and various foodstuffs. For direct measurement of background radiation levels a solid state dosimeter network was used. Results are also presented for the analysis of non radioactive pollutants in the water samples and for the particles and gaseous fluorides concentration in the atmosphere. (author)

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

    International Nuclear Information System (INIS)

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

  16. Reconstrucción de los procesos de sedimentación y contaminación en la Bahía de Almirante (Bocas del Toro), Panamá, en los últimos 100 años utilizando técnicas nucleares.

    OpenAIRE

    Peña, Alexis

    2012-01-01

    En el año 2007, el Organismo Internacional de Energía Atómica (OIEA) inició un proyecto de 4 años titulado “Aplicación de técnicas nucleares en la solución de problemas específicos del manejo integrado de las zonas costeras en el Caribe”, RLA/7/012. El objetivo general de este proyecto fue desarrollar y mejorar las capacidades para reducir la degradación, por causas antrópicas de los ecosistemas costeros de la región del Gran Caribe utilizando técnicas nucleares en apoyo de la gestión integra...

  17. Risk analysis update of the Radiation Monitor Calibration Laboratory of the Almirante Alvaro Alberto Power Station

    International Nuclear Information System (INIS)

    In 2001, a Probabilistic Safety Assessment (PSA) of the Radiation Monitor Calibration Laboratory of the Almirante Alvaro Alberto Power Station (CNAAA) was performed. The main purpose of this work was to update the original PSA study and to obtain the updated radiologic risk, as well as to include a human reliability analysis of the procedure of radiation monitor calibration. Some accident scenarios were incorporated for evaluating their importance for an accident that might expose a worker to gamma radiation. For obtaining the probability of occurrence of an exposition of a worker during an accident, the Bayesian approach has been used for the calculation of the irradiator failure probability, for this approach is often used when few plant information is available. For the other equipment used in the radiation monitor calibration, the exponential distribution is used to model their failure times for they are assumed to be in their useful life period. The human reliability was modeled by the THERP technique. Although more accident scenarios are considered in this work, including the contribution of human errors, a conservative approach was not used and thus a smaller radiological risk, about one order magnitude smaller was obtained. (author)

  18. Nuclear Power in South-Central Brazil

    International Nuclear Information System (INIS)

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

  19. 30 years of Central Institute for Nuclear Research at Rossendorf

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

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

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

    International Nuclear Information System (INIS)

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

  2. Centrales nucleares en España : el parón nuclear

    OpenAIRE

    Sanz Díaz, Benito (1949-)

    1984-01-01

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

  3. The nuclear sector in Russia and Central Europe

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  5. Environmental monitoring (operational period) of the uranium enrichment facility Almirante Alvaro Alberto. Quadrimonthly report of gamma spectroscopy measurements: march to june 1988

    International Nuclear Information System (INIS)

    In this report we present the assessment of the environmental monitoring radiation levels during the operation period of the Uranium Enrichment Facility Almirante Alvaro Alberto from March to July 1988. The purpose was achieved by sampling and analyzing using gamma spectrometry, water and terrestrial and biological indicators. (author)

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

    International Nuclear Information System (INIS)

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

  7. Experience acquired by Furnas for licensing nuclear power plants

    International Nuclear Information System (INIS)

    The system for licensing of Almirante Alvaro Alberto Nuclear Power Plant-Unit 1 is presented. The process phases for reactor construction and operation are described: preliminary site approval; bases for safety review; partial construction permits; final construction permits; emission of final report of safety analysis; initial operation license and permanent operation license. (M.C.K.)

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

    International Nuclear Information System (INIS)

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

  9. 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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  12. 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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. 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

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

    International Nuclear Information System (INIS)

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

  18. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    International Nuclear Information System (INIS)

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  19. Los límites morales de la autoridad militar : la Almirante Helena Cain en "Galáctica, estrella de combate"

    OpenAIRE

    Martín Alegre, Sara

    2010-01-01

    La Almirante Helena Cain protagoniza un controvertido arco narrativo en la serie de ciencia-ficción Galáctica, estrella de combate (2004-2009), con los episodios Pegasus (2x10) y el doble La nave resurrección (2x11 y 2x12), más la película para televisión, Razor. Cain combina cualidades muy positivas con otras muy negativas, tales como su autoritarismo, algo que la hace un personaje ideal para examinar los límites del feminismo y el impacto del militarismo en el fantástico actual (que son los...

  20. Conservation study of the stone material used in the Culture House of Almirante Oquendo, in San Sebastian

    Directory of Open Access Journals (Sweden)

    Rodríguez-Maribona, L.

    1999-09-01

    Full Text Available The historical heritage of our country is mainly made up of masonry, playing the sandstones an important role. However, because of the effect of environmental conditions and pollution, these materials can loose their cement, and eventually disintegrate. Chemical consolidants can be applied in order to prevent and stop these decay process, which, when there is a lack of cement, fix the stone grains, enhancing the strength and durability of the In order to ensure the success of the application of these products in restoration works, preliminary studies should he carried out, so as to define the suitability of their use, and select the most appropriate consolidant for each specific case, as the reliability of these products is mainly determined by the microstructure of the stone material under study. This paper describes a study which was carried out on Igueldo sandstone from the main façade of the Casa de Cultura del Almirante Oquendo, in San Sebastian, which aimed at establishing the most suitable consolidation technique for the stone degradation processes observed. Firstly, the study dealt with the diagnosis of the pathologies which affected the stone from this building. Furthermore, 6 commercial consolidants were tested on quarry stone. Finally, the results were validated applying these products in real work conditions, what enabled us to select the most appropriate treatment for the restoration of the main façade of the building.

    El Patrimonio Histórico-Artístico de nuestro país, está constituido, principalmente, por edificios de piedra de sillería, en los que las areniscas juegan un papel muy importante. Sin embargo, debido, fundamentalmente, a las condiciones medioambientales y a la contaminación, estos materiales pueden perder su matriz cementante y sufrir una desintegración. Para prevenir y frenar estos fenómenos de deterioro, se pueden emplear productos consolidantes que, en ausencia de matriz cementante, fijan los

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

    International Nuclear Information System (INIS)

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

  2. 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.

  3. Nuclear magnetic resonance imaging of the central nervous system

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  6. Oceanographic Station Data and temperature profiles from bottle and XBT casts from the ALMIRANTE IRIZAR and other platforms as part of the International Decade of Ocean Exploration / International Ocean Studies / First Dynamic Response and Kinematics Experiment in the Drake Passage (IDOE/ISOS/FDRAKE) from 18 January 1975 to 06 November 1982 (NODC Accession 8700110)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Oceanographic Station Data and temperature profiles were collected from bottle and XBT casts from the ALMIRANTE IRIZAR and other platforms from 18 January 1975 to...

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

    International Nuclear Information System (INIS)

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

  8. Application of an expert system for real time diagnosis of the limiting conditions for operation in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Paiva, Gustavo Varanda; Schirru, Roberto, E-mail: gustavopaiva@poli.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (brazil). Programa de Engenharia Nuclear

    2015-07-01

    In the history of nuclear power plants operation safety is an important factor to be considered and for this, the use of resistant materials and the application of redundant systems are used to make a plant with high reliability. Through the acquisition of experience with time and accidents that happened in the area, it was observed that the importance of creating methods that simplify the operator work in making decisions in accidents scenarios is an important factor in ensuring the safety of nuclear power plants. This work aims to create a program made with the Python language, which with the use of an expert systems be able to apply, in real time, the rules contained in the Limiting Conditions for Operation (LCO) and tell to the operator the occurrence of any limiting conditions and the occurrence of failure to perform the require actions in the time to completion. The generic structure used to represent the knowledge of the expert system was a fault tree where the events of this tree are objects in program. To test the accuracy of the program a simplified model of a fault tree was used that represents the LCO of the nuclear power station named Central Nuclear Almirante Alvaro Alberto 1. With the results obtained in the analysis of the simplified model it was observed a significant reduction in the time to identify the LCO, showing that the implementation of this program to more complex models of fault tree would be viable.(author)

  9. Application of an expert system for real time diagnosis of the limiting conditions for operation in nuclear power plants

    International Nuclear Information System (INIS)

    In the history of nuclear power plants operation safety is an important factor to be considered and for this, the use of resistant materials and the application of redundant systems are used to make a plant with high reliability. Through the acquisition of experience with time and accidents that happened in the area, it was observed that the importance of creating methods that simplify the operator work in making decisions in accidents scenarios is an important factor in ensuring the safety of nuclear power plants. This work aims to create a program made with the Python language, which with the use of an expert systems be able to apply, in real time, the rules contained in the Limiting Conditions for Operation (LCO) and tell to the operator the occurrence of any limiting conditions and the occurrence of failure to perform the require actions in the time to completion. The generic structure used to represent the knowledge of the expert system was a fault tree where the events of this tree are objects in program. To test the accuracy of the program a simplified model of a fault tree was used that represents the LCO of the nuclear power station named Central Nuclear Almirante Alvaro Alberto 1. With the results obtained in the analysis of the simplified model it was observed a significant reduction in the time to identify the LCO, showing that the implementation of this program to more complex models of fault tree would be viable.(author)

  10. AP1000, a nuclear central of advanced design

    International Nuclear Information System (INIS)

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

  11. Nuclear power plant insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Gullapalli Vamsi; Murthy Praveen; Murthy K

    1995-01-01

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

  15. Annual report 89. Central Bureau for nuclear measurements

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Guthe, Kurt

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Institute of Scientific and Technical Information of China (English)

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

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

  1. 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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  9. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Torralbo, J. R.

    2016-08-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  15. 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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    1995-12-01

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

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

    Directory of Open Access Journals (Sweden)

    Gullapalli Vamsi

    1995-01-01

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

  6. Analysis of the loss of coolant accident due to the faiture in the open position of two pressurizer relief valves, for Angra-1 nuclear power plant

    International Nuclear Information System (INIS)

    A study of the modeling techniques adequate for simulating the loss of coolant accident caused by stuck open pressurizer relief valves, using the RELAP4-MOD5 code, is performed and the model developed is applied to the analysis of this kind of accident for the Central Nuclear Almirante Alvaro Alberto Unit (Angra 1). The thermal hydraulic behavior of the reactor cooling system, when subjected to a loss of main feedwater followed by the failure in the open position of two pressurizer relief valves, is determined. The relief valves are assumed to fail in the totally open position, delivering the maximum massflow through the discharge line. The RELAP4-MOD5 code is shown to be adequate for this kind of analysis, and the detailed prediction of the thermal hydraulic behavior of the Reactor Coolant System is thus possible. The eficiency of the emergency core cooling system of Angra 1 is demonstrated, the fuel elements remaining covered by the coolant during all the accident, and the peak clad temperatures are kept within design limites, ensuring the integrity of the core. (Author)

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Ibanez, M.

    2013-09-01

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

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

    CERN Document Server

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

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  15. 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.

  16. 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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Institute of Scientific and Technical Information of China (English)

    Christian Engelmann; Falk Weih; Ronny Haenold

    2014-01-01

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

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

    CERN Document Server

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, J. R.

    2011-07-01

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

  3. 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.

  4. 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.)

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

    OpenAIRE

    Roca-Cusachs Maennicke, Beatriz

    2006-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

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

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

    International Nuclear Information System (INIS)

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

  8. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    Science.gov (United States)

    2010-03-03

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

  9. Evaluation of the ICRU operational magnitudes implantation for the photon radiation at the Angra I and Angra II nuclear power plants

    International Nuclear Information System (INIS)

    The measurements of photon radiation field intensity are usually performed by a radiation protection technician trained and having skill in using radiation rate meters. Nowadays, these measurements are reported on exposure quantity and used to protect exposed individuals against the radiation risks while executing their activities. The International Commission on Radiation Units and Measurements - ICRU - defined the operational quantity ambient equivalent dose H*(10). This quantity is accepted by the scientific community as the best estimative of the protection quantity effective dose, which can not be directly measured. The operational quantity H*(10) was introduced in Brazilian rules by the National Commission of Nuclear Energy - CNEN (2005a), although its adoption was conditioned to studies of convenience and applicability of implementation. The present work may contribute to these studies, as it presents the evaluation of H*(10)'s implementation at the Nuclear Central Almirante Alvaro Alberto - CNAAA. The evaluation involved radiological tests - the energy dependence and angular dependence - applied to six types of photon radiation rate meters utilized at the CNAAA, with represent around 83% of the total number of rate meters in use by CNAAA. The result of this evaluation is favorable to the quantity H*(10)'s implementation. Suggestions are presented in order to update de rate meters and the technical and administrative procedures related to the Laboratory of Calibration of Rate Meters - LCMR, belonging to CNAAA. Thus, it could be possible to perform the calibration of the rate meters at the nuclear installation. The results obtained allows to carry out new evaluations of H*(10)'s implementation on installations that perform measurements with radiation rate meters on the practice of radiation protection, in order to adopt the H*(10) quantity in our country. (author)

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

    CERN Document Server

    Helenius, Ilkka; Eskola, Kari J

    2016-01-01

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

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

    International Nuclear Information System (INIS)

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

  12. 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)

  13. Evaluation of the ICRU operational magnitudes implantation for the photon radiation at the Angra I and Angra II nuclear power plants; Avaliacao da implantacao das grandezas operacionais do ICRU para a radiacao de fotons nas usinas nucleares Angra I e II

    Energy Technology Data Exchange (ETDEWEB)

    Viana, Ronaldo do Nascimento

    2006-07-01

    The measurements of photon radiation field intensity are usually performed by a radiation protection technician trained and having skill in using radiation rate meters. Nowadays, these measurements are reported on exposure quantity and used to protect exposed individuals against the radiation risks while executing their activities. The International Commission on Radiation Units and Measurements - ICRU - defined the operational quantity ambient equivalent dose H{sup *}(10). This quantity is accepted by the scientific community as the best estimative of the protection quantity effective dose, which can not be directly measured. The operational quantity H{sup *}(10) was introduced in Brazilian rules by the National Commission of Nuclear Energy - CNEN (2005a), although its adoption was conditioned to studies of convenience and applicability of implementation. The present work may contribute to these studies, as it presents the evaluation of H{sup *}(10)'s implementation at the Nuclear Central Almirante Alvaro Alberto - CNAAA. The evaluation involved radiological tests - the energy dependence and angular dependence - applied to six types of photon radiation rate meters utilized at the CNAAA, with represent around 83% of the total number of rate meters in use by CNAAA. The result of this evaluation is favorable to the quantity H{sup *}(10)'s implementation. Suggestions are presented in order to update de rate meters and the technical and administrative procedures related to the Laboratory of Calibration of Rate Meters - LCMR, belonging to CNAAA. Thus, it could be possible to perform the calibration of the rate meters at the nuclear installation. The results obtained allows to carry out new evaluations of H{sup *}(10)'s implementation on installations that perform measurements with radiation rate meters on the practice of radiation protection, in order to adopt the H{sup *}(10) quantity in our country. (author)

  14. 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)

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

    OpenAIRE

    Zamora Povea, Imanol

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-01-31

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

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

    OpenAIRE

    J.A. Menéndez

    2009-01-01

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

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

    Directory of Open Access Journals (Sweden)

    J.A. Menéndez

    2009-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-09-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

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

  4. 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.

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

    International Nuclear Information System (INIS)

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

  6. 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.)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Gadó János

    2014-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Gadó János

    2014-01-01

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

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

    Science.gov (United States)

    Gadó, János

    2014-09-01

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

  14. 1989 annual report of the Rossendorf Central Institute of Nuclear Research

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez-Bolanos, M.

    2008-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    CERN Document Server

    Afanasjev, A V

    2005-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2016-08-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    CERN Document Server

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Afanasjev, A. V.; Frauendorf, S.

    2006-01-01

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

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

    CERN Document Server

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

    2007-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    González Celades, María

    2015-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2003-08-01

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

  1. 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.

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  6. A digital simulation of a pressurizer in a PWR nuclear power plant

    International Nuclear Information System (INIS)

    A model for pressurizer digital simulation of a PWR nuclear power plant during transients, considering all pressurizer control features, is presented. The pressurizer is divided into two regions separated by a water-vapor interface and non-equilibrium conditions are considered. The particular thermodynamic process followed during insurge and outsurges is determined at each instant of analysis without any previous assumption. The pressure behavior is defined by an explicit equation in any of four possible pressurizer thermodynamic conditions. Thermodynamic properties of steam and water are computed by ASME subroutines and the mathematical formulation presented in this study was programed in FORTRAN IV for a Burroughs-6700 digital computer system. This program was employed to simulate the Shippingport Atomic Power Station and Almirante Alvaro Alberto Nuclear Power Plant - Unit 1 pressurizers. The test results compared with experimental or vendor data show the validity of this analysis method. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-12-09

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

  8. Análise Bioestratigráfica com Base em Foraminíferos de Três Testemunhos da Região do Leque Almirante Câmara na Bacia de Campos, RJ.

    Directory of Open Access Journals (Sweden)

    David Bentes

    2007-07-01

    Full Text Available A Bacia de Campos é a principal áreaprodutora de hidrocarbonetos do país. A descobertade campos gigantes nessa bacia levou à intensificaçãodos estudos dos depósitos em águas profundas ehiperprofundas, tanto da dinâmica de sua gênese eevolução, quanto da tecnologia de produção. Assim,o estudo da bioestratigrafia do Quaternário dessabacia adquire importância, pois fornece uma molduraestratigráfica para a reconstituição da sedimentaçãonessa área. O objetivo do presente trabalho consisteno reconhecimento de biozonas com base emforaminíferos e na correlação estratigráfica de poçosperfurados no talude continental. O material estudadoé proveniente de três testemunhos coletados em2001, no Sistema Almirante Câmara (lâmina d’águaentre 1050 e 2400 m, pelo projeto “ImageamentoGeofísico do Sistema Turbidítico Moderno em ÁguasProfundas da Bacia de Campos”, desenvolvidopelo Depto. de Geologia/UFRJ em parceria com aPETROBRAS. Foram analisadas 77 amostras, comespaçamento de 3cm a 30cm, de acordo com critérioslitológicos e com a necessidade de um detalhamentomaior dos intervalos estudados. Em laboratório, asamostras foram pesadas (10 g e processadas segundometodologia tradicional para estudo de microfósseiscalcários. Em seguida, cada amostra foi peneiradaa seco para triagem, identificação e contagem. Aidentificação e classificação taxônomica seguiuBolli & Saunders (1985. In: Bolli et al. PlanktonStratigraphy e Kennet & Srinivasan (1983. NeogenePlanktonic Foraminifera: a Phylogenetic Atlas. Obiozoneamento utlizado como referência foi o deEricson & Wollin (1968. Sciences, v.162, refinadopor Vicalvi (1997, Bol.Geoci.Petrobras, v.11, n.1/2;1999. PPGG/UFRJ,Tese D.Sc.. Foram reconhecidasas biozonas Z (Holoceno, Y e X (Pleistoceno Finale identificado um possível hiato, englobando ointervalo Y5 – Y2; as taxas de sedimentação foramcalculadas para os intervalos Z, parte superior de Y1e Y1 total.

  9. Variações Paleoclimáticas e Registro Deposicional do Pleistoceno superior de Testemunhos do Sistema Almirante Câmara (Bacia de Campos, Baseado em Foraminíferos. s

    Directory of Open Access Journals (Sweden)

    Aristóteles de Moraes Rios-Netto

    2007-07-01

    Full Text Available O Quaternário é caracterizado pela alternância de intervalos glaciais e interglaciais. Como conseqüência dessas mudanças, a dinâmica de sedimentação marinha também é afetada. Nos intervalos mais quentes, com o nível do mar alto, regiões dos atuais talude inferior e sopé continentais recebem naturalmente sedimentação pelágica; nos intervalos mais frios, quando o nível do mar baixa,parte da plataforma continental é exposta, cânions são gerados, sedimentos de plataforma e talude superior são retrabalhados e lançados em áreas mais profundas. Todas essas mudanças são tambémacompanhadas de câmbios na microbiota marinha e, conseqüentemente, no registro microfossilífero. O presente trabalho pretende contribuir no entendimento das variações climáticas ocorridas no Pleistoceno Final e Holoceno (em especial nos últimos 25 Kano Atlântico Sul Ocidental, e sua relação com as variações do nível do mar e do comportamento das massas d’água e com movimentos de massa no talude continental. Estão sendo estudadas cerca de 100amostras, retiradas a cada três a 30 cm, provenientes de cinco testemunhos, coletados sob lâmina d’água de 550 a 2420 m, no Sistema Almirante Câmara, Bacia de Campos, em 2001, pelo projeto “ImageamentoGeofísico do Sistema Turbidítico Moderno em Águas Profundas da Bacia de Campos”. Em laboratório, as amostras foram pesadas (cinco a 11 g, processadas segundo metodologia tradicional para microfósseiscalcários quaternários, e peneiradas a seco para triagem, identificação e contagem. A interpretação paleoclimática baseia-se, principalmente, em Vicalvi (1997, Bol.Geoci.Petrobras, v.11, n.1/2; 1999. PPGG/UFRJ,Tese D.Sc.. As análises realizadas até o momento levaram ao reconhecimento do último intervalo interglacial, o último glacial e o atual intervalo pós-glacial; uma análise detalhada dointervalo correspondente aos últimos 25 Ka, em um dos testemunhos, permitiu a observação de

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2016-04-01

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

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

    CERN Document Server

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

    2005-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-04-01

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

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

    OpenAIRE

    Codinach Fitó, Marc

    2008-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cicero, R.; Corchon, F.

    2011-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Calatayud, M. A.; Sainero, J.

    2014-10-01

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

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

    International Nuclear Information System (INIS)

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

  3. 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)

  4. Nuclear

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed Hassan

    2003-01-01

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

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

    International Nuclear Information System (INIS)

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

  9. 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).

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  13. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  16. The marine environment monitoring in Saco Piraquara de Fora after the beginning of the Angra 2 nuclear power plant operation

    International Nuclear Information System (INIS)

    The goal of this paper is to evaluate the environmental monitoring around the Almirante Alvaro Alberto Nuclear Power Station after the beginning the operation of Unit II, in July 2000. The Environmental Monitoring Laboratory collects several environmental samples and analyses them radiometrically to determine the presence of artificial radionuclides. In the Environmental Monitoring Laboratory, the samples are prepared and analysed following international procedures and the activities of the detectable radionuclides are obtained by gamma spectrometry. The Environmental Monitoring Laboratory analyses tritium in sea water as well. This paper will describe only the monitoring of the marine samples and the results of the measurements are compared with those obtained in pre-operational time of Angra 1 (1978 - 1982), Angra 2 (1996 - 2000) and those obtained in operational time of the units until 2008. The results show that, since 1982 until now, there is no impact on marine environment caused by the operation of Angra 1 and Angra 2. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Antonio Torres - Valle

    2012-01-01

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

  1. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cano, J. C.; Ruiz, S.

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Dumas, H.; Sesma, J. L.

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Mendez, M.

    2012-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    International Nuclear Information System (INIS)

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

  18. Sorption of 60Co and 137Cs in sediments at Piraquara de Fora, Angra dos Reis, RJ, Brazil

    International Nuclear Information System (INIS)

    In this study, sediment of Piraquara de Fora, located near the launch area of the effluents of the Central Nuclear Almirante Alvaro Alberto - CNAAA Nuclear Power Plants, were collected. It were determined the parameters particle size and cationic exchange capacity (CTC). From the sorption curves of 60Co and 137Cs, obtained experimentally in the laboratory, were estimated preliminary values of Kd at equilibrium, for these radionuclides in order of magnitude of 102

  19. Sorption of {sup 60}Co and {sup 137}Cs in sediments at Piraquara de Fora, Angra dos Reis, RJ, Brazil; Sorcao de {sup 60}Co e {sup 137}Cs em sedimentos do Saco de Piraquara de Fora - Angra dos Reis

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Franciane M.; Martins, Nadia S.F.; Lauria, Dejanira D., E-mail: francian@ird.gov.br, E-mail: nadia@ird.gov.br, E-mail: dejanira@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Ferreira, Ingryd M., E-mail: ingrydmarques@hotmail.com [Instituto Federal do Rio de Janeiro (IFRJ), RJ (Brazil); Azevedo, Izabella M.A.P., E-mail: izabella_azevedo@id.uff.br [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

    2013-07-01

    In this study, sediment of Piraquara de Fora, located near the launch area of the effluents of the Central Nuclear Almirante Alvaro Alberto - CNAAA Nuclear Power Plants, were collected. It were determined the parameters particle size and cationic exchange capacity (CTC). From the sorption curves of {sup 60}Co and {sup 137}Cs, obtained experimentally in the laboratory, were estimated preliminary values of Kd at equilibrium, for these radionuclides in order of magnitude of 10{sup 2}.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    Science.gov (United States)

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

    2011-01-01

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

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

    Directory of Open Access Journals (Sweden)

    David R Nagarkatti-Gude

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    Directory of Open Access Journals (Sweden)

    H. Kaeriyama

    2013-06-01

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

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

    International Nuclear Information System (INIS)

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

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

    CERN Document Server

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

    2016-01-01

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

  11. 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

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

    International Nuclear Information System (INIS)

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

  13. 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)

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

    International Nuclear Information System (INIS)

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

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

    Czech Academy of Sciences Publication Activity Database

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2015-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-12-07

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    Directory of Open Access Journals (Sweden)

    Kumar Shyamesh

    2012-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-12-31

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

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

    OpenAIRE

    Rodríguez Moya, Rafael

    2007-01-01

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

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

    Directory of Open Access Journals (Sweden)

    J. Kameník

    2013-03-01

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

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

    Directory of Open Access Journals (Sweden)

    J. Kameník

    2013-09-01

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

  6. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-02-01

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

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

    Directory of Open Access Journals (Sweden)

    Antonio Torres-Valle

    2012-05-01

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

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

    Directory of Open Access Journals (Sweden)

    Igor Sokolov

    2014-09-01

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

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

    Science.gov (United States)

    Sokolov, Igor M; Kavanaugh, David H

    2014-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

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

    Science.gov (United States)

    Lee, Jae-Seung; Regatte, Ravinder R; Jerschow, Alexej

    2008-12-14

    Optimal control theory is applied for enhancing the intensity of the central peak of a spin 3/2 signal in the presence of a residual quadrupolar coupling. While a maximum enhancement is always possible in the regime omega(rf) control and test these with (23)Na NMR in this regime. In addition to enhancing the intensity of the central transition signal, the satellite peaks can be effectively suppressed, which is a useful feature for the implementation in (23)Na imaging sequences. PMID:19071931

  14. Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde; Metodologia de la gestion del envejecimiento en estructuras, sistemas y componentes de una central nuclear y su aplicacion a un programa piloto en Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Fernandez S, G. [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Dos Bocas, 54270 Veracruz (Mexico)], e-mail: gfdezs@cfe.gob.mx

    2009-10-15

    From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

  15. Procedures and techniques for monitoring the radiation detection, signalization and alarm systems in the centralized ambience monitoring systems of the basic nuclear facilities of the CEN Saclay

    International Nuclear Information System (INIS)

    After referring to the regulations governing the 'systematic ambience monitoring' in the basic nuclear facilities, the main radiation detection, signalization and alarm devices existing at present in these facilities of the Saclay Nuclear Study Centre are described. The analysis of the operating defects of the measuring channels and detection possibilities leads to the anomalies being classified in two separate groups: the anomalies of the logical 'all or nothing' type of which all the possible origins are integrated into a so-called 'continuity' line and the evolutive anomalies of various origins corresponding to poor functioning extending possibly to a complete absence of signal. The techniques for testing the detection devices of the radiation monitoring board set up in the 'Departement de Rayonnements' at the Saclay Nuclear Study Centre are also described

  16. Practical training in the operation of nuclear power plants with Interactive Graphic Simulator of Zorita; Formacion practica en la operacion de centrales nucleares con el Simulador Grafico Interactivo de Zorita

    Energy Technology Data Exchange (ETDEWEB)

    Cuervo, D.; Garcia-Herranz, N.; Garcia, S.; Davila, R.; Ahnert, C.; Aragones, J. M.; Cabellos, O.; Gallego, E.; Lorente, A.; Minguez, E.; Rebollo, L.; Blanco, J.

    2010-07-01

    In April 2008 a collaboration agreement was signed between Gas Natural Union Fenosa and the Universad Politecnica de Madrid for the creation of the Aula Jose Cabrera dedicated to train professionals in the field of nuclear technology. The Classroom located in the Department of Nuclear Engineering, has been equipped with the Interactive Graphic Simulator of Zorita (SGIZ). The use of the simulator intended to improve the quality of teaching in the area of Nuclear Engineering. It integrates in the teachings of Industrial Engineering degree and the Master of Nuclear Science and Technology. Different manuals are under preparation to make it a suitable tool for teaching purpose. These manuals will guide the student so that learning takes place both through the guidance of the teacher as independently. (Author) 3 refs.

  17. Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at $\\sqrt{s_{NN}}$ = 2.76 TeV

    CERN Document Server

    Adam, Jaroslav; Aggarwal, Madan Mohan; Aglieri Rinella, Gianluca; Agnello, Michelangelo; Agrawal, Neelima; Ahammed, Zubayer; Ahn, Sang Un; Aimo, Ilaria; Aiola, Salvatore; Ajaz, Muhammad; Akindinov, Alexander; Alam, Sk Noor; Aleksandrov, Dmitry; Alessandro, Bruno; Alexandre, Didier; Alfaro Molina, Jose Ruben; Alici, Andrea; Alkin, Anton; Millan Almaraz, Jesus Roberto; Alme, Johan; Alt, Torsten; Altinpinar, Sedat; Altsybeev, Igor; Alves Garcia Prado, Caio; Andrei, Cristian; Andronic, Anton; Anguelov, Venelin; Anielski, Jonas; Anticic, Tome; Antinori, Federico; Antonioli, Pietro; Aphecetche, Laurent Bernard; Appelshaeuser, Harald; Arcelli, Silvia; Armesto Perez, Nestor; Arnaldi, Roberta; Arsene, Ionut Cristian; Arslandok, Mesut; Audurier, Benjamin; Augustinus, Andre; Averbeck, Ralf Peter; Azmi, Mohd Danish; Bach, Matthias Jakob; Badala, Angela; Baek, Yong Wook; Bagnasco, Stefano; Bailhache, Raphaelle Marie; Bala, Renu; Baldisseri, Alberto; Baltasar Dos Santos Pedrosa, Fernando; Baral, Rama Chandra; Barbano, Anastasia Maria; Barbera, Roberto; Barile, Francesco; Barnafoldi, Gergely Gabor; Barnby, Lee Stuart; Ramillien Barret, Valerie; Bartalini, Paolo; Barth, Klaus; Bartke, Jerzy Gustaw; Bartsch, Esther; Basile, Maurizio; Bastid, Nicole; Basu, Sumit; Bathen, Bastian; Batigne, Guillaume; Batista Camejo, Arianna; Batyunya, Boris; Batzing, Paul Christoph; Bearden, Ian Gardner; Beck, Hans; Bedda, Cristina; Behera, Nirbhay Kumar; Belikov, Iouri; Bellini, Francesca; Bello Martinez, Hector; Bellwied, Rene; Belmont Iii, Ronald John; Belmont Moreno, Ernesto; Belyaev, Vladimir; Bencedi, Gyula; Beole, Stefania; Berceanu, Ionela; Bercuci, Alexandru; Berdnikov, Yaroslav; Berenyi, Daniel; Bertens, Redmer Alexander; Berzano, Dario; Betev, Latchezar; Bhasin, Anju; Bhat, Inayat Rasool; Bhati, Ashok Kumar; Bhattacharjee, Buddhadeb; Bhom, Jihyun; Bianchi, Livio; Bianchi, Nicola; Bianchin, Chiara; Bielcik, Jaroslav; Bielcikova, Jana; Bilandzic, Ante; Biswas, Rathijit; Biswas, Saikat; Bjelogrlic, Sandro; Blair, Justin Thomas; Blanco, Fernando; Blau, Dmitry; Blume, Christoph; Bock, Friederike; Bogdanov, Alexey; Boggild, Hans; Boldizsar, Laszlo; Bombara, Marek; Book, Julian Heinz; Borel, Herve; Borissov, Alexander; Borri, Marcello; Bossu, Francesco; Botta, Elena; Boettger, Stefan; Braun-Munzinger, Peter; Bregant, Marco; Breitner, Timo Gunther; Broker, Theo Alexander; Browning, Tyler Allen; Broz, Michal; Brucken, Erik Jens; Bruna, Elena; Bruno, Giuseppe Eugenio; Budnikov, Dmitry; Buesching, Henner; Bufalino, Stefania; Buncic, Predrag; Busch, Oliver; Buthelezi, Edith Zinhle; Bashir Butt, Jamila; Buxton, Jesse Thomas; Caffarri, Davide; Cai, Xu; Caines, Helen Louise; Calero Diaz, Liliet; Caliva, Alberto; Calvo Villar, Ernesto; Camerini, Paolo; Carena, Francesco; Carena, Wisla; Carnesecchi, Francesca; Castillo Castellanos, Javier Ernesto; Castro, Andrew John; Casula, Ester Anna Rita; Cavicchioli, Costanza; Ceballos Sanchez, Cesar; Cepila, Jan; Cerello, Piergiorgio; Cerkala, Jakub; Chang, Beomsu; Chapeland, Sylvain; Chartier, Marielle; Charvet, Jean-Luc Fernand; Chattopadhyay, Subhasis; Chattopadhyay, Sukalyan; Chelnokov, Volodymyr; Cherney, Michael Gerard; Cheshkov, Cvetan Valeriev; Cheynis, Brigitte; Chibante Barroso, Vasco Miguel; Dobrigkeit Chinellato, David; Chochula, Peter; Choi, Kyungeon; Chojnacki, Marek; Choudhury, Subikash; Christakoglou, Panagiotis; Christensen, Christian Holm; Christiansen, Peter; Chujo, Tatsuya; Chung, Suh-Urk; Zhang, Chunhui; Cicalo, Corrado; Cifarelli, Luisa; Cindolo, Federico; Cleymans, Jean Willy Andre; Colamaria, Fabio Filippo; Colella, Domenico; Collu, Alberto; Colocci, Manuel; Conesa Balbastre, Gustavo; Conesa Del Valle, Zaida; Connors, Megan Elizabeth; Contreras Nuno, Jesus Guillermo; Cormier, Thomas Michael; Corrales Morales, Yasser; Cortes Maldonado, Ismael; Cortese, Pietro; Cosentino, Mauro Rogerio; Costa, Filippo; Crochet, Philippe; Cruz Albino, Rigoberto; Cuautle Flores, Eleazar; Cunqueiro Mendez, Leticia; Dahms, Torsten; Dainese, Andrea; Danu, Andrea; Das, Debasish; Das, Indranil; Das, Supriya; Dash, Ajay Kumar; Dash, Sadhana; De, Sudipan; De Caro, Annalisa; De Cataldo, Giacinto; De Cuveland, Jan; De Falco, Alessandro; De Gruttola, Daniele; De Marco, Nora; De Pasquale, Salvatore; Deisting, Alexander; Deloff, Andrzej; Denes, Ervin Sandor; D'Erasmo, Ginevra; Di Bari, Domenico; Di Mauro, Antonio; Di Nezza, Pasquale; Diaz Corchero, Miguel Angel; Dietel, Thomas; Dillenseger, Pascal; Divia, Roberto; Djuvsland, Oeystein; Dobrin, Alexandru Florin; Dobrowolski, Tadeusz Antoni; Domenicis Gimenez, Diogenes; Donigus, Benjamin; Dordic, Olja; Drozhzhova, Tatiana; Dubey, Anand Kumar; Dubla, Andrea; Ducroux, Laurent; Dupieux, Pascal; Ehlers Iii, Raymond James; Elia, Domenico; Engel, Heiko; Erazmus, Barbara Ewa; Erdemir, Irem; Erhardt, Filip; Eschweiler, Dominic; Espagnon, Bruno; Estienne, Magali Danielle; Esumi, Shinichi; Eum, Jongsik; Evans, David; Evdokimov, Sergey; Eyyubova, Gyulnara; Fabbietti, Laura; Fabris, Daniela; Faivre, Julien; Fantoni, Alessandra; Fasel, Markus; Feldkamp, Linus; Felea, Daniel; Feliciello, Alessandro; Feofilov, Grigorii; Ferencei, Jozef; Fernandez Tellez, Arturo; Gonzalez Ferreiro, Elena; Ferretti, Alessandro; Festanti, Andrea; Feuillard, Victor Jose Gaston; Figiel, Jan; Araujo Silva Figueredo, Marcel; Filchagin, Sergey; Finogeev, Dmitry; Fiore, Enrichetta Maria; Fleck, Martin Gabriel; Floris, Michele; Foertsch, Siegfried Valentin; Foka, Panagiota; Fokin, Sergey; Fragiacomo, Enrico; Francescon, Andrea; Frankenfeld, Ulrich Michael; Fuchs, Ulrich; Furget, Christophe; Furs, Artur; Fusco Girard, Mario; Gaardhoeje, Jens Joergen; Gagliardi, Martino; Gago Medina, Alberto Martin; Gallio, Mauro; Gangadharan, Dhevan Raja; Ganoti, Paraskevi; Gao, Chaosong; Garabatos Cuadrado, Jose; Garcia-Solis, Edmundo Javier; Gargiulo, Corrado; Gasik, Piotr Jan; Germain, Marie; Gheata, Andrei George; Gheata, Mihaela; Ghosh, Premomoy; Ghosh, Sanjay Kumar; Gianotti, Paola; Giubellino, Paolo; Giubilato, Piero; Gladysz-Dziadus, Ewa; Glassel, Peter; Gomez Coral, Diego Mauricio; Gomez Ramirez, Andres; Gonzalez Zamora, Pedro; Gorbunov, Sergey; Gorlich, Lidia Maria; Gotovac, Sven; Grabski, Varlen; Graczykowski, Lukasz Kamil; Graham, Katie Leanne; Grelli, Alessandro; Grigoras, Alina Gabriela; Grigoras, Costin; Grigoryev, Vladislav; Grigoryan, Ara; Grigoryan, Smbat; Grynyov, Borys; Grion, Nevio; Grosse-Oetringhaus, Jan Fiete; Grossiord, Jean-Yves; Grosso, Raffaele; Guber, Fedor; Guernane, Rachid; Guerzoni, Barbara; Gulbrandsen, Kristjan Herlache; Gulkanyan, Hrant; Gunji, Taku; Gupta, Anik; Gupta, Ramni; Haake, Rudiger; Haaland, Oystein Senneset; Hadjidakis, Cynthia Marie; Haiduc, Maria; Hamagaki, Hideki; Hamar, Gergoe; Hansen, Alexander; Harris, John William; Hartmann, Helvi; Harton, Austin Vincent; Hatzifotiadou, Despina; Hayashi, Shinichi; Heckel, Stefan Thomas; Heide, Markus Ansgar; Helstrup, Haavard; Herghelegiu, Andrei Ionut; Herrera Corral, Gerardo Antonio; Hess, Benjamin Andreas; Hetland, Kristin Fanebust; Hilden, Timo Eero; Hillemanns, Hartmut; Hippolyte, Boris; Hosokawa, Ritsuya; Hristov, Peter Zahariev; Huang, Meidana; Humanic, Thomas; Hussain, Nur; Hussain, Tahir; Hutter, Dirk; Hwang, Dae Sung; Ilkaev, Radiy; Ilkiv, Iryna; Inaba, Motoi; Ippolitov, Mikhail; Irfan, Muhammad; Ivanov, Marian; Ivanov, Vladimir; Izucheev, Vladimir; Jacobs, Peter Martin; Jadlovska, Slavka; Jahnke, Cristiane; Jang, Haeng Jin; Janik, Malgorzata Anna; Pahula Hewage, Sandun; Jena, Chitrasen; Jena, Satyajit; Jimenez Bustamante, Raul Tonatiuh; Jones, Peter Graham; Jung, Hyungtaik; Jusko, Anton; Kalinak, Peter; Kalweit, Alexander Philipp; Kamin, Jason Adrian; Kang, Ju Hwan; Kaplin, Vladimir; Kar, Somnath; Karasu Uysal, Ayben; Karavichev, Oleg; Karavicheva, Tatiana; Karayan, Lilit; Karpechev, Evgeny; Kebschull, Udo Wolfgang; Keidel, Ralf; Keijdener, Darius Laurens; Keil, Markus; Khan, Kamal; Khan, Mohammed Mohisin; Khan, Palash; Khan, Shuaib Ahmad; Khanzadeev, Alexei; Kharlov, Yury; Kileng, Bjarte; Kim, Beomkyu; Kim, Do Won; Kim, Dong Jo; Kim, Hyeonjoong; Kim, Jinsook; Kim, Mimae; Kim, Minwoo; Kim, Se Yong; Kim, Taesoo; Kirsch, Stefan; Kisel, Ivan; Kiselev, Sergey; Kisiel, Adam Ryszard; Kiss, Gabor; Klay, Jennifer Lynn; Klein, Carsten; Klein, Jochen; Klein-Boesing, Christian; Kluge, Alexander; Knichel, Michael Linus; Knospe, Anders Garritt; Kobayashi, Taiyo; Kobdaj, Chinorat; Kofarago, Monika; Kollegger, Thorsten; Kolozhvari, Anatoly; Kondratev, Valerii; Kondratyeva, Natalia; Kondratyuk, Evgeny; Konevskikh, Artem; Kopcik, Michal; Kour, Mandeep; Kouzinopoulos, Charalampos; Kovalenko, Oleksandr; Kovalenko, Vladimir; Kowalski, Marek; Koyithatta Meethaleveedu, Greeshma; Kral, Jiri; Kralik, Ivan; Kravcakova, Adela; Krelina, Michal; Kretz, Matthias; Krivda, Marian; Krizek, Filip; Kryshen, Evgeny; Krzewicki, Mikolaj; Kubera, Andrew Michael; Kucera, Vit; Kugathasan, Thanushan; Kuhn, Christian Claude; Kuijer, Paulus Gerardus; Kulakov, Igor; Kumar, Ajay; Kumar, Jitendra; Lokesh, Kumar; Kurashvili, Podist; Kurepin, Alexander; Kurepin, Alexey; Kuryakin, Alexey; Kushpil, Svetlana; Kweon, Min Jung; Kwon, Youngil; La Pointe, Sarah Louise; La Rocca, Paola; Lagana Fernandes, Caio; Lakomov, Igor; Langoy, Rune; Lara Martinez, Camilo Ernesto; Lardeux, Antoine Xavier; Lattuca, Alessandra; Laudi, Elisa; Lea, Ramona; Leardini, Lucia; Lee, Graham Richard; Lee, Seongjoo; Legrand, Iosif; Lehas, Fatiha; Lemmon, Roy Crawford; Lenti, Vito; Leogrande, Emilia; Leon Monzon, Ildefonso; Leoncino, Marco; Levai, Peter; Li, Shuang; Li, Xiaomei; Lien, Jorgen Andre; Lietava, Roman; Lindal, Svein; Lindenstruth, Volker; Lippmann, Christian; Lisa, Michael Annan; Ljunggren, Hans Martin; Lodato, Davide Francesco; Lonne, Per-Ivar; Loginov, Vitaly; Loizides, Constantinos; Lopez, Xavier Bernard; Lopez Torres, Ernesto; Lowe, Andrew John; Luettig, Philipp Johannes; Lunardon, Marcello; Luparello, Grazia; Ferreira Natal Da Luz, Pedro Hugo; Maevskaya, Alla; Mager, Magnus; Mahajan, Sanjay; Mahmood, Sohail Musa; Maire, Antonin; Majka, Richard Daniel; Malaev, Mikhail; Maldonado Cervantes, Ivonne Alicia; Malinina, Liudmila; Mal'Kevich, Dmitry; Malzacher, Peter; Mamonov, Alexander; Manko, Vladislav; Manso, Franck; Manzari, Vito; Marchisone, Massimiliano; Mares, Jiri; Margagliotti, Giacomo Vito; Margotti, Anselmo; Margutti, Jacopo; Marin, Ana Maria; Markert, Christina; Marquard, Marco; Martin, Nicole Alice; Martin Blanco, Javier; Martinengo, Paolo; Martinez Hernandez, Mario Ivan; Martinez-Garcia, Gines; Martinez Pedreira, Miguel; Martynov, Yevgen; Mas, Alexis Jean-Michel; Masciocchi, Silvia; Masera, Massimo; Masoni, Alberto; Massacrier, Laure Marie; Mastroserio, Annalisa; Masui, Hiroshi; Matyja, Adam Tomasz; Mayer, Christoph; Mazer, Joel Anthony; Mazzoni, Alessandra Maria; Mcdonald, Daniel; Meddi, Franco; Melikyan, Yuri; Menchaca-Rocha, Arturo Alejandro; Meninno, Elisa; Mercado-Perez, Jorge; Meres, Michal; Miake, Yasuo; Mieskolainen, Matti Mikael; Mikhaylov, Konstantin; Milano, Leonardo; Milosevic, Jovan; Minervini, Lazzaro Manlio; Mischke, Andre; Mishra, Aditya Nath; Miskowiec, Dariusz Czeslaw; Mitra, Jubin; Mitu, Ciprian Mihai; Mohammadi, Naghmeh; Mohanty, Bedangadas; Molnar, Levente; Montano Zetina, Luis Manuel; Montes Prado, Esther; Morando, Maurizio; Moreira De Godoy, Denise Aparecida; Moretto, Sandra; Morreale, Astrid; Morsch, Andreas; Muccifora, Valeria; Mudnic, Eugen; Muhlheim, Daniel Michael; Muhuri, Sanjib; Mukherjee, Maitreyee; Mulligan, James Declan; Gameiro Munhoz, Marcelo; Murray, Sean; Musa, Luciano; Musinsky, Jan; Nandi, Basanta Kumar; Nania, Rosario; Nappi, Eugenio; Naru, Muhammad Umair; Nattrass, Christine; Nayak, Kishora; Nayak, Tapan Kumar; Nazarenko, Sergey; Nedosekin, Alexander; Nellen, Lukas; Ng, Fabian; Nicassio, Maria; Niculescu, Mihai; Niedziela, Jeremi; Nielsen, Borge Svane; Nikolaev, Sergey; Nikulin, Sergey; Nikulin, Vladimir; Noferini, Francesco; Nomokonov, Petr; Nooren, Gerardus; Cabanillas Noris, Juan Carlos; Norman, Jaime; Nyanin, Alexander; Nystrand, Joakim Ingemar; Oeschler, Helmut Oskar; Oh, Saehanseul; Oh, Sun Kun; Ohlson, Alice Elisabeth; Okatan, Ali; Okubo, Tsubasa; Olah, Laszlo; Oleniacz, Janusz; Oliveira Da Silva, Antonio Carlos; Oliver, Michael Henry; Onderwaater, Jacobus; Oppedisano, Chiara; Orava, Risto; Ortiz Velasquez, Antonio; Oskarsson, Anders Nils Erik; Otwinowski, Jacek Tomasz; Oyama, Ken; Ozdemir, Mahmut; Pachmayer, Yvonne Chiara; Pagano, Paola; Paic, Guy; Pajares Vales, Carlos; Pal, Susanta Kumar; Pan, Jinjin; Pandey, Ashutosh Kumar; Pant, Divyash; Papcun, Peter; Papikyan, Vardanush; Pappalardo, Giuseppe; Pareek, Pooja; Park, Woojin; Parmar, Sonia; Passfeld, Annika; Paticchio, Vincenzo; Patra, Rajendra Nath; Paul, Biswarup; Peitzmann, Thomas; Pereira Da Costa, Hugo Denis Antonio; Pereira De Oliveira Filho, Elienos; Peresunko, Dmitry Yurevich; Perez Lara, Carlos Eugenio; Perez Lezama, Edgar; Peskov, Vladimir; Pestov, Yury; Petracek, Vojtech; Petrov, Viacheslav; Petrovici, Mihai; Petta, Catia; Piano, Stefano; Pikna, Miroslav; Pillot, Philippe; Pinazza, Ombretta; Pinsky, Lawrence; Piyarathna, Danthasinghe; Ploskon, Mateusz Andrzej; Planinic, Mirko; Pluta, Jan Marian; Pochybova, Sona; Podesta Lerma, Pedro Luis Manuel; Poghosyan, Martin; Polishchuk, Boris; Poljak, Nikola; Poonsawat, Wanchaloem; Pop, Amalia; Porteboeuf, Sarah Julie; Porter, R Jefferson; Pospisil, Jan; Prasad, Sidharth Kumar; Preghenella, Roberto; Prino, Francesco; Pruneau, Claude Andre; Pshenichnov, Igor; Puccio, Maximiliano; Puddu, Giovanna; Pujahari, Prabhat Ranjan; Punin, Valery; Putschke, Jorn Henning; Qvigstad, Henrik; Rachevski, Alexandre; Raha, Sibaji; Rajput, Sonia; Rak, Jan; Rakotozafindrabe, Andry Malala; Ramello, Luciano; Raniwala, Rashmi; Raniwala, Sudhir; Rasanen, Sami Sakari; Rascanu, Bogdan Theodor; Rathee, Deepika; Read, Kenneth Francis; Real, Jean-Sebastien; Redlich, Krzysztof; Reed, Rosi Jan; Rehman, Attiq Ur; Reichelt, Patrick Simon; Reidt, Felix; Ren, Xiaowen; Renfordt, Rainer Arno Ernst; Reolon, Anna Rita; Reshetin, Andrey; Rettig, Felix Vincenz; Revol, Jean-Pierre; Reygers, Klaus Johannes; Riabov, Viktor; Ricci, Renato Angelo; Richert, Tuva Ora Herenui; Richter, Matthias Rudolph; Riedler, Petra; Riegler, Werner; Riggi, Francesco; Ristea, Catalin-Lucian; Rivetti, Angelo; Rocco, Elena; Rodriguez Cahuantzi, Mario; Rodriguez Manso, Alis; Roeed, Ketil; Rogochaya, Elena; Rohr, David Michael; Roehrich, Dieter; Romita, Rosa; Ronchetti, Federico; Ronflette, Lucile; Rosnet, Philippe; Rossi, Andrea; Roukoutakis, Filimon; Roy, Ankhi; Roy, Christelle Sophie; Roy, Pradip Kumar; Rubio Montero, Antonio Juan; Rui, Rinaldo; Russo, Riccardo; Ryabinkin, Evgeny; Ryabov, Yury; Rybicki, Andrzej; Sadovskiy, Sergey; Safarik, Karel; Sahlmuller, Baldo; Sahoo, Pragati; Sahoo, Raghunath; Sahoo, Sarita; Sahu, Pradip Kumar; Saini, Jogender; Sakai, Shingo; Saleh, Mohammad Ahmad; Salgado Lopez, Carlos Alberto; Salzwedel, Jai Samuel Nielsen; Sambyal, Sanjeev Singh; Samsonov, Vladimir; Sanchez Castro, Xitzel; Sandor, Ladislav; Sandoval, Andres; Sano, Masato; Sarkar, Debojit; Scapparone, Eugenio; Scarlassara, Fernando; Scharenberg, Rolf Paul; Schiaua, Claudiu Cornel; Schicker, Rainer Martin; Schmidt, Christian Joachim; Schmidt, Hans Rudolf; Schuchmann, Simone; Schukraft, Jurgen; Schulc, Martin; Schuster, Tim Robin; Schutz, Yves Roland; Schwarz, Kilian Eberhard; Schweda, Kai Oliver; Scioli, Gilda; Scomparin, Enrico; Scott, Rebecca Michelle; Seger, Janet Elizabeth; Sekiguchi, Yuko; Sekihata, Daiki; Selyuzhenkov, Ilya; Senosi, Kgotlaesele; Seo, Jeewon; Serradilla Rodriguez, Eulogio; Sevcenco, Adrian; Shabanov, Arseniy; Shabetai, Alexandre; Shadura, Oksana; Shahoyan, Ruben; Shangaraev, Artem; Sharma, Ankita; Sharma, Mona; Sharma, Monika; Sharma, Natasha; Shigaki, Kenta; Shtejer Diaz, Katherin; Sibiryak, Yury; Siddhanta, Sabyasachi; Sielewicz, Krzysztof Marek; Siemiarczuk, Teodor; Silvermyr, David Olle Rickard; Silvestre, Catherine Micaela; Simatovic, Goran; Simonetti, Giuseppe; Singaraju, Rama Narayana; Singh, Ranbir; Singha, Subhash; Singhal, Vikas; Sinha, Bikash; Sarkar - Sinha, Tinku; Sitar, Branislav; Sitta, Mario; Skaali, Bernhard; Slupecki, Maciej; Smirnov, Nikolai; Snellings, Raimond; Snellman, Tomas Wilhelm; Soegaard, Carsten; Soltz, Ron Ariel; Song, Jihye; Song, Myunggeun; Song, Zixuan; Soramel, Francesca; Sorensen, Soren Pontoppidan; Spacek, Michal; Spiriti, Eleuterio; Sputowska, Iwona Anna; Spyropoulou-Stassinaki, Martha; Srivastava, Brijesh Kumar; Stachel, Johanna; Stan, Ionel; Stefanek, Grzegorz; Steinpreis, Matthew Donald; Stenlund, Evert Anders; Steyn, Gideon Francois; Stiller, Johannes Hendrik; Stocco, Diego; Strmen, Peter; Alarcon Do Passo Suaide, Alexandre; Sugitate, Toru; Suire, Christophe Pierre; Suleymanov, Mais Kazim Oglu; Sultanov, Rishat; Sumbera, Michal; Symons, Timothy; Szabo, Alexander; Szanto De Toledo, Alejandro; Szarka, Imrich; Szczepankiewicz, Adam; Szymanski, Maciej Pawel; Takahashi, Jun; Tambave, Ganesh Jagannath; Tanaka, Naoto; Tangaro, Marco-Antonio; Tapia Takaki, Daniel Jesus; Tarantola Peloni, Attilio; Tarhini, Mohamad; Tariq, Mohammad; Tarzila, Madalina-Gabriela; Tauro, Arturo; Tejeda Munoz, Guillermo; Telesca, Adriana; Terasaki, Kohei; Terrevoli, Cristina; Teyssier, Boris; Thaeder, Jochen Mathias; Thomas, Deepa; Tieulent, Raphael Noel; Timmins, Anthony Robert; Toia, Alberica; Trogolo, Stefano; Trubnikov, Victor; Trzaska, Wladyslaw Henryk; Tsuji, Tomoya; Tumkin, Alexandr; Turrisi, Rosario; Tveter, Trine Spedstad; Ullaland, Kjetil; Uras, Antonio; Usai, Gianluca; Utrobicic, Antonija; Vajzer, Michal; Vala, Martin; Valencia Palomo, Lizardo; Vallero, Sara; Van Der Maarel, Jasper; Van Hoorne, Jacobus Willem; Van Leeuwen, Marco; Vanat, Tomas; Vande Vyvre, Pierre; Varga, Dezso; Vargas Trevino, Aurora Diozcora; Vargyas, Marton; Varma, Raghava; Vasileiou, Maria; Vasiliev, Andrey; Vauthier, Astrid; Vechernin, Vladimir; Veen, Annelies Marianne; Veldhoen, Misha; Velure, Arild; Venaruzzo, Massimo; Vercellin, Ermanno; Vergara Limon, Sergio; Vernet, Renaud; Verweij, Marta; Vickovic, Linda; Viesti, Giuseppe; Viinikainen, Jussi Samuli; Vilakazi, Zabulon; Villalobos Baillie, Orlando; Vinogradov, Alexander; Vinogradov, Leonid; Vinogradov, Yury; Virgili, Tiziano; Vislavicius, Vytautas; Viyogi, Yogendra; Vodopyanov, Alexander; Volkl, Martin Andreas; Voloshin, Kirill; Voloshin, Sergey; Volpe, Giacomo; Von Haller, Barthelemy; Vorobyev, Ivan; Vranic, Danilo; Vrlakova, Janka; Vulpescu, Bogdan; Vyushin, Alexey; Wagner, Boris; Wagner, Jan; Wang, Hongkai; Wang, Mengliang; Wang, Yifei; Watanabe, Daisuke; Watanabe, Yosuke; Weber, Michael; Weber, Steffen Georg; Wessels, Johannes Peter; Westerhoff, Uwe; Wiechula, Jens; Wikne, Jon; Wilde, Martin Rudolf; Wilk, Grzegorz Andrzej; Wilkinson, Jeremy John; Williams, Crispin; Windelband, Bernd Stefan; Winn, Michael Andreas; Yaldo, Chris G; Yang, Hongyan; Yang, Ping; Yano, Satoshi; Yin, Zhongbao; Yokoyama, Hiroki; Yoo, In-Kwon; Yurchenko, Volodymyr; Yushmanov, Igor; Zaborowska, Anna; Zaccolo, Valentina; Zaman, Ali; Zampolli, Chiara; Correia Zanoli, Henrique Jose; Zaporozhets, Sergey; Zardoshti, Nima; Zarochentsev, Andrey; Zavada, Petr; Zavyalov, Nikolay; Zbroszczyk, Hanna Paulina; Zgura, Sorin Ion; Zhalov, Mikhail; Zhang, Haitao; Zhang, Xiaoming; Zhang, Yonghong; Zhao, Chengxin; Zhigareva, Natalia; Zhou, Daicui; Zhou, You; Zhou, Zhuo; Zhu, Hongsheng; Zhu, Jianhui; Zhu, Xiangrong; Zichichi, Antonino; Zimmermann, Alice; Zimmermann, Markus Bernhard; Zinovjev, Gennady; Zyzak, Maksym

    2016-01-01

    Transverse momentum ($p_{\\rm{T}}$) spectra of pions, kaons, and protons up to $p_{\\rm{T}} = 20$ GeV/$c$ have been measured in Pb-Pb collisions at $\\sqrt{s_{\\rm NN}} = 2.76$ TeV using the ALICE detector for six different centrality classes covering 0-80%. The proton-to-pion and the kaon-to-pion ratios both show a distinct peak at $p_{\\rm{T}} \\approx 3$ GeV/$c$ in central Pb-Pb collisions that decreases towards more peripheral collisions. For $p_{\\rm{T}} > 10$ GeV/$c$, the nuclear modification factor is found to be the same for all three particle species in each centrality interval within systematic uncertainties of 10-20%. This suggests there is no direct interplay between the energy loss in the medium and the particle species composition in the hard core of the quenched jet. For $p_{\\rm{T}} < 10$ GeV/$c$, the data provide important constraints for models aimed at describing the transition from soft to hard physics.

  18. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

  19. Life time of nuclear power plants and new types of reactors; La duree de vie des centrales nucleaires et les nouveaux types de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

  20. Desarrollo de una metodología de simulación de secuencias en accidente en centrales nucleares de agua ligera considerando actuaciones del operador

    OpenAIRE

    Expósito Lorenzo, Antonio

    2006-01-01

    This thesis presents the work carried out to develop a simulation system for nuclear power plants, denominated TRETA / COPMA-III integrated simulator, which allows the simulation of the thermalhydraulic processes that take place in this type of facilities, in normal operation and emergency operation, as well as the control room crew actions related with the management of the emergency situations. The simulation of the thermalhydraulic processes is carried out by means of the TR...

  1. Preparation of the Improved Technical Specifications of Nuclear Almaraz, Asco and Vandellos; Procedimiento de elaboracion de las Especificaciones Tecnicas Mejoradas de las Centrales de Almaraz Asco y Vandellos

    Energy Technology Data Exchange (ETDEWEB)

    Fuente, I.; Mirallas, F.; Garcia, M. D.

    2012-07-01

    In 2010 the Nuclear Almaraz, Asco and Vandellos agreed with the CSN start the transition project to the Improved Plant Technical Specifications (IPTSs), with reference the Rev. 3.1 of NUREG-1431. In April 2012 has been published the Rev. 4.0 of NUREG and have decided to adapt the IPTSs to the content of this new revision. The project for the three plants is developed in parallel, which allows to optimize the process.

  2. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production; UPVAPOR: Aplicacion informatica para el analisis de resultados de produccion en Central Nuclear Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-07-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  3. Evolution of Technology Laser Scanner. Implications for use in Nuclear Power and Radioactive Facilities; Evolucion de la Tecnologia Laser Escaner. Implicaciones en uso en Centrales Nucleares e Instalaciones Radioactivas

    Energy Technology Data Exchange (ETDEWEB)

    Sarti Fernandez, F.; Bonet, J.

    2012-07-01

    The main technical factors affecting these teams their actual implementation in nuclear power plants will be analyzed: data acquisition speed, sensitivity, laser power, autonomy, contamination of equipment, radiation effect, etc. In conclusion, the real difference is displayed in the data collection in function of various technologies, embodied in field time, and costs.

  4. Follow-up of the results of the nuclear power plant stress tests and action plan.; Seguimiento de los resultados de las pruebas de resistencia de las centrales nucleares y plan de accion

    Energy Technology Data Exchange (ETDEWEB)

    Mellado Jimenez, I.

    2012-07-01

    The results of the stress tests carried out by the European nuclear power plants in the wake of the Fukushima Daiichi accident, subsequently subjected to peer reviews, have made it possible to identify the measures to be applied to improve safety. Action plans have been put in place to implement these measures within appropriate time frames. (Author)

  5. Nuclear fragmentation in central collisions: Ni + Au from 32 to 90 A*MeV; Fragmentation dans les collisions centrales du systeme Ni + Au de 32 a 90 A MeV

    Energy Technology Data Exchange (ETDEWEB)

    Bellaize, N

    2000-11-03

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

  6. Study of shear wave attenuation field variations in Central Asia region using records of nuclear and chemical explosions at the Semipalatinsk Test Site

    International Nuclear Information System (INIS)

    The temporal variations of amplitude ratio of Lg and Pg, Lg and P waves were studied using the 1964-2000 records of more than 200 underground nuclear and chemical calibration explosions obtained at the Northern Tien Shan TLG station, KURK station (Eastern Kazakhstan), BRVK (Kokchetav Massif), GRM (Southern Tien Shan) located at epicentral distances of 77-1400 km. Variations in this parameter with time are shown to be significantly different for different paths. The spatial-temporal variations of the seismic wave attenuation field are presumably associated with the ascent of juvenile fluids through large deep faults. (author)

  7. Determination of the changes of water storage in an aridisol at the central Bolivian highlands with the help of nuclear techniques

    International Nuclear Information System (INIS)

    The results of this kind of research, the first one conducted in Bolivia with the help of nuclear techniques for three years, allow to demonstrate that the soil classified as ''typical paleargid'' or ''aridisol'' with loam-clay sandy texture, has a very varied water storage until reaching a depth of 76 cm. This strictly depends on the variable rain fall in different seasons and the strong evaporation rate during the cloudless winter at 4000 m of altitude. The growing period of the Andean cultivated plants coincides with the increasing soil water content from September to January and the harvest period with the decrease of water storage from March to May

  8. The deconstruction of EDF nuclear power plants - Information note September 2011; La deconstruction des centrales nucleaires EDF - Note d'information Septembre 2011

    Energy Technology Data Exchange (ETDEWEB)

    Tran, Lionel

    2012-01-10

    As nine nuclear reactors are being deconstructed, this document outlines EDF commitment in this deconstruction, and the fact that this deconstruction is a long process which comprises several phases (stopping the reactor, partial and total dismantling). It presents the CIDEN (Deconstruction and Environment Engineering Centre), an expertise centre specialised in plant deconstruction. It briefly addresses the issue of deconstruction wastes: there are different types of wastes (conventional wastes and wastes with different levels of radioactivity), and different associated storage sites. The document highlights the importance of public, personnel and environment protection for these operations, and evokes the financial issue. Finally, the industrial project ICEDA (packaging and warehousing installation for activated wastes) is presented

  9. Update of foundation design modifications of data cables and piping in nuclear power plants in operation; Actualizacion de modificaciones de sieno de bases de datos de cables y conducciones en centrales nucleares en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Perez Pereira, J.

    2013-07-01

    The scope of this application is the manage the life cycle of cables electrical and pipes of cables in Trillo NPP. The application is integrated in a configuration Control system, so both cables and conduits become elements of configuration and management of life and history associated with the of the relevant modifying documents. The guarantees criteria of physical separation of wires for jobs and for independent networks designed according to the redundancy of the Central System.

  10. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

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

  11. Revision of by-laws about effluents of EdF's nuclear power plants; Revision des arretes de rejets des centrales nucleaires d'EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, {sup 14}C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  12. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs

  13. Analysis of the financial task generated by the construction of a nuclear power plant in Mexico; Analisis de la carga financiera generada por la construccion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, G.; Ramirez, R.; Palacios, J.; Delfin, A., E-mail: gustavo.alonso@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-11-15

    The construction of new nuclear reactors requires of a high investment making them intensive projects in capital and that require as minimum of 5 years for its construction. The financial task that represents for the electric company is of vital importance, since in the case of privates in other countries prevents them of entering in this type of projects if they do not have its Government support. In the case of Mexico, being an electric company integrated vertically can have financing to carry out this investment type. In this study is analyzed the construction viability of new nuclear reactors in Mexico based on the financial task that represents for the Electric Company its construction. (Author)

  14. New technologies of information treatment in the ERP of the Almaraz and Trillo nuclear power plants; Nuevas tecnologias de tratamiento de la informacion en el ERP de las centrales nucleares de Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Lopez-Suevos, C.; Gonzalez Crego, E.

    2013-03-01

    The Almaraz and Trillo Nuclear Power Plants are equipped with an Integrated Operation Management System (SIGE), which covers practically all of their transactional and management needs in all areas, with the exception of some specific engineering and simulation tools. In recent years, applications based on new computer technologies have been developed and integrated into the SIGE, including a Maintenance Dashboard, an Admissions Office ant the use of bar code readers, all of which are described in this article. (Author)

  15. CAGE: A standard design application to nuclear power plants of Cofrentes, Almaraz and Trillo; CAGE: Un diseno estandar de aplicacion a las centrales nucleares de Cofrentes, Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Cubian Martinez, B.; Gomez Gomez, M.; Zornoza Garcia-Andrade, J.; Turrion Lopez, F.; Barrio, M. A. del; Cobos Perabad, A.; Garcia-Serrano, J. L.

    2016-08-01

    Design, engineering, supply, construction, assembly, supervision and quality control, construction management and commissioning of Alternative Emergency Management Centres (CAGES) of nuclear power plants Cofrentes (CNC), Almaraz (CNA) and Trillo (CNT) were awarded in the first half of 2014 to Iberdrola Engineering and Construction (IIC). After obtaining the required building permits issued by municipalities, following the delivery of the corresponding, basic project and execution, in January 2015, began civil works at CNA, CNT and in February of this year in CNC. (Author)

  16. Instruction by virtual reality to operation and security of a nuclear power plant of IV generation; Instruccion por realidad virtual a la operacion y seguridad de una central nuclear de generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Neri O, J. C.; Baltasar M, J.; Valle H, J. [Facultad de Ingenieria, Division de Estudios de Posgrado, Campus Morelos, UNAM, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)], e-mail: neriunam@ieee.org

    2009-10-15

    The purpose of LaNuVi project which is developing in the Engineering Faculty of National Autonomous University of Mexico, to have a virtual laboratory of nuclear reactors as tool of multidisciplinary education at basic and advanced levels in nuclear engineering area, involves training resources in audio visual and interactive form that allow to form a comprehension more realistic of operation of different systems and components. In this work is proposed to use educational resources, as the employees in the U.S. Army and in some centers of advanced education of medicine, where have been come proving concepts like projected reality, increased reality, tele transparency and others that present big benefits to learning-education process. The proposal here is to include the resource knew as serious game based learning. The focal point of stage that is presented is of a nuclear reactor PBMR like desalination and generator of controlled alternating energy and efficient that should put on in operation to allow the subsistence of a community in a desolated region of beginning second quarter of X XI century. For this purpose the designs are initiated and programmed several subsystems that allow the three-dimensional modeling of main components of a PBMR as well as of surrounding facilities. The obtained results and reaches of this design are presented. The product is in tests for a first version and it is hope to achieve a free and integral resource of national distribution for different cultural groups, interested in this type of advanced technology. (Author)

  17. The central repeat domain 1 of Kaposi's sarcoma-associated herpesvirus (KSHV) latency associated-nuclear antigen 1 (LANA1) prevents cis MHC class I peptide presentation

    International Nuclear Information System (INIS)

    KSHV LANA1, a latent protein expressed during chronic infection to maintain a viral genome, inhibits major histocompatibility complex class I (MHC I) peptide presentation in cis as a means of immune evasion. Through deletional cloning, we localized this function to the LANA1 central repeat 1 (CR1) subregion. Other CR subregions retard LANA1 translation and proteasomal processing but do not markedly inhibit LANA1 peptide processing by MHC I. Inhibition of proteasomal processing ablates LANA1 peptide presentation. Direct expression of LANA1 within the endoplasmic reticulum (ER) overcomes CR1 inhibition suggesting that CR1 acts prior to translocation of cytoplasmic peptides into the ER. By physically separating CR1 from other subdomains, we show that LANA1 evades MHC I peptide processing by a mechanism distinct from other herpesviruses including Epstein-Barr virus (EBV). Although LANA1 and EBV EBNA1 are functionally similar, they appear to use different mechanisms to evade host cytotoxic T lymphocyte surveillance.

  18. Monitoring systems online of oil for transformers of nuclear power plants; Sistemas de monitorizacion online del aceite para transformadores de potencia de Centrales

    Energy Technology Data Exchange (ETDEWEB)

    Sarandeses, S.

    2014-07-01

    The nuclear power plants are showing their concern due to the existence of recent failures related to the bulky transformers of power. These transformers are not security, but are important for the production of power as its failure can cause transient on the floor, reactor scram or shooting, that can cause interruptions in the production of energy or might force us to reduce the power of production The analysis of gases dissolved in transformer oil is recognized as a trial key to identify a submerged transformer failure in oil. With this analysis it is not possible to ensure that there is no damage in the transformer, but the probability of risk of this type of failure can be reduced. The industry recommended to equip the new large power transformers with oil online monitoring systems and in some cases also be It recommended its use in existing transformers. (Author)

  19. The sanitary officer: first aid coordinator on EDF nuclear power plant; Le delegue sanitaire: coordonnateur des secouristes en centrale nucleaire a E.D.F

    Energy Technology Data Exchange (ETDEWEB)

    Masson, A

    2000-07-01

    The internal organisation for first aid to the injured in case of an accident on E.D.F. nuclear power plant calls for the immediate assistance of a first aid team, consisting of five workers, under the direction of a principal first aid officer; one of the first aid workers, the sanitary officer who instructs the first aid workers intervention awaiting the arrival of an external medical. When the 'Sanitary on-site Emergency Plan' was up' dated, twenty medical doctors and seventy members of staff from five different sites were questioned as to the function of the sanitary officer. The conclusions revealed a notable difference of training amongst the different sites, and concerning first aid organisation, difference of priority of actions, extent of their participation once the medical team arrives and their participation in case of decontamination treatment. The medical doctors and staff lay a particular stress on importance of defining on a national scale the limits of role and responsibilities of the sanitary officer and establish a more specific training in this field, consequently motivating commitment and professionalism involvement. There is a great difference between the training and coaching of the first aid assistance and fire protection teams. To conclude, we propose that the first aid officer be known as first aid coordinator and the qualification of 'Certificat de Formation aux Premiers Secours en Equipe' in compliance with the current legislation together with a specific nuclear module and they should undergo regular on-site drills. (author)

  20. Sensing remote nuclear spins

    OpenAIRE

    Zhao, Nan; Honert, Jan; Schmid, Berhard; Isoya, Junichi; Markham, Mathew; Twitchen, Daniel; Jelezko, Fedor; Liu, Ren-Bao; Fedder, Helmut; Wrachtrup, Jörg

    2012-01-01

    Sensing single nuclear spins is a central challenge in magnetic resonance based imaging techniques. Although different methods and especially diamond defect based sensing and imaging techniques in principle have shown sufficient sensitivity, signals from single nuclear spins are usually too weak to be distinguished from background noise. Here, we present the detection and identification of remote single C-13 nuclear spins embedded in nuclear spin baths surrounding a single electron spins of a...

  1. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico. Parte 2

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. de L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

  2. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

  3. Regulator process for the authorization of an amendment to the operation license of a nuclear power plant in Mexico; Proceso regulador para la autorizacion de una enmienda a la licencia de operacion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Perez, R.; Espinosa V, J.M.; Salgado, J.R.; Mamani, Y.R. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2005-07-01

    The regulator process by which an authorization is granted from an amendment to the License of Operation of a nuclear power station in Mexico is described. It makes an appointment the effective legal mark, the technical characteristics of the modification, the evaluation process and deposition upon oath of tests and finally the elaboration of the Safety report and the Technical Verdict that is a correspondent for the regulator organism to the Secretary of Energy, the one that in turn is the responsible of granting the amendment the License just as it establishes it the Law. (Author)

  4. Modification and updating of documentation in equipment of panels of control room in nuclear power plant operation; Modificacion y actualizacion de documentacion en aparatos de paneles de sala de control en una central nuclear en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Agudo Montero, L.

    2013-07-01

    The present paper describes a case very unique specific design of interactive 2D-CAD application, that has been developed by Empresarios Agrupados as engineering support to the nuclear power plants, aware of the problem that exists with the documentation of the instruments and devices that are on the panels of Control room, and that only have the documentation generated in its day by the manufacturers of these panels. To this end, an application (application DOPAB) has been developed to help solve the problem of management, design and modification of wiring and wiring devices existing in the Control room control panels.

  5. Experience in training of health personnel for response to radiological and nuclear accidents; Experiencia na capacitacao de profissionais de saude para a resposta a acidentes radiologicos e nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Maurmo, Alexandre M., E-mail: ammaurmo@gmail.com [Fundacao Eletronuclear de Assistencia Medica (CMRI/CTNV/FEAM), Praia Brava, RJ (Brazil). Centro de Medicina das Radiacoes Ionizantes. Centro de Treinamento Prof. Nelson Valverde; Leite, Teresa C.S.B., E-mail: feam@feam-etn.org.br [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Praia Brava, RJ (Brazil). Centro de Informacoes em Radioepidemiologia

    2013-07-01

    Eletronuclear Healthcare Foundation is the Institution responsible for the actions of health response involving ionizing radiation in the area of Nuclear Power Plant Almirante Alvaro Alberto in Angra dos Reis. Because of their specific assignments and references for being in training health manpower in the field of ionizing radiation developed a range of Training Courses for Professionals Area Health to prepare them for Response to Radiological and Nuclear Accidents. Modules are proposed specifically for the professional response of the Technical Level and Higher Level, the level Pre-hospital and hospital. These modules are further divided into specific levels or modules, Basic or Introductory, Intermediate and Advanced. Are applied pretests and post tests to monitor the content of fixing, maintaining a historical series of reviews. Your content is theoretical and practical applications developed in 30 to 48 hours, with simulations (drills) and distribution of educational materials. We already have more than 80 applications training, focusing on internal staff and external to the institution, developing interesting partner with the Armed Forces and Civil Defense. It still maintained a link on the institution seeking access and download over 400 titles on the subject and exchange of information and experiences. For improving the teaching material, the authors launched in 2011 the first manual in Portuguese on the subject with new revised edition in 2013: 'Manual of Medical Actions In Radiological Emergencies'. The results indicate increased knowledge and appropriateness of the themes and the strategy proposed for this activity, demonstrating yet passed that information can be multiplied and meets the growing demand of the country that has hosted and will host international events relevant at QBNRE risk. (author)

  6. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde; Cuestionamientos al aumento de potencia de los reactores de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B., E-mail: salasmarb@yahoo.com.mx [UNAM, Facultad de Ciencias, Departamento de Fisica, Circuito exterior s/n, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2014-08-15

    The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

  7. Economic analysis of extended cycles in the Laguna Verde nuclear power plant; Analisis economico de ciclos de extendidos en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: hermilo@correo.unam.mx

    2004-07-01

    The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

  8. Sampling and description of the resins stockpiles in the Kozloduy Nuclear Power Plant large tanks; Muestreo y caracterizacion de resinas almacenadas en tanques de grandes dimensiones de la Central Nuclear de Kozloduy (Bulgaria)

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Fernandez, L.; Gonzalez Gandal, R.; Herrera, J. A.

    2012-11-01

    The consortium ENSA-Gas Natural Fenosa Engineering has a contract with Kozloduy Nuclear Power Plant (KNPP) for the retrieval and conditioning of the resins, which were generated during the operation of the plant. The project deals with resins characterization for which its necessary to define a proper methodology that fulfills the Bulgarian authorities requirements. Also, it will be included the design, fabrication, supply and installation of the required equipment to carry out the sampling and measurements of the resins, updating the facilities and the specific training of the personnel in order to perform by themselves every activities. This article reflects how the consortium will deal with the management of this damaging project, which involves a wide range of activities, including the management of each implicated are of both KNPP and external organizations. (Author)

  9. Project development: testing of heat exchange of cooling system and cleaning fuel pool of NPP Cofrentes; Desarrollo del proyecto Prueba de Intercambio Termico del Sistema de Enfriamiento y Limpieza de la Piscina de combustible (G41) de Central Nuclear de Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, B.; Vaquer, J. I.; Mota, M.; Reyes, S.; Palomo, M.; Ruiz, G.; Rebollo, C.

    2012-07-01

    Heat exchanger tests were carried out and data in the thermodynamic models developed, turned and can verify that the efficiency of heat exchange met the requirements. The work concluded complying at all times with the technical specifications and quality proposals by the Department of engineering at the Central Nuclear de Cofrentes.

  10. 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.

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

    International Nuclear Information System (INIS)

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

  12. 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.

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

    International Nuclear Information System (INIS)

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

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

    International Nuclear Information System (INIS)

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  15. 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.

  16. Experience in training of health personnel for response to radiological and nuclear accidents

    International Nuclear Information System (INIS)

    Eletronuclear Healthcare Foundation is the Institution responsible for the actions of health response involving ionizing radiation in the area of Nuclear Power Plant Almirante Alvaro Alberto in Angra dos Reis. Because of their specific assignments and references for being in training health manpower in the field of ionizing radiation developed a range of Training Courses for Professionals Area Health to prepare them for Response to Radiological and Nuclear Accidents. Modules are proposed specifically for the professional response of the Technical Level and Higher Level, the level Pre-hospital and hospital. These modules are further divided into specific levels or modules, Basic or Introductory, Intermediate and Advanced. Are applied pretests and post tests to monitor the content of fixing, maintaining a historical series of reviews. Your content is theoretical and practical applications developed in 30 to 48 hours, with simulations (drills) and distribution of educational materials. We already have more than 80 applications training, focusing on internal staff and external to the institution, developing interesting partner with the Armed Forces and Civil Defense. It still maintained a link on the institution seeking access and download over 400 titles on the subject and exchange of information and experiences. For improving the teaching material, the authors launched in 2011 the first manual in Portuguese on the subject with new revised edition in 2013: 'Manual of Medical Actions In Radiological Emergencies'. The results indicate increased knowledge and appropriateness of the themes and the strategy proposed for this activity, demonstrating yet passed that information can be multiplied and meets the growing demand of the country that has hosted and will host international events relevant at QBNRE risk. (author)

  17. Chinese nuclear insurance and Chinese nuclear insurance pool

    International Nuclear Information System (INIS)

    Chinese Nuclear Insurance Started with Daya Bay Nuclear Power Station, PICC issued the insurance policy. Nuclear insurance cooperation between Chinese and international pool's organizations was set up in 1989. In 1996, the Chinese Nuclear Insurance Pool was prepared. The Chinese Nuclear Insurance Pool was approved by The Chinese Insurance Regulatory Committee in May of 1999. The principal aim is to centralize maximum the insurance capacity for nuclear insurance from local individual insurers and to strengthen the reinsurance relations with international insurance pools so as to provide the high quality insurance service for Chinese nuclear industry. The Member Company of Chinese Nuclear Pool and its roles are introduced in this article

  18. Europa central

    Directory of Open Access Journals (Sweden)

    Karel BARTOSEK

    2010-02-01

    Full Text Available La investigación francesa continúa interesándose por Europa Central. Desde luego, hay límites a este interés en el ambiente general de mi nueva patria: en la ignorancia, producto del largo desinterés de Francia por este espacio después de la Segunda Guerra Mundial, y en el comportamiento y la reflexión de la clase política y de los medios de comunicación (una anécdota para ilustrar este ambiente: durante la preparación de nuestro coloquio «Refugiados e inmigrantes de Europa Central en el movimiento antifascista y la Resistencia en Francia, 1933-1945», celebrado en París en octubre de 1986, el problema de la definición fue planteado concreta y «prácticamente». ¡Y hubo entonces un historiador eminente, para quién Alemania no formaría parte de Europa Central!.

  19. Use of nuclear and related techniques in studies of agroecological effects resulting from the use of persistent pesticides in Central America. Report of a final research co-ordination meeting

    International Nuclear Information System (INIS)

    The use of pesticides for the control of pests of agriculture and vectors of human and animal diseases in the countries of Central America is the highest per capita and one of the most intense in the world. There are reports of acute toxicity and chronic effects among farm workers. There are also reports that pesticide residues in food frequently exceed the Codex Alimentarius Commission's maximum residue levels (MRLs) and shipments of foodstuffs have been rejected by importing countries due to the presence of excessive residues of pesticides. Pesticides are also implicated in the contamination of continental and coastal waters. The indiscriminate use of pesticides would be expected to also aggravate pest problems by adversely affecting populations of beneficial arthropods and causing the development of resistance in pest populations. The Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture initiated a co-ordinated research project in 1992 to generate information on residues of pesticides in the environment, their persistence under local conditions and effect on local species of beneficial arthropods in agricultural and adjacent areas in the countries of Central America. Such information could be used in the implementation of legislation to control the distribution and use of pesticides and the development and application of integrated pest management programmes. Scientists from Costa Rica, Guatemala, Honduras, Nicaragua, Panama and the United States of America participated in this project. This TECDOC reports on the accomplishments of the project and includes the papers presented at the final Research Co-ordination Meeting held in Panama City, Panama, 20-24 April 1998

  20. Radiological surveillance in Mexico, derived of the accident of the Fukushima Daiichi nuclear power plant; Vigilancia radiologica en Mexico, derivado del accidente en la central nuclear de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    Aguirre G, J.; Nohpal J, X., E-mail: jaguirre@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Departamento de Vigilancia Radiologica, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    March 11, 2011 an earthquake of 9.0 grades in the Richter scale, originated in the coast of Tohoku, Japan, in the Pacific Ocean gave origin to a tsunami that caused an accident in the Fukushima Daiichi nuclear power plant. Due to this accident, derived of the loss of the reactor cooling system, as well as of the prolonged absence of alternating and direct current, radiological protection actions were realized without being able to avoid the liberation of radioactive material to the atmosphere and ocean. The radiological impact of these liberations, not only in Japan but around the world, mainly in the north hemisphere of the Earth, was analyzed by means of environmental dose measurements and radionuclide concentrations in soil and water, among others. In the Mexico case, air samples data were obtained, as well as environmental dose celerity and full-length counts of the people coming from Japan near the disaster area. The present work contains the obtained results of the realized measurements in Mexico, same that have been used to make a summary and analysis of the dispersion in the environment in several countries of the world. (Author)

  1. Corrosion in nuclear power plants and it implication in the leak before break criteria; Corrosion en centrales nucleares y su implicacion en el criterio de fuga antes de ruptura

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

    The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)

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

    International Nuclear Information System (INIS)

    In this work author proposes to constitute new virtual library which should centralize the information from nuclear disciplines on the INTERNET, in order to them to give first and foremost the connection on the most important links in set nuclear sciences. The author has entitled this new virtual library The World Wide Web Library: Nuclear Sciences. By constitution of this virtual library next basic principles were chosen: home pages of international organizations important from point of view of nuclear disciplines; home pages of the National Nuclear Commissions and governments; home pages of nuclear scientific societies; web-pages specialized on nuclear problematic, in general; periodical tables of elements and isotopes; web-pages aimed on Chernobyl crash and consequences; web-pages with antinuclear aim. Now continue the links grouped on web-pages according to single nuclear areas: nuclear arsenals; nuclear astrophysics; nuclear aspects of biology (radiobiology); nuclear chemistry; nuclear company; nuclear data centres; nuclear energy; nuclear energy, environmental aspects of (radioecology); nuclear energy info centres; nuclear engineering; nuclear industries; nuclear magnetic resonance; nuclear material monitoring; nuclear medicine and radiology; nuclear physics; nuclear power (plants); nuclear reactors; nuclear risk; nuclear technologies and defence; nuclear testing; nuclear tourism; nuclear wastes; nuclear wastes. In these single groups web-links will be concentrated into following groups: virtual libraries and specialized servers; science; nuclear societies; nuclear departments of the academic institutes; nuclear research institutes and laboratories; centres, info links

  3. Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde; Estudio de ruido ambiental en una planta BWR como la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Cruz G, M.; Amador C, C., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2013-10-15

    In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

  4. 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.

  5. The nuclear power decisions

    International Nuclear Information System (INIS)

    Nuclear power has now become highly controversial and there is violent disagreement about how far this technology can and should contribute to the Western energy economy. More so than any other energy resource, nuclear power has the capacity to provide much of our energy needs but the risk is now seen to be very large indeed. This book discusses the major British decisions in the civil nuclear field, and the way they were made, between 1953 and 1978. That is, it spans the period between the decision to construct Calder Hall - claimed as the world's first nuclear power station - and the Windscale Inquiry - claimed as the world's most thorough study of a nuclear project. For the period up to 1974 this involves a study of the internal processes of British central government - what the author terms 'private' politics to distinguish them from the very 'public' or open politics which have characterised the period since 1974. The private issues include the technical selection of nuclear reactors, the economic arguments about nuclear power and the political clashes between institutions and individuals. The public issues concern nuclear safety and the environment and the rights and opportunities for individuals and groups to protest about nuclear development. The book demonstrates that British civil nuclear power decision making has had many shortcomings and concludes that it was hampered by outdated political and administrative attitudes and machinery and that some of the central issues in the nuclear debate were misunderstood by the decision makers themselves. (author)

  6. Flow accelerated corrosion programme in Angra nuclear power plants Units 1 and 2

    International Nuclear Information System (INIS)

    Almirante Alvaro Alberto Nuclear Power Plant, referred herein as Angra NPP, comprises two generating units operated by ELETROBRAS Termonuclear S.A. - ELETRONUCLEAR. Unit 1, a Westinghouse designed PWR, operates commercially since 1982 generating 657 MW, while unit 2, designed by Siemens, is a 1350 MW PWR in operation since 2000. Flow Accelerated Corrosion (FAC) programme integrate a set of ageing related programmes established to control ageing effects on equipment and piping in order to ensure their capability to perform their functions during the plant remaining life. The objective of this paper is to describe ELETRONUCLEAR experience in developing and implementing a programme related to Flow Accelerated Corrosion, with focus on piping of the secondary sides of Angra NPP, explaining in detail the current situation for important pipings, and presenting updated results of the FAC control. Accurate inspections are the basis for an effective FAC programme. Wall thickness measurements establish the extent of wear in a given piping, providing data to support FAC trends, and to refine the predictive model. A permanently and clearly identify grid is makes re-inspection possible, at any time, at the same points. Supported by the computational system Comsy, some of its features as FAC potentially susceptible lines identification, wall thinning rates determination, inspection data recording, wear rates analyses, lifetime prediction and inspection scheduling will be showed in detail. This programme has started in 2004, and since this time it was applied in a total of six outages in Angra 1 NPP and three outages in Angra 2 NPP, with a large number of piping elements inspected and analyzed. Some of these results will be showed and discussed in this paper, regarding the potential of Flow Accelerated Corrosion occurrence. (author)

  7. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

    Energy Technology Data Exchange (ETDEWEB)

    Andriot, J.; Gaussens, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l

  8. Environmental restoration and waste management: An introduction. Student edition; Restauracion ambiental y administracion de residuos nucleares: Introduccion; Edicion estudiantil

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    For more than 40 years, the United States has produced nuclear weapons. These production activities generated both radioactive and hazardous waste and often contaminated the environment. For many years, the public was unaware of the problem and unable to do anything about it. All of this has changed. In response to recent public outcry, the former Secretary of Energy, Retired Admiral James D. Watkins, established the Office of Environmental Restoration and Waste Management (EM) in November 1989. The creation of EM was the first step toward correcting contamination problems from the past 40 years In this booklet, we at DOE, through the efforts of the students at Oak Hills High School of Cincinnati, Ohio, will introduce you to EM and encourage your involvement in this major program within the Department of Energy. [Espanol] Durante mas de 40 anos, los Estados Unidos fabricaron armamentos nucleares. Esta produccion genero residuos radiactivos y peligrosos y, en muchos casos, contaminaron el medio ambiente. Durante mucho tiempo, el publico norteamericano no tenia conocimiento de este problema y no pudo hacer nada para solucionarlo. Todo esto ha cambiado. Respondiendo a crecientes protestas publicas, el ex Secretario de Energia Almirante James D. Watkins, establecio en noviembre de 1989 la Subsecretaria de Administracion Ambiental. La creacion de esta Subsecretaria fue el primer paso que dio el Departamento de Energia para corregir los problemas de contaminacion ambiental de los ultimos 40 anos. En esta publicacion, los que trabajamos en el Departamento de Energia con la ayuda de los estudiantes de la Escuela Secundaria de Oak Hills, Cincinnati, Ohio, te introduciermos a la administracion ambiental y alentamos tu participacion en este programa de fundamental importancia en el Departamento de Energia.

  9. Control rod cluster drop time anomaly Guandong nuclear power station (Daya bay) and Electricite de France nuclear power stations (1450 MWe N4 Series); Anomalie de temps de chute des grappes de controle centrale de guang dong (daya bay) et centrales d`electricite de France (Palier N4-1450 MWE)

    Energy Technology Data Exchange (ETDEWEB)

    Olivera, J.J.; Naury, S.; Tricot, N.; Tran Dai, P.; Gama, J.M.

    1996-12-31

    The anomaly of control rod cluster drop time revealed at Guandong Nuclear Power Station in Daya Bay and in the Chooz B1 pilot unit for the N4 series, led to the replacement of the M1 type control rod cluster guide tubes with 1300 MWe PWR type guide tubes, adapted to the geometry of the Guandong reactors and the 1450 MWe reactors of the N4 series. The comparison of the drop times obtained with the 1300 MWe type control rod cluster guide 1300 MWe type control rod cluster guide tubes gave satisfactory results. These met the safety criterion for N4 series control rod cluster drop times (2.15 under hot shutdown conditions). The drop time tests which will be carried out in middle of and at the end of cycle 1 of Chooz B1 should make it possible to finally validate the solution already successfully implemented at Guandong. However, this anomaly has revealed the limits of representativeness of the experimental test loops with regard to the real reactor configuration. In view of this, it has been deemed necessary to ask Electricite de France to pursue its analysis both on the understanding of the phenomena which led to this anomaly and on the limits of the representativeness of the experimental test loops. (authors).

  10. Nuclear Physics of Neutron Stars

    OpenAIRE

    Piekarewicz, J.

    2009-01-01

    Understanding the equation of state (EOS) of cold nuclear matter, namely, the relation between the pressure and energy density, is a central goal of nuclear physics that cuts across a variety of disciplines. Indeed, the limits of nuclear existence, the collision of heavy ions, the structure of neutron stars, and the dynamics of core-collapse supernova, all depend critically on the equation of state of hadronic matter. In this contribution I will concentrate on the special role that nuclear ph...

  11. CENTRAL EUROPE: Role models

    International Nuclear Information System (INIS)

    Hungary is one of the newcomers to the CERN fold, having joined in 1992. The country's contributions are naturally in line with its slender resources and are not as immediately visible as those of the major Western European Member States. However the approach used and its consequent successes provide a good role model for a smaller nation in an international research environment. This was reflected on 24 September at a meeting of the European Committee for Future Accelerators (ECFA) convened in Budapest, continuing an ECFA tradition of holding meetings in national centres to learn more about the physics programmes of different countries. This tradition started with visits to major West European Centres, but last year ECFA held a meeting in Warsaw, its first in a central European country. By far the largest Hungarian population centre, Budapest is also a hub for national research in this sector, with university centres and the KFKI Research Institute for Particle and Nuclear Physics of the National Academy of Sciences. However important research work is also carried out in the eastern city of Debrecen. Hungarians look back to the classic investigations of Eotvos early this century as the starting point of their national tradition in fundamental physics. (In the mid-80s, these experiments briefly came back into vogue when there was a suggestion of an additional 'fifth force' contribution to nuclear masses.)

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

    International Nuclear Information System (INIS)

    The following aspects of experience gained in enhancing operational safety at Comed's nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight

  13. Nuclear Medicine

    Science.gov (United States)

    ... Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive tracers? ... funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that uses ...

  14. Nuclear regulation in transition

    International Nuclear Information System (INIS)

    The current state of nuclear regulations in the USA is examined. Since Three Mile Island the regulation of the nuclear power industry has been undergoing a noticeable transition. It will be argued here that the transition is characterized by two indicia. First, the primary focus of state and federal regulators has been on the financial aspects of the industry: this is best seen in the context of decisions allocating the costs of nuclear plant cancellations. Second, decisionmaking power has been decentralized: although the regulatory history of nuclear power demonstrates the tradition of centralized decisionmaking power (i.e., formerly the primary decisionmaking body was the Atomic Energy Commission), now States share decisionmaking power with the Nuclear Regulatory Commission. In Section 1 a brief legislative history of nuclear regulation is presented to establish the assertion that nuclear regulation, both de jure and de facto, was centralized. Next, Section 2 canvasses recent United States Supreme Court opinions regarding nuclear regulation. The Court frequently acts as policymaker through the consequences of its opinions, if not by its intent. In the area of nuclear policymaking, the Court has paid allegiance recently both to the tradition of centralization and to the movement toward decentralization. This dualism is reflected in other federal court decisions as well which will be briefly mentioned. Continuing the analysis of Federal regulation, Section 3 examines the current reform efforts of the NRC. Section 4 presents an examination of State responses to nuclear plant cancellations. In this section, State administrative agency and court decisions will be examined and recent State legislation will be discussed. (author)

  15. Invisible nuclear; converting nuclear

    International Nuclear Information System (INIS)

    This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

  16. Central Pain Syndrome

    Science.gov (United States)

    ... Enhancing Diversity Find People About NINDS NINDS Central Pain Syndrome Information Page Table of Contents (click to ... being done? Clinical Trials Organizations What is Central Pain Syndrome? Central pain syndrome is a neurological condition ...

  17. Super compacting of drums with dry solid radioactive waste in the nuclear power plant of Laguna Verde;Super compactacion de bidones con desecho radiactivo solido seco en la central nucleo electrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, R.; Lara H, M. A.; Cabrera Ll, M.; Verdalet de la Torre, O., E-mail: marco.lara@cfe.gob.m [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2009-10-15

    The nuclear power plant of Laguna Verde located in the Gulf of Mexico, completes in this 2009, nineteen years to produce by nuclear means 4.78% of the electric power that Mexico requires daily. During this time, the Unit 1 has generated more of 88.85 million mega watt-hour and the Unit 2 more of 69.48 million mega watt-hour with an availability average of 83.55%. Derived of their operation cycles, the nuclear power plant has generated (as any other installation of its type) radioactive wastes of low activity that at the moment are temporarily stored in the site. Due to the life cycle of the nuclear power plant, actually has become necessary to begin a project series focused to continue guaranteeing the storage of these wastes, guarantee that is a license requirement for the operation of this nuclear installation before the National Commission of Nuclear Security and Safeguards. The Federal Commission of Electricity beginning a project that allows continue guaranteeing space of sufficient storage for the wastes that the nuclear power plant of Laguna Verde could generate for the rest of its useful life, this project consisted on a process of physical volume reduction of dry solid radioactive wastes denominated super compacting, it has made possible to reduce the volume that these wastes occupy in the temporary storage noted Dry Solid Radioactive Wastes Deposit located inside the site that occupies the nuclear power plant of Laguna Verde. This work presents the super compacting results, as well as a description of the realization of this task until concluding with the super compacting of 5,854 drums with dry solid radioactive waste of low activity. We will enunciate which were the radiological controls that the Department of Radiological Protection of the nuclear power plant of Laguna Verde applied to this work that was realized for first time in Mexico and the nuclear power plant. (Author)

  18. 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.

  19. The nuclear case book

    International Nuclear Information System (INIS)

    The subject is covered in sections, entitled: the truth about nukes; disarmament, arms control and arms limitation; directory of nuclear weapons; tables of principal nuclear weapons; points of view 1 (Anglican); proliferation of nuclear technology; the just war; preventing proliferation; the numbers business; war scenario 1 (the Gulf); points of view 2 (Roman Catholic); deterrence; European Nuclear Balance; war scenario 2 (Germany); arguing about war and peace; points of view 3 (Jewish); is there a Soviet military threat; the view from Omsk; points of view 4 (Pugwash); the British deterrent; points of view 5 (generals for peace and disarmament); 'broken arrows'; costs of nuclear weapons; war scenario 3 (Pakistan); nuclear weapons - what is the moral response; non-use of nuclear weapons; points of view 6 (women and families for defence); dear Mr. Heseltine; why acquire nuclear weapons; the effects of nuclear weapons; war scenario 4 (Central America and the Middle East); civil defence; alternatives to nuclear defence; points of view 7 (Quaker). (U.K.)

  20. CINDU - Catalogue of numerical nuclear data available from the IAEA Nuclear Data Section

    International Nuclear Information System (INIS)

    This catalogue lists the nuclear data libraries presently held at the IAEA Nuclear Data Section. A number of evaluated neutron nuclear data files has recently been received at the IAEA Nuclear Data Section, and also libraries for charged particle nuclear data, photoneutron data, nuclear structure and decay data are now available. The primary purpose of the present issue is to publicize the various nuclear data libraries now available. CINDU is mainly addressed to nuclear and reactor physicists and other data users in the service area of the IAEA Nuclear Data Section, which includes countries in Eastern Europe and Asia (except USSR and Japan), Africa, Central and South America, Australia and New Zealand

  1. Nuclear cardiology

    International Nuclear Information System (INIS)

    Today, nuclear medicine techniques are routinely used in cardiological practice. They include procedures for the atraumatic investigation of different physiological processes in the various structures included in the central circulation: pericardium, myocardium, myocardial adrenergic innervation, cardiac chambers and valves, coronary microcirculation, and great vessels. Beside these in-Vivo procedures, they also comprise of in-Vitro methods for the detection and measurement in blood of various biological molecules of significance in the management of cardiac diseases. A common feature in this collection of in-Vivo and in-Vitro techniques is their ability to provide helpful clinical information for the diagnosis, prognosis and management of cardiac diseases. Their simplicity and safety for the patient allow their repeated use in the follow up of the progress of disease and in the assessment of the efficacy of the therapeutic measures

  2. To centralize or not to centralize?

    OpenAIRE

    Campbell, Andrew; Kunisch, Sven; Müller-Stewens, Günter

    2011-01-01

    The CEO's dilemma-were the gains of centralization worth the pain it could cause?-is a perennial one. Business leaders dating back at least to Alfred Sloan, who laid out GM's influential philosophy of decentralization in a series of memos during the 1920s, have recognized that badly judged centralization can stifle initiative, constrain the ability to tailor products and services locally, and burden business divisions with high costs and poor service.1 Insufficient centralization can deny bus...

  3. Panorama of the nuclear physics

    International Nuclear Information System (INIS)

    A summary of the topics covered by the nuclear physics, as disciplinary basis of the nuclear engineering, is presented, including from the fundamentals of modern physics used in nuclear physics, to the methods and more important applications, with the nucleus structure as central topic of the nuclear physics. In addition to a survey of the essential historical development in the different areas, this survey summarizes the basic concepts, postulates, laws and processes, which are the starting points, as in every scientific discipline for the understanding, interpretation and prediction of the variety of nuclear phenomena observed by methods increasingly improved and more complex, although such experimental methods are not discussed. (author)

  4. Laboratory Mesurements in Nuclear Astrophysics

    OpenAIRE

    Gai, Moshe

    1994-01-01

    After reviewing some of the basic concepts, nomenclatures and parametrizations of Astronomy, Astrophysics and Cosmology, we introduce a few central problems in Nuclear Astrophysics, including the hot-CNO cycle, helium burning in massive stars, and solar neutrino's. We demonstarte that SECONDARY (RADIOACTIVE) NUCLEAR BEAMS allow for considerable progress on these problems.

  5. Nuclear safety organisation in France

    International Nuclear Information System (INIS)

    This report outlines the public authorities responsible for the safety of nuclear installations in France. The composition and responsibilities of the Central Safety Service of Nuclear Installations within the Ministry of Industry, the Institute of Nuclear Protection and Safety within the CEA, the Central Service of Protection Against Ionising Radiation and the Interministerial Committee of Nuclear Safety are given. Other areas covered include the technical safety examination of large nuclear installations, the occurrence of accidents, treatment and control of release of radioactive wastes and decommissioning. The section on regulations covers the authorisation procedure, plant commissioning, release of radioactive effluents, surveillance and protection of workers exposed to ionising radiation. The situation is compared with the USA and the Federal Republic of Germany. A list of commercial nuclear installations in France is given

  6. Panel Discussion - Eastern and Central Europe decommissioning

    International Nuclear Information System (INIS)

    In conjunction with technical session 'Experience with Present Decommissioning Projects' the Panel Discussion is organized in the frame of ECED 2013 Conference. The main purposes of the panel was to analyse more in details the information given in the previous session and mainly to answer the questions from the audience. The panel was focused on the on-going decommissioning projects and on the projects in the final phase of preparation in the region of Eastern and Central Europe as follows: - Ignalina Nuclear Power Plant in Lithuania - RBMK-1500 reactors; - Chernobyl Nuclear Power Plant in Ukraine - RBMK-1000 reactors; - Kozloduy Nuclear Power Plant in Bulgaria - VVER-440 reactors; - Metsamor Armenian Nuclear Power Plant - VVER-440 reactors; - Greifswald Nuclear Power Plant in Germany (former East Germany) - VVER-440 reactors; - V1 Nuclear Power Plant in Slovakia - VVER-440 reactors; - A1 Nuclear Power Plant in Slovakia - Heavy Water Gas Cooled Reactor; shutdown after accident. The panel speakers listed the skilled and experienced representatives from all above mentioned countries and from Russian Federation where many decommissioning projects are ongoing or under preparation. The region of Eastern and Central Europe has actually become very important in the field of decommissioning and the lessons learned from the performed projects could make a significant base for decommissioning projects worldwide.

  7. Seismotectonic model of Central Europe

    International Nuclear Information System (INIS)

    Earthquakes belong to natural disasters which are associated with tectonic processes in the interior of the Earth. They are extremely devastating in populated areas; they cause human losses and damage personal estates and the environment. To mitigate the potential effects of earthquakes it is necessary that relief and mitigation structures operate following an earthquake, but it is also essential to stimulate and enhance preparedness and prevention. Prevention includes the development of scenarios of potential earthquakes, hazard mapping, formulation of regulations, etc. Preparedness includes the installation and operation of warning systems, establishing communication networks to operate before, during, and after earthquakes. As nuclear technology belongs to high-risk technologies with regard to human health and the environment and its hazard substantially increases in consequence of earthquakes, in the siting of a nuclear plant engineering solutions are generally available to mitigate the potential vibratory effects through design. For the choice of a suitable engineering solution, reliable data must be processed by reliable techniques. The IAEA safety guide of the safety series No. 50-SG-S1(Rev. 1) specifies the demands on data and on their processing and also on the regional seismotectonic model. With a view of this the regional seismotectonic model of Central Europe was created. The paper presents regional geological characteristics of Central Europe and a chronological model of neotectonic movements in Central Europe with specification of neotectonic regional units and their present movements. Moreover, it contains earthquake characteristics for Central Europe and the specification of seismogenic movements. It was found that the genesis of local regions with occurrence of the strongest earthquakes is connected with several movement trends in the last 5 Ma. Six more or less tectonically separate regional units were revealed. The earthquake epicenters often

  8. Nuclear scientists, merchants and persons

    International Nuclear Information System (INIS)

    This article on the investigations made in the field of nuclear fission in the Netherlands during the past decades was included as a central chapter in the book 'Nuclear Energy in Motion, a Handbook on Issues of Nuclear Energy' which shall be published shortly by Keesing Boeken, Amsterdam. The book containing contributions of about 30 authors, was edited by C.D. Andriesse and A. Heertje. (orig./HP)

  9. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident provides valuable lessons for China national nuclear Corp.as it continues to expand its operations AS Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp. (CNNC),the country’s largest nuclear plant operator, comes under the spotlight.

  10. A central spent fuel storage in Sweden

    International Nuclear Information System (INIS)

    A planned central spent fuel storage facility in Sweden is described. The nuclear power program and quantities of spent fuel generated in Sweden is discussed. A general description of the facility is given with emphasis on the lay-out of the buildings, transport casks and fuel handling. Finally a possible design of a Swedish transportation system is discussed. (author)

  11. Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

    International Nuclear Information System (INIS)

    Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

  12. Nuclear undertakers

    International Nuclear Information System (INIS)

    The Shippingport Atomic Power Station, the first commercial nuclear central electric-generating station in the US, will soon be taken apart and buried in a process known as decommissioning. Beginning in the spring of 1985, and expected to last four years, the process will be closely watched by both the nuclear industry and its critics. A small crew has just finished removing the last fuel assemblies from the reactor's nuclear core; however, the pressure-vessel walls remain intensely radioactive. The author outlines the radiation protective measures that will be used as the workers cut and saw to disassemble the 21 miles of piping inside the plant - e.g., building plastic enclosures around certain work areas to trap radioactive dust and working behind shielding as positioned saws do the cutting. Also, any radioactive concrete in the plant will be removed, again using the best radiation-protective measures. Once the decommissioning team works its way in the heart of the reactor, the pressure vessel - a steel cylinder 35 ft high and 10 ft across with walls 8 inches thick - plans call for erecting a tower above and pouring concrete into the cavity around the vessel. The 770-ton steel and concrete package will then be hoisted in one piece, placed on a heavy-duty transporter and hauled to a barge on the Ohio River, eventually following a water route to the Hanford, Washington energy reservation; there it will join some other 120 truckloads of other radioactive wastes from its plant for burial. Even if this is successfully accomplished as planned and at the $80 million estimate, critics point out that decommissioning the much larger plants will be much more complex and costly - that Shippingport is far from an analogous situation

  13. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

  14. Centrality, Rapidity And Transverse-Momentum Dependence of Cold Nuclear Matter Effects on J/Psi Production in D Au, Cu Cu And Au Au Collisions at S(NN)**(1/2)

    Energy Technology Data Exchange (ETDEWEB)

    Ferreiro, E.G.; /Santiago de Compostela U.; Fleuret, F.; /Ecole Polytechnique; Lansberg, J.P.; /Ecole Polytechnique /SLAC; Rakotozafindrabe, A.; /SPhN, DAPNIA, Saclay

    2011-11-11

    We have carried out a wide study of Cold Nuclear Matter (CNM) effects on J/{Psi} = production in dAu, CuCu and AuAu collisions at {radical}s{sub NN} = 200 GeV. We have studied the effects of three different gluon-shadowing parameterizations, using the usual simplified kinematics for which the momentum of the gluon recoiling against the J/{Psi} is neglected as well as an exact kinematics for a 2 {yields} 2 process, namely g + g {yields} J/{psi} + g as expected from LO pQCD. We have shown that the rapidity distribution of the nuclear modification factor R{sub dAu}, and particularly its anti-shadowing peak, is systematically shifted toward larger rapidities in the 2 {yields} 2 kinematics, irrespective of which shadowing parameterization is used. In turn, we have noted differences in the effective final-state nuclear absorption needed to fit the PHENIX dAu data. Taking advantage of our implementation of a 2 {yields} 2 kinematics, we have also computed the transverse momentum dependence of the nuclear modification factor, which cannot be predicted with the usual simplified kinematics. All the corresponding observables have been computed for CuCu and AuAu collisions and compared to the PHENIX and STAR data. Finally, we have extracted the effective nuclear absorption from the recent measurements of RCP in dAu collisions by the PHENIX collaboration.

  15. Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model; Analisis de viabilidad en la propuesta de expansion de la central nucleoelectrica Laguna Verde: aplicacion de opciones reales, modelo binomial

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez I, S.; Ortiz C, E.; Chavez M, C., E-mail: lunitza@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2011-11-15

    At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

  16. Development of a severe accident module of a nuclear power plant based in the MELCOR nuclear code and its incorporation to the room simulator; Desarrollo del modulo de accidentes severos de una central nucleoelectrica basado en el codigo nuclear MELCOR y su incorporacion al simulador de aula

    Energy Technology Data Exchange (ETDEWEB)

    Cortes M, F.S.; Ramos P, J.C.; Nelson E, P.; Chavez M, C. [Facultad de Ingenieria, Division de Ingenieria Electrica, Grupo de Ingenieria Nuclear, UNAM, Ciudad Universitaria, Distrito Federal (Mexico)]. E-mail: samuelcortes@correo.unam.mx

    2004-07-01

    This work describes the development of the Severe Accidents Module (MAS) based on the Code MELCOR and its incorporation to the Simulator of Classroom of the Group of Nuclear Engineering of the Engineering Faculty (GrINFI) of the National Autonomous University of Mexico (UNAM). The module of Severe Accidents has the purpose of counting with installed and operational capacity for the simulation of accident sequences with capacitation purposes, training, analysis and design. A shallow description of SimAula is presented, and the philosophy used to obtain the interactive version of MELCOR are discussed, as well as its implementation in the atmosphere of SimAula. Finally, after confirming the correct operation of the development of the tool, some possible topics are discussed for specific applications of the MAS. (Author)

  17. Central Neuropathic Pain Syndromes.

    Science.gov (United States)

    Watson, James C; Sandroni, Paola

    2016-03-01

    Chronic pain is common in patients with neurologic complications of a central nervous system insult such as stroke. The pain is most commonly musculoskeletal or related to obligatory overuse of neurologically unaffected limbs. However, neuropathic pain can result directly from the central nervous system injury. Impaired sensory discrimination can make it challenging to differentiate central neuropathic pain from other pain types or spasticity. Central neuropathic pain may also begin months to years after the injury, further obscuring recognition of its association with a past neurologic injury. This review focuses on unique clinical features that help distinguish central neuropathic pain. The most common clinical central pain syndromes-central poststroke pain, multiple sclerosis-related pain, and spinal cord injury-related pain-are reviewed in detail. Recent progress in understanding of the pathogenesis of central neuropathic pain is reviewed, and pharmacological, surgical, and neuromodulatory treatments of this notoriously difficult to treat pain syndrome are discussed. PMID:26944242

  18. NIDDK Central Repository

    Data.gov (United States)

    U.S. Department of Health & Human Services — The NIDDK Central Repository stores biosamples, genetic and other data collected in designated NIDDK-funded clinical studies. The purpose of the NIDDK Central...

  19. Central and peripheral demyelination

    OpenAIRE

    Man Mohan Mehndiratta; Natasha Singh Gulati

    2014-01-01

    Several conditions cause damage to the inherently normal myelin of central nervous system, perepheral nervous system or both central and perepheral nervous system and hence termed as central demyelinating diseases, perepheral demyelinating diseases and combined central and perepheral demyelinating diseases respectively. Here we analysed and foccused on the etiology, prevalance, incidence and age of these demyelinating disorders. Clinical attention and various diagnostic tests are needed to ad...

  20. Analysis of a natural draught tower in the circulation seawater system of nuclear power plant of Laguna Verde; Analisis de una torre de tiro natural en el sistema de agua de circulacion de mar de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Vargas A, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Veracruz (Mexico)], e-mail: francisco.tijerina@cfe.gob.mx

    2009-10-15

    The analysis of a natural draught tower in open circuit for the cooling system of seawater circulation on the nuclear power plant of Laguna Verde, it is based on conditions of 2027 MWt and 2317 MWt, where the flows of circulation water system hardly vary and whose purpose will be, to cool the seawater circulation. The circulation water system is used as heat drain in main condenser of turbo generator to condense the nuclear vapor. The annual average temperature in the seawater at present is of 26 C to the entrance to circulation water system and it is vary in accordance with the time of year. The mean temperature of leaving of circulation water system to the sea is of 41 C. Having a cooling tower to reduce the entrance temperature to the circulation water system, it improves the efficiency of thermal transfer in condenser, it improves the vacuum in condenser giving more operative margin to avoid condenser losses by air entrances and nuclear power plant shutdowns, as well as for to improve the efficiency of operative balance of nuclear power plant, also it prevents the impact in thermal transfer efficiency in condenser by the climatic change. (Author)

  1. Pensar la organización del tiempo de trabajo cuando la tecnología cambia: el caso del equipo de trabajo de operación de una central nuclear

    Directory of Open Access Journals (Sweden)

    Sophie Prunier-Poulmaire

    2011-12-01

    Full Text Available The construction of a new generation of nuclear power plant has implied an ergonomics contribution in order to define the shift work schedule for the future operation crew. The study was carried out in three existing nuclear power plants through observation of activities specific to the concerned operating professionals. The data collected highlights major disparities between the performed tasks and their dynamics in terms of physical and mental demands. Furthermore, the same data underlines a strong temporal interdependence amidst the operation crew based on shift work schedules and the maintenance crew organized with set day time schedules. Vast differences are also recorded in terms of physical and mental demands of the tasks performed between day and night shifts as well as between the different stages of nuclear installations. The difficulties of workforce management are also at the source of large differences concerning the theoretical shift work schedule and the shift work schedule in place. In a multifactorial and systemic approach, with the general knowledge of chronobiology and the characteristics of the population involved, the outcomes will be a necessary component to define the shift work schedule for the operation crew of the nuclear power plant in construction.

  2. Exploitation continuation of Fessenheim nuclear plant nr 1 reactor after thirty years of operation; Poursuite d'exploitation du reacteur n.1 de la centrale nucleaire de fessenheim apres trente annees de fonctionnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After having recalled the regulatory framework, this report indicates how the Fukushima accident has been taken into account by the French nuclear safety authority (ASN) for the decision of keeping on operating the Fessenheim nuclear plant. Then, after a general presentation of nuclear installations, the report describes some peculiarities of the Fessenheim power plant with respect to the other French nuclear plants. It comments and discusses various issues: reactor exploitation, fuel management, vessel exploitation, exploitation of the main secondary circuits, of the confinement enclosure, and of other equipment. It recalls significant events, exploitation rules, and modifications brought to the reactor. It gives a global assessment. The authors report the safety re-examination (approach, compliance examination, security re-assessment), controls performed during decennial inspection (main controls and tests, implementation of modifications foreseen by safety re-examination, significant events, monitoring by the ASN, reactor restarting after the third decennial inspection). Perspectives are then discussed for the ten following years in terms of maintenance policy, ageing management, reactor vessel serviceability, and additional actions within the frame of ageing management. The operation continuation is then discussed

  3. Activities of nuclear human resource development in nuclear industry

    International Nuclear Information System (INIS)

    Since 2007, the JAIF (Japan Atomic Industrial Forum) had established the nuclear energy human resource development council to make analysis of the issue on nuclear human resource development. The author mainly contributed to develop its road map as a chairman of working group. Questionnaire survey to relevant parties on issues of nuclear human resource development had been conducted and the council identified the six relevant issues and ten recommendations. Both aspects for career design and skill-up program are necessary to develop nuclear human resource at each developing step and four respective central coordinating hubs should be linked to each sector participating in human resource development. (T. Tanaka)

  4. French nuclear energy development strategy

    International Nuclear Information System (INIS)

    The nuclear energy development in France is based on the spirit of democracy. Through the discussions in various groups and so on, an energy independent policy has been decided. That is, the energy independence of 50% is aimed at by 1990, by reducing the energy import. In order to lower the current petroleum reliance from 48.5% to 32% (by 1990), the development of new energy sources, including nuclear power, is essential. Nuclear energy is particularly important for French energy independence. The nuclear energy development program is on a very large scale; the share of nuclear energy in the total primary energy will be from 26% to 28% by 1990. Nuclear power generation features its low cost, and its remarkably high safety. For the nuclear power development, the consensus by all people is necessary. For the purpose, the network of both local and central organs is set up. (Mori, K.)

  5. Computerized management of nuclear material at the Grenoble nuclear research centre

    International Nuclear Information System (INIS)

    Under French law the production, possession, transfer, use and transport of nuclear material are subject to prior authorization by the Ministry of Industry and to control with a view to preventing losses, theft or diversion of such material. The holder of the authorization is required, in particular, to take measures for the monitoring and accounting of the nuclear material. For this purpose, the Grenoble Nuclear Research Centre, in collaboration with the Central Directorate for Safety and the Institute for Nuclear Protection and Safety (IPSN) of the Commissariat a l'energie atomique, has designed a computerized network which can be used for automation and centralization of nuclear material monitoring and accounting at the Centres and for interfacing with the IPSN's national centralized accounting system. The paper describes this network with the possibilities of its use in real time and emphasizes the advantages offered by automated centralized nuclear material management. (author). 2 figs, 2 tabs

  6. Nuclear power in perspective

    International Nuclear Information System (INIS)

    The nuclear power debate hinges upon three major issues: radioactive waste disposal, reactor safety and proliferation. An alternative strategy for waste disposal is advocated which involves disposing of the radwaste (immobilized in SYNROC, a titanate ceramic waste form) in deep (4 km) drill-holes widely dispersed throughout the entire country. It is demonstrated that this strategy possesses major technical (safety) advantages over centralized, mined repositories. The comparative risks associated with coal-fired power generation and with the nuclear fuel cycle have been evaluated by many scientists, who conclude that nuclear power is far less hazardous. Considerable improvements in reactor design and safety are readily attainable. The nuclear industry should be obliged to meet these higher standards. The most hopeful means of limiting proliferation lies in international agreements, possibly combined with international monitoring and control of key segments of the fuel cycle, such as reprocessing

  7. Organization of the nuclear safety in France

    International Nuclear Information System (INIS)

    The organization of the French public authorities in nuclear safety is presented: the Central Department of Safety for Nuclear Facilities (S.C.S.I.N.), the Institute of Nuclear Protection and Safety (I.P.S.N.), the Central Department for Ionizing Radiation Protection (S.C.P.R.I.) and Interministerial Commission for Nuclear Safety; the Permanent Groups of specialists (reactors, accelerators and other facilities); the Permanent Nuclear Section for nuclear boiler safety. The safety principles for basic nuclear installations are recalled (technical inspection, risks, radioactive wastes, radioactive effluents, decommissioning). The French regulation is completed by instructions relating to the procedure (authorization, operation, effluent release), the monitoring of installations, protection of the workers exposed to ionizing radiations. The situation is compared with USA and the Federal Republic of Germany. A list of the French nuclear facilities is given

  8. Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant; Estimacion de requerimientos de energia eolica equivalente a la generacion electrica de la Central Nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A.; Hernandez M, I.A. [Facultad de Ingenieria, Division de Ingenieria Electrica, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: maiki27@yahoo.com; Martin del Campo M, C. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2004-07-01

    The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

  9. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  10. Nuclear Medicine.

    Science.gov (United States)

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  11. Nuclear power

    OpenAIRE

    Waller, David; McDonald, Alan; Greenwald, Judith; Mobbs, Paul

    2005-01-01

    David Waller and Alan McDonald ask whether a nuclear renaissance can be predicted; Judith M. Greenwald discusses keeping the nuclear power option open; Paul Mobbs considers the availability of uranium and the future of nuclear energy.

  12. Nuclear electronics

    International Nuclear Information System (INIS)

    A short survey is given on nuclear radiation detectors and nuclear electronics. It is written for newcomers and those, who are not very familiar with this technique. Some additional information is given on typical failures in nuclear measurement systems. (orig.)

  13. Reactivity follow of the two first loadings of the Jose Cabrera Reactor; Seguimiento de la ractividad durante las dos primeras cargas del Reactor de la Central Nuclear Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Bru, A.

    1975-07-01

    In this paper the first two cores together with the in-core measurements taken during the operation of the Nuclear Power Station Jose Cabrera are described. The results of this measurements have been processed with the INCORE and FOLLOW codes. The peaking factors and the boron concentration versus burn-up are displayed. The final burn-up of the fuel elements in these two loading are given, too. (Author)

  14. Technical economic feasibility study for the implementation of a nuclear power plant for the production of electricity in Colombia; Estudio de factibilidad tecnico economica para la implementacion de una central de energia nuclear para la produccion de energia electrica en Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Gonzales, David E.; Bolanos, Hernan G.; Mayorga, Manuel A.; Rodriguez, Edwin A., E-mail: david_egO@yahoo.es, E-mail: hernanbolaos@yahoo.com.ar, E-mail: alejo_mayorga@yahoo.com, E-mail: edwin.rodriguez@distoyota.com.co [Escuela Colombiana de Carreras Industriales (ECCI), Bogota (Colombia). Grupo de Investigacion GIATME

    2013-07-01

    A study on the technical and economic feasibility will be used to implement a nuclear power in Colombia to generate electricity. To this will be searched if there are previous studies on this topic and what they concluded. The manner in which power is supplied will be discussed in a national level nowadays, its strengths and weaknesses. It will be investigated the legal norms that exists in the country on nuclear power and renewable energy sources, the standards established at world level, the nuclear accidents and the great examples. Providers will be sought on the world market nuclear equipment which serve to this purpose and the technical characteristics of these equipment will be discussed. The type of fuel used in nuclear reactors, its origin, method of production, specifications, availability and long-term and safe handling and final disposal are considered. safe handling of this technology and policy or international rules that will studied.

  15. Experiences in the implementation of the Coaching project in the nuclear power plant of Laguna Verde (NPP-L V); Experiencias en la implementacion del proyecto Coaching en la Central Nucleoelectrica Laguna Verde (CNLV)

    Energy Technology Data Exchange (ETDEWEB)

    Mendez M, H. I., E-mail: hugo.mendez01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Departamento del Centro de Entrenamiento, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2012-10-15

    This document has the purpose of to share acquired experiences during the implementation of the Coaching project focused the training of supervisors and directive personnel of the nuclear power plant of Laguna Verde (NPP-L V). Derived of the improvement areas identified by the supervisor organization of the nuclear power stations WANO (World Association Nuclear of Operators) and of the auto-evaluations realized by the expert personnel of the same power station that based on external experiences carried out through the Benchmarking (comparison with other power stations) they have reflected the necessity to activate a training process in Coaching with a practical focus toward the directive and supervisor personnel in the power station. By means of the observation of the personnel's acting so much in the control rooms like in different areas, three focus areas have been identified for the training in Coaching, these are the personnel's motivation, the organizational communication so much in vertical form as horizontal and the perception of confidence lack among directive, supervisors, operators and technicians. The plan focused in the abilities training of Coaching with practical sense was development, supported with an evaluation of 360 grades as tool of competitions development through a computer application e-Coaching. The use of application and Coaching following techniques facilitated the conformation of the practical focus, same that are of continuous use starting from the training of the supervisor and directive personnel. (Author)

  16. Nuclear power

    International Nuclear Information System (INIS)

    The subject is covered in chapters entitled: nuclear power certainties and doubts; nuclear power in the Western World to 2000; the frequency of core meltdown accidents; hidden costs of the accident at Three Mile Island; costs of nuclear accidents - implications for reactor choice; defining the risks of nuclear power; the uncertain economics of a nuclear power program; the economics of enabling decisions (Sizewell B as an enabling decision); trade in nuclear electricity; some pointers to the future. (U.K.)

  17. Nuclear data needs in Thailand

    International Nuclear Information System (INIS)

    The major nuclear facilities in Thailand are composed of nuclear research reactor, neutron generators, electron linear accelerators and 1 GeV Synchrotron facility, which is under construction. The other small facilities are radioisotope sources and X ray tubes for X ray diffraction and fluorescence studies. Office of Atomic Energy for Peace (OAEP) is the function arm for nuclear institutions in Thailand. Its major roles are nuclear regulatory, coordinating for nuclear affairs and foreign relations, R and D for nuclear science and technology and giving nuclear services. Nuclear data activities concerning Thai Research Reactor (TRR-1/M1) are for examples: neutronics and thermalhydraulics for reactor operation, neutron energy spectrum and neutron flux measurement for neutron activation analysis and isotope production, neutron and gamma doses, shielding and material testing for radiation safety, and neutron beam experiments. OAEP is taking part in the areas of regional cooperation on utilization of nuclear research reactors, education and training, sharing of research reactor experimental facilities, establishment of nuclear data program and information exchange. The nuclear data reports have been shared among institutions in Thailand through OAEP, which is served as a central nuclear data depository including e.g., INIS, IAEA-NDS, Joint Research Centre Commission of the European Communities and Japanese Nuclear Data Committee (JNDC). This report shows the nuclear facilities in Thailand, the roles of the Office of Atomic Energy for Peace on nuclear data depository and nuclear power development program. The main activities at the Thai Research Reactor TRR-1/M1 concerning nuclear data needs for specific uses in both theoretical and experimental aspects are also described. (J.P.N.)

  18. Nuclear data needs in Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Chongkum, S. [Physics Division, Office of Atomic Energy for Peace, Bangkok (Thailand)

    1999-03-01

    The major nuclear facilities in Thailand are composed of nuclear research reactor, neutron generators, electron linear accelerators and 1 GeV Synchrotron facility, which is under construction. The other small facilities are radioisotope sources and X ray tubes for X ray diffraction and fluorescence studies. Office of Atomic Energy for Peace (OAEP) is the function arm for nuclear institutions in Thailand. Its major roles are nuclear regulatory, coordinating for nuclear affairs and foreign relations, R and D for nuclear science and technology and giving nuclear services. Nuclear data activities concerning Thai Research Reactor (TRR-1/M1) are for examples: neutronics and thermalhydraulics for reactor operation, neutron energy spectrum and neutron flux measurement for neutron activation analysis and isotope production, neutron and gamma doses, shielding and material testing for radiation safety, and neutron beam experiments. OAEP is taking part in the areas of regional cooperation on utilization of nuclear research reactors, education and training, sharing of research reactor experimental facilities, establishment of nuclear data program and information exchange. The nuclear data reports have been shared among institutions in Thailand through OAEP, which is served as a central nuclear data depository including e.g., INIS, IAEA-NDS, Joint Research Centre Commission of the European Communities and Japanese Nuclear Data Committee (JNDC). This report shows the nuclear facilities in Thailand, the roles of the Office of Atomic Energy for Peace on nuclear data depository and nuclear power development program. The main activities at the Thai Research Reactor TRR-1/M1 concerning nuclear data needs for specific uses in both theoretical and experimental aspects are also described. (J.P.N.)

  19. Nuclear power

    International Nuclear Information System (INIS)

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  20. Nuclear building blocks

    International Nuclear Information System (INIS)

    The Candu 300 is the latest and smallest version of the CANDU pressurized heavy water reactor. It is designed for modular construction which, it is hoped, will shorten the construction schedule, take advantage of factory construction, improve quality (because central work locations and better conditions can be used) and provide flexibility of supply. The basic CANDU nuclear steam supply system is described generally and then the station and building layout, modular construction sequence (using a very heavy lift mobile crane), the process system modules and major nuclear equipment modules, are described in more detail. The advantages of modularisation are explained and plans for future modular reactors are mentioned. (U.K.)

  1. Nuclear fuels accounting interface: River Bend experience

    Energy Technology Data Exchange (ETDEWEB)

    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.

  2. Nuclear fuels accounting interface: River Bend experience

    International Nuclear Information System (INIS)

    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

  3. Use of isotope techniques in the study of radioactive contamination of hydric resources in the central region of Cuba as a consequence of fallout from atmospheric nuclear bomb tests

    International Nuclear Information System (INIS)

    The Central Radiological and Environmental Surveillance Laboratory has developed a monitoring programme for some environmental variables among which are included measurements of Cs-137 or Sr-90 concentrations in soil, grass, milk, foods, surface and underground waters and air, thereby almost completely surveying the natural cycle of these radionuclides in nature. The main goal of this paper is to present the Cs-137 and Sr-90 activity levels determined in atmospheric and water samples and to present some considerations about the transfer of these radionuclides between different environmental components

  4. CENTRAL ASIA'S POWER DILEMMAS

    OpenAIRE

    Budkin, Viktor

    2006-01-01

    It turned out to be much harder to create new power structures in Central Asia than elsewhere in the post-socialist world: no matter how hard it was for the Central European countries to acquire new political institutions, their advance toward the Western democratic model was much smoother. In the European part of the post-Soviet geopolitical expanse, Russia, Ukraine, and Moldova experienced fewer problems than the Central Asian region (CAR for short), though they too had their share of contr...

  5. Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Cuantificacion de secuencias de accidente y resultados

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1994-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

  6. Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis; Analisis de Eventos Internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Analisis de sistemas

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant{sup ,} CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

  7. Análisis de secuencias de accidente de pérdida de refrigerante en centrales nucleares de agua a presión mediante la metodología ISA

    OpenAIRE

    González Cadelo, Juan

    2015-01-01

    El accidente de pérdida de refrigerante (LOCA) en un reactor nuclear es uno de los accidentes Base de Diseño más preocupantes y estudiados desde el origen del uso de la tecnología de fisión en la industria productora de energía. El LOCA ocupa, desde el punto de vista de los análisis de seguridad, un lugar de vanguardia tanto en el análisis determinista (DSA) como probabilista (PSA), cuya diferenciada perspectiva ha ido evolucionando notablemente en lo que al crédito a la actuación de las salv...

  8. Detailed study of the heat sink of Saint-Laurent-des-Eaux nuclear plant; Etude detaillee de la source froide de la centrale de Saint-Laurent des Eaux

    Energy Technology Data Exchange (ETDEWEB)

    Audrerie, Y

    1997-12-31

    This work is dedicated to a detailed study of the reliability of the heat sink of the nuclear plant which is situated on the banks of the Loire river. In the first part the requirements the heat sink has to comply with are reviewed, in the second part the various operating modes, the different procedures established to cope with the hazards of the river: icing up, frost, overflow, lowest water, choking are reported. This analysis highlights the good compliance of the heat sink with the specifications but some improvements about periodic testing are proposed. (A.C.)

  9. Risco, simbolização e mito: o caso da possível construção de uma central nuclear em Portugal (2005-2006)

    OpenAIRE

    Graça, Inês Lampreia de Oliveira

    2008-01-01

    Mestrado em Comunicação, Cultura e Tecnologias da Informação A presente dissertação tem como principal objectivo aceder à discursividade simbólica do risco associado à energia nuclear. Num primeiro capítulo elaboramos uma proposta teórica do conceito de risco tecnológico, tentando delimitar alguns dos seus elementos mais importantes salientados por diversos autores. Na sequência deste capítulo, tomando como premissa que a imprensa desempenha um papel fundamental na circulação d...

  10. Central Laboratories Services

    Data.gov (United States)

    Federal Laboratory Consortium — The TVA Central Laboratories Services is a comprehensive technical support center, offering you a complete range of scientific, engineering, and technical services....

  11. Nuclear medicine

    International Nuclear Information System (INIS)

    Several growth areas for nuclear medicine were defined. Among them were: cardiac nuclear medicine, neuro-psychiatric nuclear medicine, and cancer diagnosis through direct tumor imaging. A powerful new tool, Positron Emission Tomography (PET) was lauded as the impetus for new developments in nuclear medicine. The political environment (funding, degree of autonomy) was discussed, as were the economic and scientific environments

  12. Analysis of the noise of the jet pumps of the Unit 2 of the Laguna Verde nuclear power plant; Analisis de ruido de las bombas de chorro de la Unidad 2 de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Castillo D, R.; Ortiz V, J.; Ruiz E, J.A. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica de Laguna Verde, Alto Lucero, Veracruz (Mexico)]. E-mail: rcd@nuclear.inin-mx

    2004-07-01

    The use of the analysis of noise for the detection of badly functioning of the components of a BWR it is a powerful tool in the determination of abnormal conditions of operation, during the life of a nuclear plant of power. From the eighties, some nuclear reactors have presented problems related with the jet pumps and the knots of the recirculation. The Regulatory Commission of the United States, in the I E bulletin 80-07, recommended to carry out a periodic supervision of the pressure drop of the jet pumps, to prevent structural failures. In this work, methods of analysis of noise are used for the detection of abnormal conditions of operation of the jet pumps of a BWR. Signals are analysed to low and high frequency of pressure drop with the NOISE software that is in development. The obtained results show the behavior of the jet pumps of jet 6 and 11 before and after a partial blockade in their throats where the pump 6 return to their condition of previous operation and the pump 11 present a new fall of pressure, inside the limit them permissible of operation. The methodology of the analysis of noise demonstrated to be an useful tool for the badly functioning detection, and you could apply to create a database to supervise the dynamic behavior of the jet pumps of an BWR. (Author)

  13. Review of progress in modelling for the assessment of the operating life of a nuclear power plant; Panorama des progres de la modelisation au service de la duree de vie des centrales

    Energy Technology Data Exchange (ETDEWEB)

    Monnier, B. [Electricite de France (EDF/RD), 78 - Chatou (France); Gilles, Ph. [FRAMATOME ANP, 92 - Paris-La-Defence (France); Chauliac, Ch. [CEA Saclay, Dir. de l' Energie Nucleaire DEN/DSOE, 91 - Gif sur Yvette (France)

    2004-07-01

    This article reviews the contributions of simulation and modelling to the assessment of the service life of a nuclear power plant. 4 aspects are considered. The first aspect concerns the operating life of the reactor vessel, in order to evaluate its aging a series of more or less intertwined modelling is necessary, they concern thermal-hydraulic transients, neutron fluences, damages due to irradiation and thermal-mechanical behaviour. The second aspect is the use of simulation to optimize non-destructive testing (NDT) particularly to assess the performances and limits of NDT methods in order to assure safety in any situation. The third aspect concerns the simulation of welding in order to assess the risk of defect occurrence, the pile-up of residual stresses and the feasibility of a complex welding. The last aspect is a global simulation of a nuclear unit as a whole involving its main components such as vessel, pumps, steam generators, turbine...; their maintenance, their failure risks in order to define indicator parameters that are relevant to the real state of the plant. (A.C.)

  14. Glossary of nuclear energy

    International Nuclear Information System (INIS)

    TNC 90 focuses on nuclear energy technology. Some more basic or less central terms which were included in the previous glossary, TNC 55, have not been included in this version. About 1200 definitions in swedish included together with translations to english, german and french. The terms have been listed in alphabetical order. To make it easier to look up a certain term or terms that stand for related concepts the terms have been systematically arranged in a special index. (L.E.)

  15. Nuclear links

    International Nuclear Information System (INIS)

    The subject is dealt with in sections: introduction; energy and the third world; world energy consumption 1978; oil -the energy dilemma; nuclear chains - introduction; uranium; Namibia; enrichment and reprocessing; countries with enrichment and reprocessing facilities; waste; conclusion; why take the nuclear option; third world countries with nuclear reactors; the arms connection; government spending and human resources 1977 (by countries); nuclear power - the final solution; the fascists; world bank; campaigns; community action in Plogoff; Australian labour movement; NUM against nuclear power; Scottish campaign; students against nuclear energy; anti-nuclear campaign; partizans; 3W1 disarmament and development; campaign ATOM; CANUC; 3W1; SANE. (U.K.)

  16. Second School of Nuclear Energetics

    International Nuclear Information System (INIS)

    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.

  17. NUCLEAR TERRORISM

    OpenAIRE

    RUTIC SRDJAN Z.

    2016-01-01

    The paper has analyzed different manifestations of terrorism with nuclear weapons and ionizing radiation as a special kind of terrorism. Possibilities that terrorist groups come into possession of nuclear weapons and apply them for terrorist purposes have been analysed. The forms and methods of terrorist activities with nuclear means have been given as well. It has been concluded that nuclear terrorism includes various forms of threats, including not only nuclear weapons but also the sources ...

  18. Central centrifugal cicatricial alopecia

    OpenAIRE

    Collin Blattner; Dennis C Polley; Frank Ferritto; Elston, Dirk M

    2013-01-01

    Central centrifugal cicatricial alopecia is a common cause of progressive permanent apical alopecia. This unique form of alopecia includes entities previously know as “hot comb alopecia,” “follicular degeneration syndrome,” “pseudopelade” in African Americans and “central elliptical pseudopelade” in Caucasians. The etiology appears to be multifactorial and the condition occurs in all races.

  19. Central pontine myelinolysis

    Science.gov (United States)

    ... from one nerve to another. The most common cause of central pontine myelinolysis is a quick change in the body's sodium ... The nerve damage caused by central pontine myelinolysis is usually ... The disorder can cause serious long-term (chronic) disability.

  20. Central Diffraction at ALICE

    CERN Document Server

    Lämsä, Jerry W

    2011-01-01

    The ALICE experiment is shown to be well suited for studies of exclusive final states from central diffractive reactions. The gluon-rich environment of the central system allows detailed QCD studies and searches for exotic meson states, such as glueballs, hybrids and new charmonium-like states. It would also provide a good testing ground for detailed studies of heavy quarkonia. Due to its central barrel performance, ALICE can accurately measure the low-mass central systems with good purity. The efficiency of the Forward Multiplicity Detector (FMD) and the Forward Shower Counter (FSC) system for detecting rapidity gaps is shown to be adequate for the proposed studies. With this detector arrangement, valuable new data can be obtained by tagging central diffractive processes.

  1. Central diffraction at ALICE

    Energy Technology Data Exchange (ETDEWEB)

    Laemsae, J W; Orava, R, E-mail: risto.orava@helsinki.fi [Helsinki Insitute of Physics, and Division of Elementary Particle Physics, Department of Physics, PL 64 (Gustaf Haellstroeminkatu 2a), FI-00014 University of Helsinki (Finland)

    2011-02-01

    The ALICE experiment is shown to be well suited for studies of exclusive final states from central diffractive reactions. The gluon-rich environment of the central system allows detailed QCD studies and searches for exotic meson states, such as glueballs, hybrids and new charmonium-like states. It would also provide a good testing ground for detailed studies of heavy quarkonia. Due to its central barrel performance, ALICE can accurately measure the low-mass central systems with good purity. The efficiency of the Forward Multiplicity Detector (FMD) and the Forward Shower Counter (FSC) system for detecting rapidity gaps is shown to be adequate for the proposed studies. With this detector arrangement, valuable new data can be obtained by tagging central diffractive processes.

  2. Nuclear safeguards and nuclear shutdowns

    International Nuclear Information System (INIS)

    The issues involved in the California nuclear initiative (Proposition 15) are described. Some of the characteristics of the anti-nuclear lobby are outlined. Some do's and don'ts for the nuclear group are listed. The nuclear shutdown effort was concentrated on the safeguards and high-level waste disposal issues

  3. Topical questions of nuclear energy

    International Nuclear Information System (INIS)

    The discussion with the general public on reactor safety, environmental protection, and the relevance of nuclear energy for the energy supply - including the increasingly political character of the nuclear energy debate - was a central issue at this meeting of reactor experts which recurred even more often than in recent years and also found its way into the opening and closing speeches. This first report on the reactor meeting, therefore, contains three excerpts from papers read on this issue. (orig./AK)

  4. Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel; Analisis de los danos micro-estructurales por irradiacion neutronica del acero de la vasija de los reactores de la Central Nuclear de Laguna Verde. Caracterizacion del acero de diseno

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y Rodriguez, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Av. Luis Enrique Erro s/n, Unidad Profesional Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.m [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-09-15

    The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

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

    International Nuclear Information System (INIS)

    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.)

  6. Development of an interactive model of the Laguna Verde nuclear power plant based on the RELAP/SCDAP code; Desarrollo del modelo interactivo de la central nucleoelectrica de Laguna Verde basado en el codigo RELAP/SCDAP

    Energy Technology Data Exchange (ETDEWEB)

    Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [LAIRN, FI-UNAM, DEPFI Campus Morelos, Jiutepec, Morelos (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    The present work describes the development of an interactive model of the Nuclear power plant of Laguna Verde (CNLV) based on the RELAP/SCDAP nuclear code, and it incorporation to a classroom simulator. The functional prototype it allows to make evaluations for operational transients and postulates accidents, with capacitation purposes, training, analysis and design. It emphasizes on the methodology used to establish the inter activity. Such methodology, is based on a modular structure in the one that multiple processes can be executed in an independent way and where the generated information is stored in segments of shared memory (characteristic that allows the UNIX operating system) and sent to the different processes by means of communication routines developed in C programming language. The utility of the system is demonstrated by means of the use of interactive display graphics (mimic diagrams, pictorials and tendency graphics) for the simultaneous dynamic visualization of the variables more significant that involve to the pattern of a transitory event type (for example failure of the controller of feeding water in a BWR reactor). Near with the interactive module, it was developed a model of the reactor of the CNLV for the code of better estimation RELAP/SCDAP. Finally the evaluation of the model is described, where it is interpreted in general form the behavior of those main variables that describe the stationary state, corroborating that follow the same tendency that those reported in the FSAR (Final Safety Analysis Report) of the Laguna Verde plant. The obtained results allow to conclude that the made development was satisfactory and that it presents enormous advantages regarding the capacity and time of analysis when using tools of visualization in real time of execution. (Author)

  7. International nuclear material safeguards

    International Nuclear Information System (INIS)

    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)

  8. Nuclear deformation and magic numbers from POT

    International Nuclear Information System (INIS)

    The shell structure in nuclei has been the central theme of nuclear structure physics for the past three decades. Evolution of shell structure with particle numbers, nuclear shapes and angular momenta gives rise to a wide variety of phenomena. Central to the use of shell effects has been the Strutinsky's shell correction method. A semiclassical trace formula based on the periodic orbit theory has also been quite successful in calculating the shell corrections to the level density

  9. Training strategic community agents in health effects of ionizing radiation

    International Nuclear Information System (INIS)

    The main motivation for the development of training was the need to train agents (opinion makers) with proximity and credibility among the population, to clarify the most frequently asked questions in relation to ionizing radiation, the operation of nuclear power plants, emergency plans and about the possibility of there effects of radiation on the health of inhabitants in regions close to the central Nuclear Almirante Alvaro Alberto - CNAAA. The project has a target audience of 420 agents, 60 of them have already been trained in a pilot project . The results indicate that the topics of training were adequate and the agents have expanded their knowledge. On the other hand, the information passed on to communities by agents, recognized by this population as ' the most reliable people', is of greater credibility and likelihood of success in communicating important issues for the population living in the vicinity of the CNAAA. (author)

  10. Analysis of reactivity insertion accidents in PWR reactors

    International Nuclear Information System (INIS)

    A calculation model to analyze reactivity insertion accidents in a PWR reactor was developed. To analyze the nuclear power transient, the AIREK-III code was used, which simulates the conventional point-kinetic equations with six groups of delayed neutron precursors. Some modifications were made to generalize and to adapt the program to solve the proposed problems. A transient thermal analysis model was developed which simulates the heat transfer process in a cross section of a UO2 fuel rod with Zircalloy clad, a gap fullfilled with Helium gas and the correspondent coolant channel, using as input the nulcear power transient calculated by AIREK-III. The behavior of ANGRA-i reactor was analized during two types of accidents: - uncontrolled rod withdrawal from subcritical condition; - uncontrolled rod withdrawal at power. The results and conclusions obtained will be used in the license process of the Unit 1 of the Central Nuclear Almirante Alvaro Alberto. (Author)

  11. Off-site emergency response plans in case of technological catastrophes: the case Angra dos Reis

    International Nuclear Information System (INIS)

    In the first part of the thesis a discussion of the technical, operational and methodological features of the current practices for emergency planning in case of a nuclear fallout. Based on this general reference is possible to evaluate the features in the natural and social environment of Angra dos Reis that probably will obstruct the application of the protective countermeasures to the public. These critical points are enhanced to permit the discussion of a methodological approach that is supposed to be suitable to the reality of Angra dos Reis. The approach was developed specifically to this region and was introduced as a part of the general emergency off-site plan to the Central Nuclear Almirante Alvaro Alberto (CNAAA). Starting from this experience will be possible to enlarge this approach in a further research, in order to study this potential hazards of other industrial plants. (author)

  12. Central Safety Department. Annual report 1986

    International Nuclear Information System (INIS)

    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.)

  13. Modelling turbulent fluid flows in nuclear and fossil-fired power plants; La modelisation des ecoulements turbulents rencontres dans les reacteurs nucleaires et dans les centrales thermiques a flamme

    Energy Technology Data Exchange (ETDEWEB)

    Viollet, P.L.

    1995-06-01

    The turbulent flows encountered in nuclear reactor thermal hydraulic studies or fossil-fired plant thermo-aerodynamic analyses feature widely varying characteristics, frequently entailing heat transfers and two-phase flows so that modelling these phenomena tends more and more to involve coupling between several branches of engineering. Multi-scale geometries are often encountered, with complex wall shapes, such as a PWR vessel, a reactor coolant pump impeller or a circulating fluidized bed combustion chamber. When it comes to validating physical models of these flows, the analytical process highlights the main descriptive parameters of local flow conditions: tensor characterizing the turbulence anisotropy, characteristic time scales for turbulent flow particle dynamics. Cooperative procedures implemented between national or international working parties can accelerate validation by sharing and exchanging results obtained by the various organizations involved. With this principle accepted, we still have to validate the products themselves, i.e. the software used for the studies. In this context, the ESTET, ASTRID and N3S codes have been subjected to a battery of test cases covering their respective fields of application. These test cases are re-run for each new version, so that the sets of test cases systematically benefit from the gradually upgraded functionalities of the codes. (author). refs., 3 figs., 6 tabs.

  14. Nuclear law

    International Nuclear Information System (INIS)

    Different laws on use of atomic energy for peaceful purposes in Bulgaria and Italy are given here: civil liability, nuclear safety, radiation protection, radioactive waste, nuclear facilities, decommissioning, health and environment protection. (N.C.)

  15. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  16. Nuclear forensics

    International Nuclear Information System (INIS)

    Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone activity

  17. Central line infections - hospitals

    Science.gov (United States)

    ... risk is higher if you: Are in the intensive care unit (ICU) Have a weakened immune system or serious ... unless you have washed your hands. Tell your nurse if your central line: Gets dirty Is coming ...

  18. Central Data Exchange

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Central Data Exchange (CDX) enables fast, efficient and more accurate environmental data submissions from state and local governments, industry and tribes to...

  19. "Central Station" Londonis

    Index Scriptorium Estoniae

    2000-01-01

    Londoni galeriis Milch seitsme läti, leedu ja eesti kunstniku projekt "Central Station". Kuraatorid Lisa Panting, Sally Tallant. Eestist osalevad Hanno Soans (Catarina Campinoga koostöös valminud video), Kiwa, Kai Kaljo

  20. Central Asian Republic Info

    Data.gov (United States)

    US Agency for International Development — CAR Info is designed and managed by the Central Asian Republic Mission to fill in the knowledge and reporting gaps in existing agency systems for that Mission. It...

  1. Central nervous system

    Science.gov (United States)

    The central nervous system is composed of the brain and spinal cord. Your brain and spinal cord serve as the main "processing center" for your entire nervous system. They control all the workings of your body.

  2. Central nervous system resuscitation

    DEFF Research Database (Denmark)

    McIntosh, T K; Garde, E; Saatman, K E;

    1997-01-01

    Traumatic injury to the central nervous system induces delayed neuronal death, which may be mediated by acute and chronic neurochemical changes. Experimental identification of these injury mechanisms and elucidation of the neurochemical cascade following trauma may provide enhanced opportunities...

  3. Comparison of different nuclear fuel cycles for LWR applications

    OpenAIRE

    Winblad von Walter, Tobias

    2008-01-01

    Nuclear power is considered a vital energy source, without greenhouse gas emissions, regarding the commitment towards sustainable energy systems. This is especially on the topic of the present climate debate. A central aspect of nuclear power is nuclear fuel. Presently Uranium dioxide (UOX) is the most common nuclear fuel in the world. However, an increased uranium price, waste and proliferation issues are some of the aspects that have resulted in a growing interest for other nuclear fuels. M...

  4. Evaluation of the transfer of {sup 3}H rain to fungi into two areas, near and far from the Almaraz Nuclear Power Plant; Evaluacion de la transferencia del {sup 3}H de la lluvia a los hongos en dos zonas, proxima y alejada de la central nuclear de Almaraz

    Energy Technology Data Exchange (ETDEWEB)

    Baeza, A.; Garcia, E.; Riesgo, R.; Rodriguez, A.; Guillen, J.

    2013-07-01

    The main objective of this work has been to study for two years the incorporation of 3H atmospheric from rainwater to several species of fungi collected in two ecosystems, one in the vicinity of the Almaraz Nuclear Power Plant and one away from it. (Author)

  5. BORILAIN. Mobile device for automatic continuous supply of liquid injection system backup of a nuclear plant in emergency; BORILAIN. Dispositivo movil para el abastecimiento automatico en continuo del sistema de inyeccion del liquido de reserva de una central nuclear en situacion de emergencia

    Energy Technology Data Exchange (ETDEWEB)

    Lacalle, J.; Traino, J.; Troeung, J.; Arnaldos, A.; Alcaraz, D. A.; Lopez, B.; Ponce, A. T.

    2014-07-01

    This paper presents the design and development of the first automatic mobile device for the preparation of a neutron absorbing solution, and providing continuous, 30 days, of the injection system liquid reserve of a nuclear emergency. The work has been developed by GD Energy Services (GDES) for Electricite de France (EDF). (Author)

  6. Modernization of the Electric Power Systems (transformers, rods and switches) in the Laguna Verde Nuclear Power Plant (Mexico); Modernizacion de los Sistemas Electricos de Potencia (Transformadores de Principales, Interruptor de Generacion, Barras de Fase Aislada) de la Central Nuclear de Laguna Verde (Mexico)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Solarzano, J. J.; Gabaldon Martin, M. A.; Pallisa Nunez, J.; Florez Ordeonez, A.; Fernandez Corbeira, A.; Prieto Diez, I.

    2010-07-01

    Description of the changes made in the Electric Power Systems as a part of the power increase project in the Laguna Verde Nuclear Power Plant (Mexico). The main electrical changes to make, besides the turbo group, are the main generation transformers, the isolated rods and the generation switch.

  7. Central Bank independence

    OpenAIRE

    Vasile DEDU; Tiberiu STOICA

    2012-01-01

    In this paper we present the key aspects regarding central bank’s independence. Most economists consider that the factor which positively influences the efficiency of monetary policy measures is the high independence of the central bank. We determined that the National Bank of Romania (NBR) has a high degree of independence. NBR has both goal and instrument independence. We also consider that the hike of NBR’s independence played an important role in the significant disin...

  8. EMT Central Offices

    OpenAIRE

    Campo Baeza, Alberto

    2001-01-01

    The brief was the construction of the Central Headquarters of the Municipal Transportation Company of Madrid (EMT) on a site edged by the train lines, near the Atocha train station. = Se trataba de la construcción de la sede central de la empresa EMT de Madrid, en un solar junto a las vías del tren cerca de la estación de Atocha.

  9. Centralization and political accountability

    OpenAIRE

    Hindriks, Jean; Lockwood, Ben

    2004-01-01

    In this paper we abstract from the usual gains and costs of decentralization (e.g. preference matching, spillovers and economies of scale). Instead we compare the political accountability of decentralized governments relative to centralized ones when there is a risk of "bad" governance. We study both the selection and incentive effects of accountability. A key aspect of centralization is to make the politician answerable to multiple constituencies subject to a common budget constraint. Our ma...

  10. SOCRATES Invades Central Europe

    OpenAIRE

    Joseph Slowinski

    1998-01-01

    The objective of this article is to explore the current reality faced by higher education students in Central and Eastern Europe and to draw out the implications of this current reality for policy makers in the future. In the article, I explore the influence of transnational corporations' training programs on education as it currently pertains to Central and Eastern European higher education and employment. In addition, multinational corporate entities exercise influence on European Union pol...

  11. Outsourcing central banking

    OpenAIRE

    Khoury, Sarkis Joseph; Wihlborg , Clas

    2005-01-01

    The literature on Currency Boards (CB) stops at the water edge in terms of dealing with the totality of the functions of a central bank. Monetary policy, and banking supervision can be "outsourced" in an open economy with substantial foreign direct investment (FDI) in the banking sector if political nationalism does not trump economic rationality. An orthodox CB renders the central banking function redundant in terms of interest rate and exchange rate determination. FDI in banking could...

  12. Nuclear structure

    International Nuclear Information System (INIS)

    The paper on 'nuclear structure' is the Appendix to the Daresbury (United Kingdom) Annual Report 1985/86, and contains the research work carried out at the Nuclear Structure Facility, Daresbury, within that period. During the year a total of 74 experiments were scheduled covering the main areas of activity including: nuclear collective motion, nuclei far from stability, and nuclear collisions. The Appendix contains brief reports on these experiments and associated theory. (U.K.)

  13. Nuclear power in the developing countries

    International Nuclear Information System (INIS)

    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.)

  14. Nuclear energy

    International Nuclear Information System (INIS)

    An overview about the evolution of nuclear energy for the next 25 years is presented. Several types of nuclear power reactors are described and the power installed up to year 2000 are discussed. Some processes of nuclear fuel enrichment used in the world are shown. (E.G.)

  15. Nuclear structure

    CERN Document Server

    Nazarewicz, W

    1999-01-01

    Current developments in nuclear structure are discussed from a theoretical perspective. The studies of the nuclear many-body system provide us with invaluable information about the nature of the nuclear interaction, nucleonic correlations at various energy-distance scales, and the modes of the nucleonic matter.

  16. Nuclear Ambitions

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    China will begin to build the world’s first third-generation nuclear power plant at the Sanmen Nuclear Power Project in Sanmen City, coastal Zhejiang Province, in March 2009, accord-ing to the State Nuclear Power Technology Corp.

  17. Nuclear weapons, nuclear effects, nuclear war

    Energy Technology Data Exchange (ETDEWEB)

    Bing, G.F.

    1991-08-20

    This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

  18. Modeling of delayed strains of concrete under biaxial loadings. Application to the reactor containment of nuclear power plants; Modelisation des deformations differees du beton sous sollicitations biaxiales. application aux enceintes de confinement de batiments reacteurs des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Benboudjema, F

    2002-12-15

    The prediction of delayed strains is of crucial importance for durability and long-term serviceability of concrete structures (bridges, containment vessels of nuclear power plants, etc.). Indeed, creep and shrinkage cause cracking, losses of pre-stress and redistribution of stresses, and also, rarely, the ruin of the structure. The objective of this work is to develop numerical tools, able to predict the long-term behavior of concrete structures. Thus, a new hydro mechanical model is developed, including the description of drying, shrinkage, creep and cracking phenomena for concrete as a non-saturated porous medium. The modeling of drying shrinkage is based on an unified approach of creep and shrinkage. Basic and drying creep models are based on relevant chemo-physical mechanisms, which occur at different scales of the cement paste. The basic creep is explicitly related to the micro-diffusion of the adsorbed water between inter-hydrates and intra-hydrates and the capillary pores, and the sliding of the C-S-H gel at the nano-porosity level. The drying creep is induced by the micro-diffusion of the adsorbed water at different scales of the porosity, under the simultaneous effects of drying and mechanical loadings. Drying shrinkage is, therefore, assumed to result from the elastic and delayed response of the solid skeleton, submitted to both capillary and disjoining pressures. Furthermore, the cracking behavior of concrete is described by an orthotropic elastoplastic damage model. The coupling between all these phenomena is performed by using effective stresses which account for both external applied stresses and pore pressures. This model has been incorporated into a finite element code. The analysis of the long-term behavior is also performed on concrete specimens and prestressed concrete structures submitted to simultaneous drying and mechanical loadings. (author)

  19. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  20. Micro-pollutant exchanges at the water-bryophyta interface: monitoring of the copper concentration in nuclear power plants; Echanges de micropolluants a l`interface eau-bryophytes: suivi de la concentration en cuivre dans les centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ciffroy, P.

    1994-12-31

    The purpose of this study is to calibrate and validate a descriptive model of the copper exchanges at the water-bryophyta interface. In theory, this model should allow calculation of the average concentrations of copper dissolved in water, using spot measurements on the bryophyta. The calibration procedure, based on mathematical use of laboratory data, demonstrated that the kinetic coefficients representing the processes of accumulation and release of the micro-pollutant by aquatic mosses, are effectively independent of the copper concentration in the water in contact with these latter, and that the reactional diagram proposed is thus well suited to representing exchanges at the water-bryophyta interface. The data collected during monitoring of the metal flows emitted by the nuclear power plants at Cattenom, Dampierre and Nogent/Seine enabled the validity of the model to be tested over a relatively large range of concentrations. The results obtained on the Cattenom and Dampierre sites would appear to be satisfactory: over the majority of control points selected, we noted good correlation between the measured and calculated concentrations of copper dissolved in water. In particular, the simulations run on periods of from 7 to 10 days show that the method is well suited to medium-term monitoring. On the other hand, the model proved inadequate for interpreting the measurements acquired during monitoring of releases from the Nogent/Seine plant set up for winter conditions. Consequently the dissolved copper estimates, calculated according to the model, considerably overestimate the actual values measured by atomic and absorption spectrometry and by voltametry. It would seem that these results can be attributed to a particular speciation of the copper on the site studied. Subsequent studies would seem necessary to confirm this point. (author). 5 refs., 10 figs., 10 tabs.

  1. Nuclear electric power and the proliferation of nuclear weapon states

    International Nuclear Information System (INIS)

    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

  2. Australia's nuclear graveyard

    International Nuclear Information System (INIS)

    Britain and Australia have become locked in a battle of wills and wits over a nuclear legacy that is now more than 30 years old. At stake is the issue of who will pay to clean up a stretch of the central Australian outback where at least 23 kilograms of plutonium are buried in nuclear graveyards or scattered in fine particles on the ground. The plutonium was left there after a series of British nuclear weapons tests in the 1950s and 1960s. The cost of cleaning it up today, and rendering the ground safe the the Aborigines who claim it as their tribal homeland, has been estimated at up to $158 million. Australia's minister for resources, Senator Gareth Evans, went to London in October 1986 to try to involve the British in the cleanup. But Britain is still taking the stand that it had discharged any obligations on this score long ago. This question is at the heart of controversy that began mounting in the late 1970s over the British nuclear tests. It was then that Aborigines and test veterans from Britain and Australia started alleging that they had been exposed to unduly high doses of radiation. Clearly, the nuclear tests, which began as a political exercise between Britain and Australia more than 30 years ago, seem destined to remain the source of much legal, diplomatic, and financial fallout between the two countries for a long time to come

  3. Movies about nuclear disasters

    International Nuclear Information System (INIS)

    '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.)

  4. Nuclear insurance

    International Nuclear Information System (INIS)

    The annual report presents among other things the figures of the nuclear insurance line. The Association of Nuclear Insurers in the F.R.G., the DKVG, counts more than 100 member companies in the year 1989, who offer reinsurance protection for West German nuclear power stations up to DM 1.5 billions in the property insurance sector, and up to DM 200 millions in the nuclear liability sector. The inland portfolio of the DKVG' covers 22 nuclear power stations. The expenses to satisfy claims in 1988 amounted to DM 9 millions. (HP)

  5. Nuclear energy

    International Nuclear Information System (INIS)

    This digest document was written by members of the union of associations of ex-members and retired people of the Areva group (UARGA). It gives a comprehensive overview of the nuclear industry world, starting from radioactivity and its applications, and going on with the fuel cycle (front-end, back-end, fuel reprocessing, transports), the nuclear reactors (PWR, BWR, Candu, HTR, generation 4 systems), the effluents from nuclear facilities, the nuclear wastes (processing, disposal), and the management and safety of nuclear activities. (J.S.)

  6. Perspectives in high energy nuclear collisions

    International Nuclear Information System (INIS)

    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.)

  7. Ongkharak nuclear research center in Thailand

    International Nuclear Information System (INIS)

    The project for the building of a new nuclear research center to be build in Thailand is discussed. The main facilities of this project are (1) a research reactor as the core of the Nuclear Research Center; (2) an isotope production facility; (3) a centralized waste processing and storage facility; (4) supporting facilities such as nuclear chemistry and physics laboratories, radiation protection buildings, construction and maintenance workshops, a computer center, administration and management buildings, cyclotron building

  8. Nuclear power

    International Nuclear Information System (INIS)

    The committee concludes that the nature of the proliferation problem is such that even stopping nuclear power completely could not stop proliferation completely. Countries can acquire nuclear weapons by means independent of commercial nuclear power. It is reasonable to suppose if a country is strongly motivated to acquire nuclear weapons, it will have them by 2010, or soon thereafter, no matter how nuclear power is managed in the meantime. Unilateral and international diplomatic measures to reduce the motivations that lead to proliferation should be high on the foreign policy agenda of the United States. A mimimum antiproliferation prescription for the management of nuclear power is to try to raise the political barriers against proliferation through misuse of nuclear power by strengthening the Non-Proliferation Treaty, and to seek to raise the technological barriers by placing fuel-cycle operations involving weapons-usable material under international control. Any such measures should be considered tactics to slow the spread of nuclear weapons and thus earn time for the exercise of statesmanship. The committee concludes the following about technical factors that should be considered in formulating nuclear policy: (1) rate of growth of electricity use is a primary factor; (2) growth of conventional nuclear power will be limited by producibility of domestic uranium sources; (3) greater contribution of nuclear power beyond 400 GWe past the year 2000 can only be supported by advanced reactor systems; and (4) several different breeder reactors could serve in principle as candidates for an indefinitely sustainable source of energy

  9. Nuclear physics

    International Nuclear Information System (INIS)

    Explains the concepts in detail and in depth. Provides step-by-step derivations. Contains numerous tables and diagrams. Supports learning and teaching with numerous worked examples, questions and problems with answers. Sketches also the historical development of the subject. This textbook explains the experimental basics, effects and theory of nuclear physics. It supports learning and teaching with numerous worked examples, questions and problems with answers. Numerous tables and diagrams help to better understand the explanations. A better feeling to the subject of the book is given with sketches about the historical development of nuclear physics. The main topics of this book include the phenomena associated with passage of charged particles and radiation through matter which are related to nuclear resonance fluorescence and the Moessbauer effect., Gamov's theory of alpha decay, Fermi theory of beta decay, electron capture and gamma decay. The discussion of general properties of nuclei covers nuclear sizes and nuclear force, nuclear spin, magnetic dipole moment and electric quadrupole moment. Nuclear instability against various modes of decay and Yukawa theory are explained. Nuclear models such as Fermi Gas Model, Shell Model, Liquid Drop Model, Collective Model and Optical Model are outlined to explain various experimental facts related to nuclear structure. Heavy ion reactions, including nuclear fusion, are explained. Nuclear fission and fusion power production is treated elaborately.

  10. Nuclear forensics

    International Nuclear Information System (INIS)

    This review discusses the methodology of nuclear forensics and illicit trafficking of nuclear materials. Nuclear forensics is relatively new scientific branch whose aim it is to read out material inherent from nuclear material. Nuclear forensics investigations have to be considered as part of a comprehensive set of measures for detection,interception, categorization and characterization of illicitly trafficking nuclear material. Prevention, detection and response are the main elements in combating illicit trafficking. Forensics is a key element in the response process. Forensic science is defined as the application of a broad spectrum of sciences to answer questions of interest to the legal system. Besides, in this study we will explain age determination of nuclear materials.

  11. Polarographic determination of Iodide and Iodate, in Solutions Coming from Aerosols in Fission Products Containment Studies in Nuclear Power Stations; Determinacion Polarografica de Especies de Iodo (Ioduro y Iodato) en Soluciones Procedentes de Aerosoles, para Estudios de Contencion de Productos de Fision en Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, M.; Ballesteros, O.; Fernandez, M.; Clavero, M.; Gonzalez, A. M. [Ciemat, Madrid (Spain)

    2000-07-01

    A polarographic method is described for the iodine species determination, iodide and iodate in water solutions. the iodate can be determined by differential pulse polarography. Calibration curves and the detection and determination limits have been obtained. Iodides is oxidized to iodate with sodium hypochlorite and the excess of oxidizing agent is destroyed with sodium sulphide. The concentration of iodide is calculated as the difference between the concentration of iodate in the sample before and after the oxidation. As an application, species of iodine in samples coming from the experimental plants GIRS (Gaseous Iodine Removal by Sprays) of Nuclear Fission Department of the CIEMAT, dedicated to fission products containment studies in nuclear power station, were determined. (Author) 10 refs.

  12. CENTRAL PLATEAU REMEDIATION

    Energy Technology Data Exchange (ETDEWEB)

    ROMINE, L.D.

    2006-02-01

    A systematic approach to closure planning is being implemented at the Hanford Site's Central Plateau to help achieve the goal of closure by the year 2035. The overall objective of Central Plateau remediation is to protect human health and the environment from the significant quantity of contaminated material that resulted from decades of plutonium production in support of the nation's defense. This goal will be achieved either by removing contaminants or placing the residual contaminated materials in a secure configuration that minimizes further migration to the groundwater and reduces the potential for inadvertent intrusion into contaminated sites. The approach to Central Plateau cleanup used three key concepts--closure zones, closure elements, and closure process steps--to create an organized picture of actions required to complete remediation. These actions were merged with logic ties, constraints, and required resources to produce an integrated time-phased schedule and cost profile for Central Plateau closure. Programmatic risks associated with implementation of Central Plateau closure were identified and analyzed. Actions to mitigate the most significant risks are underway while high priority remediation projects continue to make progress.

  13. CENTRAL PLATEAU REMEDIATION

    International Nuclear Information System (INIS)

    A systematic approach to closure planning is being implemented at the Hanford Site's Central Plateau to help achieve the goal of closure by the year 2035. The overall objective of Central Plateau remediation is to protect human health and the environment from the significant quantity of contaminated material that resulted from decades of plutonium production in support of the nation's defense. This goal will be achieved either by removing contaminants or placing the residual contaminated materials in a secure configuration that minimizes further migration to the groundwater and reduces the potential for inadvertent intrusion into contaminated sites. The approach to Central Plateau cleanup used three key concepts--closure zones, closure elements, and closure process steps--to create an organized picture of actions required to complete remediation. These actions were merged with logic ties, constraints, and required resources to produce an integrated time-phased schedule and cost profile for Central Plateau closure. Programmatic risks associated with implementation of Central Plateau closure were identified and analyzed. Actions to mitigate the most significant risks are underway while high priority remediation projects continue to make progress

  14. Application of cybernetic models in the study of safety and economics of nuclear power systems and other high risk organizations: A study of nuclear power and high risk organizations to understand the central role of management in the safety and economics of these operations

    OpenAIRE

    Spurgin, Anthony

    2013-01-01

    The safety and economics of nuclear utilities and High Risk Operations (HROs) is very dependent on the quality of both the management and operations personnel. The decisionmaking capability of management is important in ensuring that the operators are adequately prepared to deal effectively with accidents. This means that management has to understand the risk of power production and adequately deal with it, so that the viability of the utility is not compromised, while still operating in an e...

  15. Nuclear law and disorder

    International Nuclear Information System (INIS)

    debate. This strategy was rewarded when eight NATO States - Belgium, Canada, Germany, Lithuania, Luxembourg, The Netherlands, Norway and Turkey - voted for the resolution. The priorities for action would not be difficult to achieve provided the nuclear-weapons States cooperate on: early entry-into-force of the Comprehensive Test Ban Treaty; reduction of non-strategic nuclear weapons and non-development of new types of nuclear weapons; negotiation of an effectively verifiable fissile material cut-off treaty; establishment of a subsidiary body to deal with nuclear weapons at the Conference on Disarmament; and compliance with the principles of irreversibility and transparency and development of verification capabilities. A new common front may yet be able to inject new life into the only worldwide legal instrument we have to stop the spread of nuclear weapons.But it is precisely this co-operation, or rather lack of it, between the nuclear haves and have nots that is the central issue. There has been little co-operation in the 35-year history of the NPT. Will the recognition of new dangers finally jolt governments into action? Much will now depend on the actions taken by the re-elected Bush Administration in the US. It seems to me that the only way to stop the NPT erosion is for a new burst of energy to be shown by the middle power States - the New Agenda, non-nuclear NATO, the European Union and a few other like-minded States - to shore up and influence the centre positions in the nuclear weapons debate. Even though India, Pakistan and Israel continue to shun the NPT, it is also in the interests of these countries to cooperate in implementing the New Agenda's list of priorities. Can we expect this burst of energy if parliamentarians and the public remain docile? A new common front of an awakened civil society and caring middle power States may yet be able to inject new life into the only worldwide legal instrument we have to stop the spread of nuclear weapons

  16. Calculation of the pipes failure probability of the Rcic system of a nuclear power station by means of software WinPRAISE 07; Calculo de la probabilidad de falla de tuberias del sistema RCIC de una central nuclear mediante el software WinPRAISE 07

    Energy Technology Data Exchange (ETDEWEB)

    Jasso G, J.; Diaz S, A.; Mendoza G, G.; Sainz M, E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Garcia de la C, F. M., E-mail: angeles.diaz@inin.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    The growth and the cracks propagation by fatigue are a typical degradation mechanism that is presented in the nuclear industry as in the conventional industry; the unstable propagation of a crack can cause the catastrophic failure of a metallic component even with high ductility; for this reason, activities of programmed maintenance have been established in the industry using inspection and visual techniques and/or ultrasound with an established periodicity allowing to follow up to these growths, controlling the undesirable effects; however, these activities increase the operation costs; and in the peculiar case of the nuclear industry, they increase the radiation exposure to the participant personnel. The use of mathematical processes that integrate concepts of uncertainty, material properties and the probability associated to the inspection results, has been constituted as a powerful tool of evaluation of the component reliability, reducing costs and exposure levels. In this work the evaluation of the failure probability by cracks growth preexisting by fatigue is presented, in pipes of a Reactor Core Isolation Cooling system (Rcic) in a nuclear power station. The software WinPRAISE 07 (Piping Reliability Analysis Including Seismic Events) was used supported in the probabilistic fracture mechanics principles. The obtained values of failure probability evidenced a good behavior of the analyzed pipes with a maximum order of 1.0 E-6, therefore is concluded that the performance of the lines of these pipes is reliable even extrapolating the calculations at 10, 20, 30 and 40 years of service. (Author)

  17. Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants; Interfase visual para la automatizacion del pendulo instrumentado de pruebas Charpy utilizado en el programa de vigilancia de la vasija de reactores de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A. [ININ, Carretera Mexico-Toluca Km.36.5, Mpio. de Ocoyoacac, Estado de Mexico (Mexico)]. E-mail: asrs@nuclear.inin.mx; esm@nuclear.inin.mx; jare@nuclear.inin.mx

    2004-07-01

    Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)

  18. Colloquium on Central Asia

    International Nuclear Information System (INIS)

    This colloquium on Azerbaijan was organized by the direction of international relations of the French Senate and the French center of foreign trade (CFCE). This document gathers the interventions of the participants and the debates with the audience following these interventions. The topics treated concern: - the present day political-economical situation of Central Asia countries (problem of borders, relations with Russia and China); - the economies of Central Asia countries: short term problems and medium-term perspectives; - the relations with the European Union (political, economical, trade and investments, perspectives); - the European energy stakes of Caspian sea (oil and gas reserves, development of hydrocarbon resources, exploitation and transport constraints, stakes for Europe and France); - TotalFinaElf company in Central Asia (Kazakhstan, Azerbaijan, enclavement problem); - the economical impacts of the TRACECA pathway (Transport Corridor Europe Caucasus Asia). (J.S.)

  19. The Naive Central Banker

    Directory of Open Access Journals (Sweden)

    Marcelo de Carvalho Griebeler

    2015-09-01

    Full Text Available There has been in some countries a trend of assigning other functions to central banks besides price stability. The most suggested function to be added to monetary authority’s obligations is to pursue economic growth or full employment. In this paper we characterize the behavior and analyse the optimal monetary policy of, what we call, a naive central banker. We describe the naive behavior as one that does face the inflation-unemployment trade-off, but it tries to minimize both variables simultaneously. Our findings, both under discretion and commitment, indicate that the naive central banker delivers lower expected inflation and inflation variance than the benchmark behavior whenever the economy is rigid enough. However, the degree of conservativeness also affects this result, such that the less conservative the naive policymaker, the more rigidity is necessary.

  20. SOCRATES Invades Central Europe

    Directory of Open Access Journals (Sweden)

    Joseph Slowinski

    1998-04-01

    Full Text Available The objective of this article is to explore the current reality faced by higher education students in Central and Eastern Europe and to draw out the implications of this current reality for policy makers in the future. In the article, I explore the influence of transnational corporations' training programs on education as it currently pertains to Central and Eastern European higher education and employment. In addition, multinational corporate entities exercise influence on European Union policy through the role of lobby organizations and activities. I explore the influence of these practices on education with an emphasis on the emerging importance of Western language skills. In addition, I focus on the European Union and its efforts to expand into Central and Eastern Europe in order to provide a focal point for analysis.

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

    International Nuclear Information System (INIS)

    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)

  2. Nuclear energy and nuclear weapons

    International Nuclear Information System (INIS)

    We all want to prevent the use of nuclear weapons. The issue before us is how best to achieve this objective; more specifically, whether the peaceful applications of nuclear energy help or hinder, and to what extent. Many of us in the nuclear industry are working on these applications from a conviction that without peaceful nuclear energy the risk of nuclear war would be appreciably greater. Others, however, hold the opposite view. In discussing the subject, a necessary step in allaying fears is understanding some facts, and indeed facing up to some unpalatable facts. When the facts are assessed, and a balance struck, the conclusion is that peaceful nuclear energy is much more part of the solution to preventing nuclear war than it is part of the problem

  3. 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…

  4. Centralization and decentralization in energy systems and associated risks

    International Nuclear Information System (INIS)

    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

  5. ORIC central region calculations

    International Nuclear Information System (INIS)

    The central region for the K = 100 Oak Ridge Isochronous Cyclotron, ORIC, will be modified to provide better orbit centering, focusing of orbits in the axial direction, and phase selection, in order to improve extraction efficiency, and reduce radioactive activation of cyclotron components. The central region is specifically designed for the acceleration of intense light ion beams such as 60 MeV protons and 15--100 MeV alphas. These beams will be used in the production of radioactive atoms in the Radioactive Ion Beam Project at Oak Ridge National Laboratory

  6. Hale Central Peak

    Science.gov (United States)

    2004-01-01

    19 September 2004 This Mars Global Surveyor (MGS) Mars Orbiter Camera (MOC) image shows some of the mountains that make up the central peak region of Hale Crater, located near 35.8oS, 36.5oW. Dark, smooth-surfaced sand dunes are seen to be climbing up the mountainous slopes. The central peak of a crater consists of rock brought up during the impact from below the crater floor. This autumn image is illuminated from the upper left and covers an area approximately 3 km (1.9 mi) across.

  7. Workers doses in central European PWR NPPs

    International Nuclear Information System (INIS)

    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)

  8. Panel report: nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Joseph A [Los Alamos National Laboratory; Hartouni, Edward P [LLNL

    2010-01-01

    Nuclear science is at the very heart of the NNSA program. The energy produced by nuclear processes is central to the NNSA mission, and nuclear reactions are critical in many applications, including National Ignition Facility (NIF) capsules, energy production, weapons, and in global threat reduction. Nuclear reactions are the source of energy in all these applications, and they can also be crucial in understanding and diagnosing the complex high-energy environments integral to the work of the NNSA. Nuclear processes are complex quantum many-body problems. Modeling and simulation of nuclear reactions and their role in applications, coupled tightly with experiments, have played a key role in NNSA's mission. The science input to NNSA program applications has been heavily reliant on experiment combined with extrapolations and physical models 'just good enough' to provide a starting point to extensive engineering that generated a body of empirical information. This body of information lacks the basic science underpinnings necessary to provide reliable extrapolations beyond the domain in which it was produced and for providing quantifiable error bars. Further, the ability to perform additional engineering tests is no longer possible, especially those tests that produce data in the extreme environments that uniquely characterize these applications. The end of testing has required improvements to the predictive capabilities of codes simulating the reactions and associated applications for both well known and well characterized cases as well as incompletely known cases. Developments in high performance computing, computational physics, applied mathematics and nuclear theory have combined to make spectacular advances in the theory of fission, fusion and nuclear reactions. Current research exploits these developments in a number of Office of Science and NNSA programs, and in joint programs such as the SciDAC (Science Discovery through Advanced Computing) that

  9. The Sombrero Galaxy III Ionised gas and dust in the central 200 pc

    CERN Document Server

    Emsellem, E; Emsellem, Eric; Ferruit, Pierre

    2000-01-01

    We present the results of new 3D TIGER spectroscopic observations and archived HST/WFPC2 and NICMOS images of the central region of M 104. The [NII]+Ha images reveal the presence of a nuclear spiral structure, and the gaseous kinematics in the central arcsecond shows evidence for kinematical decoupling of the central peak. A straight nuclear dust lane, with a weak symmetric counterpart, is seen in the V-I and V-H colour maps. These results hint for the presence of a strong nuclear bar, that would be located inside the inner Linblad resonance of the large-scale bar discussed by Emsellem (1995).

  10. Nuclear power

    International Nuclear Information System (INIS)

    Nuclear power has been seen as an answer to the energy problems of the Third World and Third World markets have been seen as an answer to the problems of the nuclear power industry. For some years during the 1970s both views seemed tenable. This paper examines the progress and setbacks of nuclear power in developing countries. In concentrates mainly on the four countries with real nuclear power commitments (as opposed to all-but-abandoned ambitions) - South Korea and Taiwan, where the interest has been mainly in obtaining cheaper and reliable electricity supplies, and Argentina and India, where the main interest has been in developing indigenous nuclear technological capabilities. A number of possibilities are examined which could influence future nuclear ordering, including smaller reactors to suit Third World electricity grids and a possible way round the constraint of large external debts. (author)

  11. Nuclear power

    International Nuclear Information System (INIS)

    This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

  12. The central government power generating capacity- reforms and the future

    International Nuclear Information System (INIS)

    The alarming resource gap that the states were facing in 1970's has prompted the Central Government to augment the resources for power generation by creating two new entities in November 1975 viz the National Thermal Power Corporation (NTPC) and National Hydro Power Corporation (NHPC). Few other organisations also exist in central sector which are engaged in power generation like Nuclear Power Corporation (NPC). NTPC being the leading player in the power sector, it can neither be indifferent nor dissociate itself from the reforms sweeping the sector today. The article describes the Central Government's role in power generation, reforms and NTPC and further prospects of NTPC

  13. Nuclear Speckles

    OpenAIRE

    Spector, David L.; Lamond, Angus I.

    2011-01-01

    Nuclear speckles, also known as interchromatin granule clusters, are nuclear domains enriched in pre-mRNA splicing factors, located in the interchromatin regions of the nucleoplasm of mammalian cells. When observed by immunofluorescence microscopy, they usually appear as 20–50 irregularly shaped structures that vary in size. Speckles are dynamic structures, and their constituents can exchange continuously with the nucleoplasm and other nuclear locations, including active transcription sites. ...

  14. Nuclear Astrophysics

    OpenAIRE

    Brune, Carl R.

    2005-01-01

    Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier ...

  15. Nuclear Reactions

    OpenAIRE

    Bertulani, C. A.

    2009-01-01

    Nuclear reactions generate energy in nuclear reactors, in stars, and are responsible for the existence of all elements heavier than hydrogen in the universe. Nuclear reactions denote reactions between nuclei, and between nuclei and other fundamental particles, such as electrons and photons. A short description of the conservation laws and the definition of basic physical quantities is presented, followed by a more detailed account of specific cases: (a) formation and decay of compound nuclei;...

  16. Nuclear APC.

    Science.gov (United States)

    Neufeld, Kristi L

    2009-01-01

    Mutational inactivation of the tumor suppressor gene APC (Adenomatous polyposis coli) is thought to be an initiating step in the progression of the vast majority ofcolorectal cancers. Attempts to understand APC function have revealed more than a dozen binding partners as well as several subcellular localizations including at cell-cell junctions, associated with microtubules at the leading edge of migrating cells, at the apical membrane, in the cytoplasm and in the nucleus. The present chapter focuses on APC localization and functions in the nucleus. APC contains two classical nuclear localization signals, with a third domain that can enhance nuclear import. Along with two sets of nuclear export signals, the nuclear localization signals enable the large APC protein to shuttle between the nucleus and cytoplasm. Nuclear APC can oppose beta-catenin-mediated transcription. This down-regulation of nuclear beta-catenin activity by APC most likely involves nuclear sequestration of beta-catenin from the transcription complex as well as interaction of APC with transcription corepressor CtBP. Additional nuclear binding partners for APC include transcription factor activator protein AP-2alpha, nuclear export factor Crm1, protein tyrosine phosphatase PTP-BL and perhaps DNA itself. Interaction of APC with polymerase beta and PCNA, suggests a role for APC in DNA repair. The observation that increases in the cytoplasmic distribution of APC correlate with colon cancer progression suggests that disruption of these nuclear functions of APC plays an important role in cancer progression. APC prevalence in the cytoplasm of quiescent cells points to a potential function for nuclear APC in control of cell proliferation. Clear definition of APC's nuclear function(s) will expand the possibilities for early colorectal cancer diagnostics and therapeutics targeted to APC. PMID:19928349

  17. Nuclear astrophysics

    International Nuclear Information System (INIS)

    The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized

  18. Channeling the Central Dogma.

    Science.gov (United States)

    Calabrese, Ronald L

    2014-05-21

    How do neurons and networks achieve their characteristic electrical activity, regulate this activity homeostatically, and yet show population variability in expression? In this issue of Neuron, O'Leary et al. (2014) address some of these thorny questions in this theoretical analysis that starts with the Central Dogma. PMID:24853932

  19. Central Dogma Goes Digital.

    Science.gov (United States)

    Lin, Yihan; Elowitz, Michael B

    2016-03-17

    In this issue of Molecular Cell, Tay and colleagues (Albayrak et al., 2016) describe a new technique to digitally quantify the numbers of protein and mRNA in the same mammalian cell, providing a new way to look at the central dogma of molecular biology. PMID:26990983

  20. Central areolar choroidal dystrophy.

    NARCIS (Netherlands)

    Boon, C.J.F.; Klevering, B.J.; Cremers, F.P.M.; Zonneveld-Vrieling, M.N.; Theelen, T.; Hollander, A.I. den; Hoyng, C.B.

    2009-01-01

    OBJECTIVE: To describe the clinical characteristics, follow-up data and molecular genetic background in a large group of patients with central areolar choroidal dystrophy (CACD). DESIGN: Retrospective case series study. PARTICIPANTS: One hundred three patients with CACD from the Netherlands. METHODS

  1. [Central manifestations of dystrophinopathies].

    Science.gov (United States)

    Cuisset, J-M; Rivier, F

    2015-12-01

    The dystrophin gene involved in Duchenne and Becker muscular dystrophy is expressed in three main tissues resulting in clinical manifestations: skeletal muscle, heart and central nervous system. The 6 different existing dystrophins in the brain may play a role in the maturation and plasticity of neuronal synapses in particular by their functions in clustering and stabilization of different receptors at the post synaptic membrane. The possibility of an intellectual deficiency in Duchenne muscular dystrophy is known from the original description by Duchenne himself. Current data are in line with a constant cognitive impairment with a Gaussian curve shifted intellectual quotient (IQ) at -1 standard deviation from the standard population with an average IQ around 80. Clinical manifestations suggestive of a central nervous system involvement can affect all dystrophinopathies, including isolated central presentations without myopathic sign. The phenotypic spectrum appears broader and more subtle than non specific intellectual deficiency. The isolated or shared involvement of specific cognitive functions is possible (memory functions, executive functions, attention) with or without intellectual deficiency. Autism spectrum disorders are also among the encountered events. In clinical practice, it seems worth to ask for a measurement of serum creatine kinase (CK) in these different situations, keeping in mind that pure forms of central dystrophinopathies with a normal CK level have been recently reported. PMID:26773588

  2. Retiring the central executive.

    Science.gov (United States)

    Logie, Robert H

    2016-10-01

    Reasoning, problem solving, comprehension, learning and retrieval, inhibition, switching, updating, or multitasking are often referred to as higher cognition, thought to require control processes or the use of a central executive. However, the concept of an executive controller begs the question of what is controlling the controller and so on, leading to an infinite hierarchy of executives or "homunculi". In what is now a QJEP citation classic, Baddeley [Baddeley, A. D. (1996). Exploring the central executive. Quarterly Journal of Experimental Psychology, 49A, 5-28] referred to the concept of a central executive in cognition as a "conceptual ragbag" that acted as a placeholder umbrella term for aspects of cognition that are complex, were poorly understood at the time, and most likely involve several different cognitive functions working in concert. He suggested that with systematic empirical research, advances in understanding might progress sufficiently to allow the executive concept to be "sacked". This article offers an overview of the 1996 article and of some subsequent systematic research and argues that after two decades of research, there is sufficient advance in understanding to suggest that executive control might arise from the interaction among multiple different functions in cognition that use different, but overlapping, brain networks. The article concludes that the central executive concept might now be offered a dignified retirement. PMID:26821744

  3. Centralizers of spin subalgebras

    Science.gov (United States)

    Arizmendi, Gerardo; Herrera, Rafael

    2015-11-01

    We determine the centralizers of certain isomorphic copies of spin subalgebras spin(r) in so(dr m), where dr is the dimension of a real irreducible representation of Clr0, the even Clifford algebra determined by the positive definite inner product on Rr, where r, m ∈ N.

  4. Outsourcing central banking

    DEFF Research Database (Denmark)

    Khoury, Sarkis Joseph; Wihlborg, Clas

    2005-01-01

    The literature on Currency Boards (CB) stops at the water edge in terms of dealing with the totality of the functions of a central bank. Monetary policy, and banking supervisioncan be "outsourced" in an open economy with substantial foreign direct investment (FDI)in the banking sector if politica...

  5. Nuclear Law

    International Nuclear Information System (INIS)

    This book on nuclear law is the first of a series of analytical studies to be published by the French Energy Commission (CEA) concerning all the various nuclear activities. It describes national and international legislation applicable in France covering the following main sectors: the licensing procedure for nuclear installations, the law of the sea and nuclear law, the legal system governing radioisotopes, the transport of radioactive materials, third party liability and insurance and radiation protection. In each chapter, the overall analysis is supplemented by the relevant regulatory texts and by organisation charts in annex. (NEA)

  6. Nuclear safeguards and export controls

    International Nuclear Information System (INIS)

    Precisely from the perspective of the two most important nonnuclear weapons states, Japan and Germany, the safeguards and arms control agendas have not been finally dealt with. Because of their central position in the nonproliferation regime as nuclear suppliers and states with large nuclear energy industries, both countries are compelled to take a leading role in pursuing future reforms. In the dialogue with the nonaligned, this leadership position is helped by their nonnuclear status. In fact, Japan and Germany have some interests in common with the nonaligned states, such as the expansion of safeguards in the nuclear weapons states. To be sure, both Japan and Germany will pursue such interests with due regard to the interests of their friends and allies. For Japan, maintaining a close relationship with the United States is as important as shaping viable relations with China. Initiatives and controversies on nuclear policy must be weighed against this interest. By the same token, Germany must take into account the dense network of relations with its allies and with Russia, in addition to the German-French friendship. This will always set limits to Germany's readiness to confront the nuclear weapons states on nuclear issues. This, however, does not mean that both countries must shut up when the P 5 speak. The nuclear weapons register and the extension of the ''erga omnes'' rule in export controls, for example, should not be relegated to the dustbin of history, just because some friendly nuclear powers don't like these ideas. (orig.)

  7. Nuclear industry and national security

    International Nuclear Information System (INIS)

    The central issue of the book is not nuclear power as such, but its effects on the country as a whole in terms of security and safety. The contributions to the book examine aspects of national security affected by nuclear power, and the measures taken to make nuclear power safe, with safety covering the engineering aspects, and security the social, economic, and legal aspects. Experts in their field explain the safety philosophies modified in the course of nuclear industry development, and how technological problems have been tackled. Physical protection of nuclear power plant is an aspect, and insurance for financial security another. Security problems in connection with nuclear weapons in the F.R.G. are discussed as well as the political dimension of nuclear power safety, which is explained by representatives of the parties in the Bundestag. The role of the general public in the democratic process of defining 'security' or 'safety', and security in the context of a constitutional state are further topics under investigation. The book gathers contributions from authors who are known for their advocating, oppositional, or sceptical attitude towards nuclear power. (orig./HSCH)

  8. Isospin in nuclear fragmentation

    Energy Technology Data Exchange (ETDEWEB)

    Baran, V. [Bucharest Univ., IFIN-HH (Romania); Baran, V.; Colonna, M.; Di Toro, M. [Catania Univ., Laboratori Nazionali del Sud, INFN (Italy)

    2003-07-01

    The isospin dynamics when we explore various reaction mechanisms at intermediate energies is discussed. We are concerned with its peculiarities in the nuclear liquid-gas phase transition, in mid-rapidity fragment formation for semi-central collisions as well as in the diffusion process in binary, peripheral reactions. The connection of these effects to the density dependence of symmetry energy is analyzed in detail. In this work we showed how various reaction mechanism at Fermi energies can provide complementary information about the density dependence of symmetry term of the nuclear equation of state. In these reactions several observables are sensitive to the isovector channel: i) isospin distillation in multifragmentation, ii) isospin content of neck fragments, iii) iso-scaling parameters, and iv) isospin content of PLF (projectile-like fragments) and TLF (target-like fragments) in peripheral reaction.

  9. Transportation of nuclear fuel

    International Nuclear Information System (INIS)

    Shipment of used fuel from nuclear reactors to a central fuel management facility is discussed with particular emphasis on the assessment of the risk to the public due to these shipments. The methods of transporting used fuel in large shipping containers is reviewed. In terms of an accident scenario, it is demonstrated that the primary risk of transport of used fuel is due to injury and death in common road accidents. The radiological nature of the used fuel cargo is, for all practical purposes, an insignificant factor in the total risk to the public. (author)

  10. Swedish nuclear waste efforts

    International Nuclear Information System (INIS)

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981

  11. Nuclear critics and nuclear economics

    International Nuclear Information System (INIS)

    The ongoing nuclear debate is given to attacks on the economics of nuclear power that ignore the actual performance of operating plants. Today, almost every existing nuclear power plant has provided significant savings to the customers it supplies. (The exceptions to this, while important, are not being hidden. Instead, the problem plants, Palisades and Browns Ferry in the main, as well as all our nuclear units, are being studied and carefully monitored with the view to improving performance. The fact remains that nuclear units ordered today are expected to provide more economical energy in almost all parts of the nation than any other available steam-electric alternative.) Despite extensive data to the contrary on file with regulatory commissions, both state and Federal, publications on nuclear power economics by adversary groups appear to have gained far more attention that the actual record. But, during 1977, nuclear generation accounted for about 12 percent of the nation's production of electricity, exceeding the output of hydroelectric power for the first time in history. For Northeast Utilities, where for the first nine months of 1977 63 percent of the electricity was nuclear, every nuclear kWh meant a direct reduction in imported oil. U.S. government figures for the first eight months of 1977 show that nuclear generation totaled 160 billion net kWh, equivalent to about 300 million barrels of oil, almost a million barrels per day. Obviously nuclear capacity that displaces that much oil is advantageous, both for the utility and for the nation. The U.S. could build a lot of generating capacity (nuclear and coal) and do a lot of research (solar, fusion, breeder reactors) with even a fraction of the $40 billion now going to the oil-exporting countries each year

  12. Central Safety Department, annual report 1987

    International Nuclear Information System (INIS)

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behaviour of biologically particularly active radionuclides, behaviour of HT in the air/plan/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 1987 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig./HP)

  13. Central Waste Complex (CWC) Waste Analysis Plan

    International Nuclear Information System (INIS)

    The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  14. The collapse of nuclear economics

    International Nuclear Information System (INIS)

    Nuclear power has failed to live up to the expectation that it could generate electricity more cheaply than other fuels. Subsidies and dubious accounting methods have been used to disguise the true cost of nuclear-generated electricity. The truth is shown to be that it is more expensive than the alternatives. In part this is because the long-term costs of decommissioning and waste disposal have not been included. Discounting procedures can also reduce the apparent costs. The distortions in economic evaluation brought about by discounting over long periods are illustrated and the effects on nuclear economics discussed. Indirect subsidies and inflation also make nuclear electricity look better than it really is but the Central Electricity Generating Board still had difficulties at the Sizewell-B Inquiry in making a good economic case. (U.K.)

  15. Nuclear power: tomorrow's energy source

    International Nuclear Information System (INIS)

    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)

  16. Nuclear installations

    International Nuclear Information System (INIS)

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  17. Nuclear violence

    International Nuclear Information System (INIS)

    A great deal of attention has been paid in the past decade or so to the characteristics of terrorists and their apparent goals and objectives, capabilities, and evolving strategy and tactics with respect to nuclear terrorism. In contrast, little has been said about the procedural aspects of nuclear terrorism, and even less about the way in which such endeavors can fail. This latter omission is important because it bears directly on the ability to evaluate credibly the potential for nuclear terrorism. Here, the author addresses the requirements inherent in acquiring a nuclear explosive capability by three routes: separation of plutonium from irradiated light or heavy water reactor (LWR or HWR) fuel, processing, or use of separated fissile material, and theft of a nuclear weapon. In addition, he deals with other potential acts of nuclear terrorism: sabotage of power reactors, uranium enrichment facilities and spent nuclear fuel in transport, and dispersal of radioactive materials, in particular, plutonium. He specifically does not look at the design or production of a nuclear weapon. Finally, the discussion here assumes that the terrorist is subnational; that is, a nation is not involved. Also, the discussion of subnational participation does not address the possibility of collusion with insiders

  18. Nuclear engineering introduction

    International Nuclear Information System (INIS)

    This book describes nuclear engineering introducing nuclear energy and its utilization, nuclear engineering basics, nuclear reactor and nuclear reaction, nuclear steam system, thermal output and reactor physics, transient reactor, radiation management, safety in nuclear power plant and nuclear economy. It explains the technical terms of nuclear engineering in detail.

  19. Nuclear stress test

    Science.gov (United States)

    ... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

  20. Nuclear measurements

    International Nuclear Information System (INIS)

    Nuclear measurements play a fundamental role in the development of nuclear technology and the assurance of its peaceful use. They are also required in many non-power nuclear applications such as in nuclear medicine, agriculture, environmental protection, etc. This presentation will show examples of most recent advances in measurement methodology or technology in the areas described below. The Generation IV International Forum has selected six innovative reactor systems as candidates for a next generation of sustainable, economic and safe nuclear energy systems. The choice of the best options relies heavily on the availability of accurate nuclear data that can only be obtained, in an international effort, using highly specialised facilities. Significant efforts are being directed towards the partitioning and transmutation of highly active nuclear waste. Different concepts involving fast reactors or accelerator-driven systems are being studied in view of their transmutation capabilities. State of the art equipment has been developed to assess basic properties of nuclear fuel at very high burn-up; some fine examples of this work will be shown. Physical and chemical methods play a crucial role in the detection and identification of radioisotopes used in various stages of the nuclear fuel cycle. Radiation measurement techniques are used, for example, to monitor the quantities of uranium, plutonium and other actinide elements in fuel enrichment and reprocessing facilities. Another field of application of physical and chemical methods is the characterisation of nuclear material seized from illicit trafficking. Seized material has to be analysed in order to obtain clues on its origin and intended use and to prevent diversion of nuclear material from the same source in the future. A recent highlight in basic physics relates to nuclear fission and transmutation with high intensity lasers. Ultra-fast high intensity lasers can produce high energy (tens of MeV) photons through