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Sample records for nuclear centrals etude

  1. 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

    'on decrit en discutant la validite des approximations choisies. 4. Les simulateurs de machines tournantes: on souligne le caractere particulier que presentent les calculs des machines tournantes en raison de la necessite ou l'on est de passer par l'intermediaire d'abaques. On propose l'utilisation d'une memoire a acces aleatoire permettant un traitement analogique de ces problemes. 5. Etude d'une centrale nucleaire: on etudie, sur un exemple, les problemes poses par l'interconnexion d'elements du type precedent pour la simulation de grands ensembles (centrales nucleaires) et on souligne le role des elements ordinaires de calcul. 6. Conclusion: on souligne la necessite pour toutes ces etudes, de disposer d'un materiel de qualite et on discute la signification des resultats ainsi obtenus. (auteur)

  2. Nuclear study of Melusine; Etude nucleaire de Melusine

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    In this report are reviewed - with respect to starting of experiments - the main nuclear characteristics of a 20 per cent enriched uranium lattice, with light water as moderator and reflector. The reactor is to operate at 1 MW. 1) Study of various critical masses. 2) Control. Effectiveness of cadmium. Control rods and of a stainless steel regulating rod. 3) Study of the effect on reactivity of disturbances in the core center. 4) Study of xenon and samarium poisoning. 5) Temperature factor. 6) Heat exchanges in a fuel element. (author) [French] On etudie, dans ce rapport, les principales proprietes nucleaires d'un reseau a uranium enrichi (20 pour cent), dont le moderateur et le reflecteur sont l'eau legere en vue des experiences de demarrage. Ce reacteur devra fonctionner a 1 MW. 1) Etude de diverses masses critiques. 2) Controle. Efficacite des barres de controle en cadmium et d'une barre de reglage en acier inoxydable. 3) Etude de l'effet sur la reactivite de perturbation au centre du coeur. 4) Etude de l'empoisonnement xenon et samarium. 5) Coefficient de temperature. 6) Echanges thermiques dans un element. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    Bendarag, A

    1999-07-09

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

  4. Pointing Out Main Factors from Design, Construction and Operating Experience of Existing Nuclear Plants for Assisting in Shaping Future Nuclear Power Programmes; Les principaux criteres degages de l'etude, de la construction et de l'exploitation des centrales nucleaires existantes et leur interet pour l'elaboration des futurs programmes d'energie d'origine nucleaire; Ukazanie osnovnykh faktorov proektirovaniya, stroitel'stva i opyta ehkspluatatsii sushchestvuyutsikh atomnykh ehlektrostantsij, chto dolzhno pomoch' pri sostavlenii budushchikh programm atomnoj ehnergetiki; Principales consideraciones relativas al diseno, construccion y explotacion de centrales nucleares, encaminadas a facilitar la preparacion de programas futuros de energia nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Dalla Volta, F. [Comitato Nazionale per l' Energia Nucleare, Rome (Italy)

    1963-10-15

    enseignements qui ont ete fournis, aux points de vue technique et economique, par l'etude, la construction et l'exploitation des premieres centrales nucleaires, et qui peuvent etre particulierement utiles pour l'implantation de nouvelles centrales de ce genre dans l'avenir, notamment eu egard aux conditions qui regnent en Italie. La technologie actuelle des reacteurs et les progres qu'elle continue de faire revelent une tendance marquee vers la reduction du cout, non seulement des cycles de combustible, mais aussi des elements de la centrale. Cette evolution se trouve d'ailleurs favorisee par la tendance croissante a construire des centrales plus grandes et par le fait que l'etude du developpement du reseau electrique semble indiquer que, sur le plan economique, il y a plus d' avantage ainstaller des centrales nucleaires plus puissantes que d'augmenter la puissance des centrales classiques. Se fondant sur l'experience acquise concernant l'etu de, la construction et l'essai des divers types de centrales existantes, l'auteur donne un apercu des principaux facteurs dont il convient de tenir compte lors de l'etablissement des programmes futurs. Il insiste sur le probleme de l'isolement, vu les incidences favorables que peut avoir sur le choix du site de la centrale la mise au point d'ecrans de protection tres surs, qui puissent etre construits sans augmentation sensible du prix de revient, en tirant notamment parti, pour resoudre certains aspects de ce probleme, des conditions particulieres qui se trouvent reunies en Italie. Quant a l'experience du fonctionnement de certaines centrales d'un modele eprouve, l'auteur examine dans quelle mesure ces installations peuvent etre construites sans difficulte et satisfaire la demande du reseau; il se refere ici egalement au role croissant qu'il est prevu d'attribuer a l'energie d'origine nucleaire en Italie. Enfin, l'auteur souligne a quel point le rassemblement et l'interpretation des donnees relatives aux trois centrales, qui doivent

  5. Nuclear Energy in Central Europe 98, Proceedings

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  6. Underground nuclear explosions. Geological survey of the cavities; Explosions nucleaires souterraines etude geologique des cavites

    Energy Technology Data Exchange (ETDEWEB)

    Faure, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    A geological survey of underground nuclear explosions makes it possible to determine the main characteristics of the cavity formed. The lower portion is spherical; the same was very likely true of the roof, which collapses in the majority of media with the exception of rock-salt. Its radius, for a given bomb size, can vary by a factor of two according to the type of rock. The lay-out of its contents depends on the characteristics of the solid and liquid products at the moment of the roof collapse; according to the medium involved, mixing of the rubble and the mud-flow occurs (granite) or does not occur (tuff and alluvia). In all media, the average physical properties can be evaluated. (author) [French] L'etude geologique d'explosions nucleaires souterraines permet de determiner les principaux caracteres de la cavite creee. Sa partie inferieure est spherique; il en etait vraisemblablement de meme de sa voute, effondree dans la plupart des milieux a l'exception du sel gemme. Son rayon, a energie d'engin egale, varie selon les roches du simple au double. La disposition de son contenu depend des caracteristiques des produits solides et liquides au moment de la chute du toit; selon le cas, il n'y a pas (tuf et alluvions) ou il y a (granite) melange des eboulis et des laves. Dans tous les milieux, les proprietes physiques moyennes peuvent etre evaluees. (auteur)

  7. Nuclear insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

    Warren, G.

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    Flach, G.; Bonitz, M.

    1979-12-01

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

  9. Blowing loop in the EL-4 reactor: CO{sub 2} flow control analogue study; Boucle de soufflage de la centrale EL-4 - regulation du debit CO{sub 2} - etude analogique

    Energy Technology Data Exchange (ETDEWEB)

    Chazal, G; Merle, J P; Guillemard, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Leroy, C; Robin, L; Jacquin, J C; Cornudet, A [Societe INDATOM, France (France)

    1966-07-01

    This report describes one study which contributed to the construction of the Monts d'Arree nuclear power station: EL-4. The reactor is cooled by a CO{sub 2} current provided by 3 turbo-blower groups. The priming vapour for the turbines is taken at the exit of the main CO{sub 2} - H{sub 2}O exchangers. The operation of EL 4 is based on a high degree of centralization of the controls which attributes an important role to the general regulation circuits. This general regulation includes in particular an internal blowing loop which controls the CO{sub 2} flow. The study of the control of this CO{sub 2} flow is made up of 3 parts: - analogue representation of the reactors cooling circuit and of the turbo blower unit. - first test campaign using the analogue computer describing the natural behaviour of the system in the absence of control. theoretical determination of the regulation factors; definition of the regulation using an analogue computer and second test campaign for recording the performances of the blowing loop. The 4. part of the report deals with the analogue study: analogue equations - development. (authors) [French] Ce rapport prend place parmi les etudes de realisation de la Centrale des Monts d'Arree EL-4. Le reacteur est refroidi par une circulation de CO{sub 2} assuree par 3 groupes turbosoufflantes. La vapeur d'entrainement des turbines est prelevee a la sortie des echangeurs principaux CO{sub 2} - H{sub 2}O. L'exploitation de EL-4 repose sur une centralisation poussee des moyens de controle-commande qui attribue un role essentiel aux circuits de regulation generale. Cette regulation generale comporte en particulier une boucle interne de soufflage qui realise un asservissement du debit de CO{sub 2}. L'etude de cette regulation du debit CO{sub 2} comprend 3 parties: - representation analogique du circuit de refroidissement du reacteur et de l'ensemble turbine-soufflante. - premiere campagne d'essais sur calculateur analogique decrivant le comportement

  10. Central Bureau for Nuclear Measurements

    International Nuclear Information System (INIS)

    1991-01-01

    The main task of CBNM is defined as the specific programme Nuclear Measurements and Reference Materials. In the field of neutron data for standards, for fission and for fusion application, the nuclear charge distribution and odd-even effects for mass, charge and neutron number in the cold spontaneous fission of 252 Cf were determined. X- and γ-ray emission probabilities were evaluated in the frame of an IAEA coordinated Research Project. The subthermal fission cross section measurements of 235 U, 233 U and 239 Pu, were finalised. The dependence of the experimental weighting function of C 6 D 6 detectors on thickness of several 56 Fe samples was determined. Fusion data studies involved the development of a light-ion telescope with improved time - and energy resolution. Double differential cross-sections of 9 Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192 Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO 2 ), 523 (Al), 525 (Nb) and 526 (Nb). Progress was achieved in the preparation of dried solid spikes of uranium and plutonium for undiluted reprocessing input solution analysis. 10 B and 6 Li deposits were prepared for a redetermination of the neutron lifetime. Preliminary studies on speciation of trace metals in biological fluids were successful. Radioactive waste barrels were analysed by γ-scanning and blood samples were irradiated with 0.6 MeV neutrons. Exploratory research resulted in first measurements of transition radiation properties

  11. Nuclear Electric's central dose record service

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  12. Central depression of nuclear charge density distribution

    International Nuclear Information System (INIS)

    Chu Yanyun; Ren Zhongzhou; Wang Zaijun; Dong Tiekuang

    2010-01-01

    The center-depressed nuclear charge distributions are investigated with the parametrized distribution and the relativistic mean-field theory, and their corresponding charge form factors are worked out with the phase shift analysis method. The central depression of nuclear charge distribution of 46 Ar and 44 S is supported by the relativistic mean-field calculation. According to the calculation, the valence protons in 46 Ar and 44 S prefer to occupy the 1d 3/2 state rather than the 2s 1/2 state, which is different from that in the less neutron-rich argon and sulfur isotopes. As a result, the central proton densities of 46 Ar and 44 S are highly depressed, and so are their central charge densities. The charge form factors of some argon and sulfur isotopes are presented, and the minima of the charge form factors shift upward and inward when the central nuclear charge distributions are more depressed. Besides, the effect of the central depression on the charge form factors is studied with a parametrized distribution, when the root-mean-square charge radii remain constant.

  13. Nuclear Safety in Central and Eastern Europe

    International Nuclear Information System (INIS)

    2001-04-01

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

  14. Perspectives for nuclear electricity in Central Africa

    International Nuclear Information System (INIS)

    Wa Kalenga, M.

    1977-01-01

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

  15. Perspectives for nuclear electricity in central Africa

    International Nuclear Information System (INIS)

    Wa Kalenga, M.

    1977-01-01

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

  16. Study of global control of VIRGO Central Interferometer; Etude du controle global de l'Interferometre Central de VIRGO

    Energy Technology Data Exchange (ETDEWEB)

    Matone, Luca [Paris-11 Univ., 91 Orsay (France)

    1999-10-29

    The VIRGO project for the detection of gravitational waves will first operate in a test configuration, known as the Central Area Interferometer (CITF). The subject of this thesis consists of a study for the global control of this interferometer. In particular, the problems of auto-alignment and acquisition of lock are addressed. First, an investigation of the CITF optical response to longitudinal and angular mirror movements is given. On the basis of this study, we show how the ratio of photodiode signals can be used to detect and control the dark fringe when the CITF is far from its operating point (locked state). Furthermore, we present the simulation results of a quadrant photodiode configuration capable of reconstructing the mirrors' tilts once the CITF is in a locked state. The performance of a control system for the auto-alignment is then given. A study on the mode-cleaner prototype MC30 is then introduced in order to comprehend the process of lock acquisition by a linear feedback system for two different finesse values: F {approx_equal}100 and F {approx_equal} 1600. We define a threshold velocity for the mirrors' relative motion below which acquisition of lock is possible. A phenomenon, referred to as ringing effect, was observed and examined on the MC30 prototype in high finesse. The results of numerical calculations allowed us to fit measurement and estimate from them the cavity finesse as well as the mirrors' relative velocity during the resonance crossing. An empirical formula is then presented capable of determine the relative velocity from the positions of the oscillations' minima and maxima. An algorithm to guide into lock the CITF is then presented, consisting of an iterative procedure of velocity reconstruction and pulse application. A numerical calculation simulated the algorithm, the mirrors' motion, the optical response and the ADCs' process. As a result, acquisition times of the order of one second were observed: an improvement of more than one

  17. Study of global control of VIRGO Central Interferometer; Etude du controle global de l'Interferometre Central de VIRGO

    Energy Technology Data Exchange (ETDEWEB)

    Matone, Luca [Paris-11 Univ., 91 Orsay (France)

    1999-10-29

    The VIRGO project for the detection of gravitational waves will first operate in a test configuration, known as the Central Area Interferometer (CITF). The subject of this thesis consists of a study for the global control of this interferometer. In particular, the problems of auto-alignment and acquisition of lock are addressed. First, an investigation of the CITF optical response to longitudinal and angular mirror movements is given. On the basis of this study, we show how the ratio of photodiode signals can be used to detect and control the dark fringe when the CITF is far from its operating point (locked state). Furthermore, we present the simulation results of a quadrant photodiode configuration capable of reconstructing the mirrors' tilts once the CITF is in a locked state. The performance of a control system for the auto-alignment is then given. A study on the mode-cleaner prototype MC30 is then introduced in order to comprehend the process of lock acquisition by a linear feedback system for two different finesse values: F {approx_equal}100 and F {approx_equal} 1600. We define a threshold velocity for the mirrors' relative motion below which acquisition of lock is possible. A phenomenon, referred to as ringing effect, was observed and examined on the MC30 prototype in high finesse. The results of numerical calculations allowed us to fit measurement and estimate from them the cavity finesse as well as the mirrors' relative velocity during the resonance crossing. An empirical formula is then presented capable of determine the relative velocity from the positions of the oscillations' minima and maxima. An algorithm to guide into lock the CITF is then presented, consisting of an iterative procedure of velocity reconstruction and pulse application. A numerical calculation simulated the algorithm, the mirrors' motion, the optical response and the ADCs' process. As a result, acquisition times of the order of one second were observed: an

  18. Central depression of the nuclear charge distribution

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  19. Prospective economical study of the nuclear power file; Etude economique prospective de la filiere electrique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Charpin, J M [Commissariat General du Plan, 75 - Paris (France); Dessus, B [Ecodev-CNRS, 92 - Meudon (France); Pellat, R [CEA, 75 - Paris (France)

    2000-07-01

    On May 7, 1999 an economical study of the overall nuclear file, and in particular, of the back-end part of the fuel cycle and including the reprocessing, was requested by the French Prime Minister. This study includes the cost comparisons with the other means of power production and takes into consideration the environmental costs. The study is shared into five chapters dealing with: 1 - the legacy of the past: todays park of nuclear plants, economical and material status; 2 - the international evolution: the dynamics of nuclear policies worldwide (existing parks and R and D programs), the rise of environmental problems worldwide (CO{sub 2} and the climate convention, nuclear risks, attempts of including environment in the power costs), the choices made for the management of spent fuels in the main countries; 3 - the technological prospects for the power production and use: technologies for the mastery of power demand (residential, industrial and tertiary sectors, power transportation), technologies of power production (production from nuclear, fossil and renewable energies); 4 - prospective scenarios for France: two demand scenarios at the year 2050 vista (energy, electric power), power supply (supply structure with respect to scenarios, nuclear parks, power capacities), environmental aspects (CO{sub 2} emissions, plutonium and minor actinides production); 5 - the economical status of the different scenarios: data preparation, fossil fuel price scenarios, investment and operation costs of the different power production means (nuclear, fossil and renewable energies, natural gas and power distribution networks), comparison between fluxes and cumulated economic costs linked with the different scenarios (investments, exploitation, fuels, R and D, status for 2000 to 2050), time structure of expenditures with respect to the different scenarios (chronology, statuses, kWh costs, sensitivity with respect to the rate of discount, valorization of existing parks in 2050

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-07-01

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

  1. Development of mercury porosimeter. Application to nuclear graphite studies (1961); Mise au point d'un porosimetre a mercure. Application a l'etude des graphites nucleaires (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Bocquet, M; Genisson, J; Sailleau, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    A mercury porosimeter, model IFP-CEA, has been developed for application to nuclear graphite studies. The apparatus is based on the capillary depression phenomenon. The relationship between the radius of a pore and the pressure at which mercury fills it is pr = -2 {sigma} cos {theta} ( {sigma} is the surface tension, {theta} the angle of contact of the mercury). After some theoretical consideration, the apparatus is described. The mercury pressure is increased step-wise from 0 to 1000 kg/cm{sup 2} thus yielding the complete distribution of pores from 92 {mu} to 75 A. Results are, then presented concerning nuclear graphites which show the evolution of the porous structure under the effect of bitumen impregnation. In general, the volume of the large pores decreases while that of the small pores increases. The structure of impregnated products appears to depend to a certain extent on that of the starting materials. It has also been possible to study other products with this porosimeter; the range of measurements possible is such that it may be used for the study of the majority of porous materials. (authors) [French] Un porosimetre a mercure modele IFP-CEA a ete mis au point en vue de son application a l'etude de graphites nucleaires. Le fonctionnement de l'appareil repose sur le phenomene de depression capillaire. On etablit la relation existant entre le rayon r d'un pore et la pression p pour laquelle le mercure peut y penetrer: pr = -2 {sigma} cos {theta} ( {sigma} tension superficielle, {theta} angle de contact du mercure). Apres quelques considerations theoriques, l'appareil utilise est decrit. Il permet de faire varier par palier la pression du mercure entre 0 et 1000 kg/cm{sup 2} et d'etablir ainsi la distribution complete des rayons de pores compris entre 92 {mu} et 75 A. Les resultats d'une etude faite sur des graphites nucleaires sont alors presentes faisant apparaitre l'evolution de la structure poreuse sous l'effet des impregnations au brai. D'une facon

  2. Central Institute of Nuclear Research Rossendorf 25 years old

    International Nuclear Information System (INIS)

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

    1981-12-01

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

  3. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  4. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  5. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

    Le Coroller, Y. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux

  6. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

    Le Coroller, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux millimetres fonctionnent

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

    International Nuclear Information System (INIS)

    Stritar, A.; Jencic, I.

    1996-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-07-01

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

  9. THERMOS, district central heating nuclear reactors

    International Nuclear Information System (INIS)

    Patarin, L.

    1981-02-01

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

  10. Nuclear energy in central and eastern Europe

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  11. Study methods for the drillings around the underground nuclear explosions in the Sahara. Part 1. study of rock samples; Methodes d'etude des forages realises autour des explosions nucleaires souterraines au Sahara. Premiere partie: etude des echantillons de roche

    Energy Technology Data Exchange (ETDEWEB)

    Derlich, S [Commissariat a l' Energie Atomique, Bruyers-le-Chatel (France). Centre d' Etudes

    1969-07-01

    An examination of the mechanical effects produced on rocks by an underground nuclear explosion calls for the use of particular means of exploration which are described in this report, special attention being paid to the equipment used in connection with the French nuclear tests in the Sahara. The drilling methods used (rotary and turbo-drilling) are adapted to the particular conditions of the sampling programme, to the radioactivity and to the temperature in the region of the explosion. A study of the samples makes it possible to obtain the new characteristics of the rock and to assess the chemical and mechanical transformations which it has undergone. An examination of the core obtained from the drilling, together with a knowledge of the drilling parameters (depth of the probe, sample recovery, etc...), makes it possible to study the extent and the characteristics of the zones which have been damaged to different degrees according to their distance from the zero point: cavity, strongly powdered zone, fractured zone, chimney, zones containing high stresses leading to a particular type of fracture of the cores. The problems connected with the interpretation of the results are also presented. (author) [French] L'examen des effets mecaniques provoques par une explosion nucleaire souterraine sur la roche necessite la mise en oeuvre de moyens d'exploration particuliers dont l'expose fait l'objet de ce rapport, essentiellement pour les moyens utilises autour des essais nucleaires francais au Sahara. Les methodes de forage (rotary et turboforage) sont adaptees aux conditions particulieres dues au programme d'echantillonnage, a la radioactivite et a la temperature regnant a proximite du point de tir. L'etude des echantillons permet la determination des nouveaux caracteres de la roche et de ses transformations chimique et mecanique. L'examen des carottes et l'utilisation des parametres de forage (cotes sondeurs, recuperation des echantillons, etc...) permettent d'etudier l

  12. Central eastern Europe approach to the security over nuclear materials

    International Nuclear Information System (INIS)

    Smagala, G.

    2002-01-01

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

  13. Etude bactériologique et biochimique du miel vendu au marché central de Bukavu (Congo

    Directory of Open Access Journals (Sweden)

    Kitambala, K.

    1999-01-01

    Full Text Available Bacteriological and Biochemical Study of Honey Sold at Bukavu (Congo Central Market. The honey sold in the central market of Bukavu (Congo is produced by traditional bee keepers. This article deals with a bacteriological and biochemical study of this product in order to determine its contamination and pollution levels. Results indicated a contamination of faecal origin (presence of enterobacteria such as Escherichia coli. The bacteriological tests showed the presence of bacteria fermenting glucose, thus altering the quality of the honey. The latter is therefore inappropriate for consumption and constitutes a danger for the health of humans.

  14. Jose Cabrera NPP; Central Nuclear Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Diez, P.

    2004-07-01

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

  15. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

  16. Folds and Etudes

    Science.gov (United States)

    Bean, Robert

    2007-01-01

    In this article, the author talks about "Folds" and "Etudes" which are images derived from anonymous typing exercises that he found in a used copy of "Touch Typing Made Simple". "Etudes" refers to the musical tradition of studies for a solo instrument, which is a typewriter. Typing exercises are repetitive attempts to type words and phrases…

  17. 30 years of Central Institute for Nuclear Research at Rossendorf

    International Nuclear Information System (INIS)

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

    1986-10-01

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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  19. Nuclear Power in South-Central Brazil

    International Nuclear Information System (INIS)

    Cintra do Prado, L.

    1966-01-01

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

  20. Nuclear spin noise in the central spin model

    Science.gov (United States)

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

    2018-05-01

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

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

    International Nuclear Information System (INIS)

    2009-06-01

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

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

    International Nuclear Information System (INIS)

    Yang Xiaowei

    2014-01-01

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

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

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  4. Some aspects of nuclear graphite production in France; Etude generale sur les graphites nucleaires produits en France

    Energy Technology Data Exchange (ETDEWEB)

    Gueron, J; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legendre, A [Pechiney, 75 - Paris (France)

    1958-07-01

    1) Manufacturing: A summary and results on the CEA-Pechiney purification process are given. Variations in the preparation of green pastes and their effects on graphitized material are described. 2) Physical and mechanical properties: Results are given on: - Statistics of dimensional variatior products having square cross-section. - Statistical variation of thermal expansion coefficients and of electrical conductivity. - Density of normals to carbon layer planes and their connexion with thermal expansion. - Stress-strain cycles and conclusions drawn therefrom. - Mechanical resistance and gas permeability of items for supporting fuel elements. 3) Behaviour under radiation: Alteration under radiation of French graphites irradiated either in G1 pile or in experimental piles, and thermal annealing of those alterations, are given. (author)Fren. [French] 1) Fabrication: On resume le procede d'epuration CEA-PECHINEY, ainsi que diverses modalites de preparation des pates et on expose les resultats obtenus. 2) Proprietes physiques et mecaniques: On indique le resultat d'etudes sur: - la statistique des dimensions de produits a section carree. - celle des variations des coefficients de dilatation thermique et de la conductibilite electrique. - la densite des normales aux plans graphitiques et leur connexion avec la dilatation thermique. - la compression mecanique du graphite. - la solidite mecanique et la permeabilite aux gaz de pieces destinees a supporter des cartouches de combustible. 3) Tenue sous rayonnement: Modification sous rayonnement des graphites fran is irradies soit dans la pile G1, soit dans des piles experimentales, et guerison thermique de ces modifications. (auteur)

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

    International Nuclear Information System (INIS)

    Koelzer, W.

    1993-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

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

    International Nuclear Information System (INIS)

    Stritar, A.; Jencic, I.

    1995-01-01

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

  8. Study on underground gas storage in Europe and Central Asia; Etude sur le stockage souterrain du gaz en Europe et en Asie Centrale

    Energy Technology Data Exchange (ETDEWEB)

    Sedlacek, R. [NlfB, Germany (Germany); Rott, W. [Wintershall AG, Celle (Germany); Rokosz, W. [POGC, Poland (PL)] (and others)

    2000-07-01

    The Working Party on Gas of the United Nations Economic Commission for Europe (UN/ECE), at its sixth session in 1996, decided to undertake a study on 'Underground gas storage in Europe and Central Asia'. The study was launched by the Working Party on Gas in the recognition of the role of underground gas storage (UGS) in the creation of unified European gas market, its liberalization, security of gas supply and cooperation among gas enterprises. The data analysed by the study was collected through the comprehensive questionnaire, circulated among gas companies/organizations of the ECE member-countries. To carry out the study, a special Ad Hoc Group of Experts, representing leading gas companies of the region, was set up. The study deals with a wide range of issues related to the underground storage of gas, such as current status of UGS in Europe and Central Asia, new and emerging technologies, new and existing UGS projects, regulatory framework, cost of storage in USA and in Europe, future gas markets development. An attempt was also made to identify the UGS facilities that play (and could provide in the future) the international contract border services. (authors)

  9. Reports by the Parliamentary Office for scientific and technological assessments. Thursday, April 14, 2011. Information on the Fukushima accident by Mr Thomas Houdre, Nuclear plant manager by the Nuclear Safety Authority. Nuclear safety, the role and future of the sector - Presentation of the feasibility study; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 14 avril 2011. Point d'information sur l'accident de Fukushima par M. Thomas Houdre, directeur des centrales nucleaires de l'Autorite de Surete Nucleaire. Securite nucleaire, place de la filiere et son avenir - Presentation de l'etude de faisabilite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-04-15

    In a first part, a representative of the ASN describes the situation of the Fukushima Daiichi nuclear power station about one month after the accident. He reports the phenomena which have occurred, gives some explanations, compares this accident with that of Chernobyl. The second part is a discussion about the content and the organization of a parliamentary mission which aims at investigating nuclear safety, and the role and future of the nuclear sector

  10. 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)

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

    International Nuclear Information System (INIS)

    1984-05-01

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

  12. Study and installation of concrete shielding in the civil engineering of nuclear construction (1960); Etude et mise en place des betons de protection dans le genie civil des ouvrages nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Dubois, F [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The object of this report is to give technical information about high density concretes which have become very important for radiation biological shielding. The most generally used heavy aggregates (barytes, ilmenite, ferrophosphorus, limonite, magnetite and iron punching) to make these concretes are investigated from the point of view prospecting and physical and chemical characteristics. At first, a general survey of shielding concretes is made involving the study of components, mixing and placing methods, then, a detailed investigation of some high density concretes: barytes concrete, with incorporation of iron punching or iron shot, ferrophosphorus concrete, ilmenite concrete and magnetite concrete, more particularly with regard to grading and mix proportions and testing process. To put this survey in concrete form, two practical designs are described such as they have been carried out at the Saclay Nuclear Station. Specifications are given for diverse concretes and for making the proton-synchrotron 'Saturne' shielding blocks. (author) [French] Ce rapport a pour objet de donner des precisions techniques au sujet des betons a haute densite qui ont pris une grande importance pour la protection biologique contre les rayonnements. Les agregats lourds les plus couramment utilises (barytine, ilmenite, ferrophosphore, limonite, magnetite et riblons) pour la fabrication de ces betons, sont examines du point de vue prospection et caracteristiques physiques et chimiques. On procede d'abord a une etude generale des betons de protection comprenant l'etude des constituants, de la confection et de la mise en place, ensuite, a un examen detaille de quelques betons a haute densite: betons a base de barytine, avec incorporation de riblons ou de grenaille de fonte, betons au ferrophosphore, a base d'ilmenite ou de magnetite, notamment en ce qui concerne la granulometrie, la composition, le dosage et les processus d'essais. Pour concretiser ces etudes, deux applications pratiques

  13. Study and installation of concrete shielding in the civil engineering of nuclear construction (1960); Etude et mise en place des betons de protection dans le genie civil des ouvrages nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Dubois, F. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The object of this report is to give technical information about high density concretes which have become very important for radiation biological shielding. The most generally used heavy aggregates (barytes, ilmenite, ferrophosphorus, limonite, magnetite and iron punching) to make these concretes are investigated from the point of view prospecting and physical and chemical characteristics. At first, a general survey of shielding concretes is made involving the study of components, mixing and placing methods, then, a detailed investigation of some high density concretes: barytes concrete, with incorporation of iron punching or iron shot, ferrophosphorus concrete, ilmenite concrete and magnetite concrete, more particularly with regard to grading and mix proportions and testing process. To put this survey in concrete form, two practical designs are described such as they have been carried out at the Saclay Nuclear Station. Specifications are given for diverse concretes and for making the proton-synchrotron 'Saturne' shielding blocks. (author) [French] Ce rapport a pour objet de donner des precisions techniques au sujet des betons a haute densite qui ont pris une grande importance pour la protection biologique contre les rayonnements. Les agregats lourds les plus couramment utilises (barytine, ilmenite, ferrophosphore, limonite, magnetite et riblons) pour la fabrication de ces betons, sont examines du point de vue prospection et caracteristiques physiques et chimiques. On procede d'abord a une etude generale des betons de protection comprenant l'etude des constituants, de la confection et de la mise en place, ensuite, a un examen detaille de quelques betons a haute densite: betons a base de barytine, avec incorporation de riblons ou de grenaille de fonte, betons au ferrophosphore, a base d'ilmenite ou de magnetite, notamment en ce qui concerne la granulometrie, la composition, le dosage et les processus d'essais. Pour concretiser ces

  14. Nuclear legislation in central and eastern europe and the NIS

    International Nuclear Information System (INIS)

    2003-01-01

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

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

    International Nuclear Information System (INIS)

    Koelzer, W.

    1994-04-01

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

  16. Centralized operation and monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

    1988-01-01

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

  17. 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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  19. Criticality studies; Etudes de criticite

    Energy Technology Data Exchange (ETDEWEB)

    Breton, D; Lecorche, P; Clouet d' Orval, Ch [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    Criticality studies made at the Commissariat a l'Energie atomique deal on the one hand with experiments on plutonium and uranium solutions, on the other hand with theoretical work on the development and use of computation, methods for the resolution of problems concerning the nuclear safety of chemical and metallurgical plants. I - Since 1958 the experimental studies have dealt with homogeneous media constituted by a fissile salt dissolved in light water. Developed using the reactor Proserpine, the experiments have been carried on at Saclay on the Alecto assemblies where solutions of plutonium or of 90 p.100 - enriched uranium can be made critical. The results already obtained relate to critical masses of cylindrical tanks of diameters from 20 to 50 cm. reflected in several ways (water, concrete, etc. . ) at concentrations up to 100 g/liter. Physical measurements (spectra, reactor noises) and interaction measurements complete the results. Other experiments relating to plutonium solutions were begun in 1963, at the Valduc Center. They deal with the study of critical masses of annular vessels of external diameter 50 cm and internal diameter varying from 10 to 30 cm. These vessels can be water reflected internally, externally, or both. Two of these vessels have been studied in interaction for various geometries. Slabs of various thicknesses were also studied. II - The studies thus undertaken allowed the development of methods of computation which have been tested on several experiments. Particular use has been made of the possibilities of calculations based on transport theory and on Monte Carlo methods. All these theoretical studies are applied to the design and control of industrial plants from the point of view of safety. (authors) [French] Les etudes de criticite effectuees au CEA comportent d'une part des experiences sur des solutions de plutonium et d'uranium enrichi, d'autre part des travaux theoriques portant sur la mise au point et l'exploitation de methodes

  20. Study of the chimney produced by an underground nuclear explosion; Etude de la cheminee creee par une explosion nucleaire souterraine

    Energy Technology Data Exchange (ETDEWEB)

    Derlich, S [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    Underground nuclear explosions lead to the formation of a cavity which is roughly of spherical shape. The roof of this cavity is unstable and collapses in most cases, leading to the formation of a chimney. The height and the diameter depend on the energy of the charge and on the nature of the surroundings. The chronology of the various stages can be determined by seismic observations. The interior of the chimney is filled, either partially or completely, with rubble earth. This phenomenon is of great importance as far as the use of nuclear explosions for industrial applications is concerned. (author) [French] Les explosions nucleaires souterraines creent une cavite de forme grossierement spherique. La voute de cette cavite est instable et s'effondre dans la plupart des cas, donnant lieu a la formation d'une cheminee. La hauteur et le diametre sont fonction de l'energie du tir et de la nature du milieu. La chronologie des evenements peut etre determinee par des observations seismiques. L'interieur des cheminees est occupe, en partie ou en totalite, par des eboulis. Ce phenomene presente un grand interet pour l'utilisation des explosions nucleaires a des fins industrielles. (auteur)

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

    International Nuclear Information System (INIS)

    Myers, L.C.

    1993-11-01

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

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

    International Nuclear Information System (INIS)

    Widell, C.-O.

    1978-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-11-01

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

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

    International Nuclear Information System (INIS)

    Matsumoto, Masaru

    1977-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-07-01

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

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

    International Nuclear Information System (INIS)

    Gortnar, O.; Stritar, A.

    1999-01-01

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

  7. Feasibility study for the installation of a small hydro electric power plant; Etude de faisabilite. Petite centrale hydro-electrique au lieu dit 'Sous les Roches' a Sonceboz

    Energy Technology Data Exchange (ETDEWEB)

    Tissot, N. [MHyLab, Mini-Hydraulics Laboratory, Montcherand (Switzerland); Hausmann, H. [Hans Hausmann, Bevilard (Switzerland)

    2003-07-01

    This report for the Swiss Federal Office of Energy presents a technical, economical and ecological analysis of the feasibility of a small hydroelectric power plant at Sonceboz, in the Swiss Jura mountains. The power of the planed plant would typically be 500 kW for a water head of about 10 m. The study shows that, compared to one single turbine, a pair of Kaplan type turbines would be operational over a larger range of the river's water flow rate. This solution would be a little bit more costly but offer more flexibility for maintenance. Two maximum water flow rates are considered, 4.5 and 6 m{sup 3}/s respectively. According to the economical study, done with current electric kWh prices, both configurations are viable while the largest flow rate leads to a larger profit. The report is rounded up by a sensitivity analysis considering variations in annual power generation, electro-mechanical and construction cost as well as turbine efficiency. It indicates that this last factor could be crucial for the overall profitability. [French] Ce rapport est le resultat detaille de l'analyse technico-economique et ecologique de faisabilite de la realisation d'une petite centrale hydroelectrique basse chute qui pourrait exploiter une denivellation d'environ 10 m pour une puissance de l'ordre de 500 kW pres de Sonceboz dans le Jura suisse. L'etude montre que le couplage de deux turbines Kaplan offrirait une possibilite de fonctionnement sur une plus grande plage de flux ainsi qu'une plus grande flexibilite de maintenance, ceci pour un cout legerement superieur a l'option a une seule turbine. Les debits de 4.5 et 6 m{sup 3}/s sont consideres. L'etude economique montre que le debit de 6 m{sup 3}/s est plus rentable au prix de vente actuel du kWh. L'article se termine par une analyse de sensibilite sur les incertitudes concernant la production annuelle, les prix de l'electromecanique et du genie civil et le rendement des

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  9. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-09-15

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

  11. Centralized digital computer control of a research nuclear reactor

    International Nuclear Information System (INIS)

    Crawford, K.C.

    1987-01-01

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

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

    International Nuclear Information System (INIS)

    Jencic, I.; Glumac, B.

    2001-01-01

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

  13. CENTRAL NUCLEAR ELECTRIC, A FUTURE OF ROMANIAN ENERGY

    Directory of Open Access Journals (Sweden)

    Gabriel I. NĂSTASE

    2010-05-01

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

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

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  15. Contribution to the study of deformed heavy nuclei by means of nuclear reactions; Contribution a l'etude des noyaux lourds deformes au moyen de reactions nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-01

    The experimental results obtained in the study of the (d,p) reactions, at E{sub d} = 12 MeV, on the three even-even deformed nuclei {sup 170}Yb, {sup 172}Yb and {sup 174}Yb have been analysed in terms of DWBA calculations. The spectroscopic information relative to the odd final nuclei have been compared with the predictions of the collective model and of the Nilsson's model. The effect of various parameters used in the DWBA analysis (form factors, optical wave functions) has been carefully studied. The observed differences between the three final nuclei are qualitatively reproduced in the experimental study of resonances, seen in excitation functions of elastically and inelastically scattered protons on the same target nuclei, and corresponding to analogue states in the three nuclei {sup 171}Lu, {sup 173}Lu and {sup 175}Lu. (author) [French] Les resultats experimentaux de l'etude des reactions (d.p) a E{sub d} = 12 MeV, sur les noyaux deformes pairs-pairs {sup 170}Yb, {sup 172}Yb et {sup 174}Yb ont ete interpretes dans le cadre de l'approximation de Born des ondes deformees. Les informations spectroscopiques relatives aux noyaux impairs finals ont ete comparees aux predictions du modele collectif et du modele de Nilsson, apres avoir examine avec soin l'influence des differents parametres (facteurs de forme, fonctions d'onde 'optiques') utilises lors de l'analyse. Les differences observees entre les trois noyaux finals sont qualitativement reproduites par les resultats experimentaux de l'etude de resonances dans les fonctions d'excitation de diffusion elastique et inelastique de protons sur les memes noyaux-cibles, lors de la recherche d'etats analogues dans les noyaux {sup 171}Lu, {sup 173}Lu et {sup 175}Lu. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-01

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

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

    International Nuclear Information System (INIS)

    Duran, Felicia Angelica; Waymire, Russell L.

    2013-01-01

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

  18. First-order effects of a nuclear moratorium in Central Europe

    International Nuclear Information System (INIS)

    Messner, S.; Strubegger, M.

    1986-12-01

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

  19. Study of the nuclear matter flow with the multidetector INDRA; Etude de l`ecoulement de matiere nucleaire avec le multidetecteur INDRA

    Energy Technology Data Exchange (ETDEWEB)

    Lefort, T. [Caen Univ., 14 (France). Lab. de Physique Corpusculaire

    1997-06-12

    The work presented in this thesis relates to the study of the products which are not emitted by the statistical deexcitation of the projectile and target. The experiment on which this work is based on was performed at GANIL with the detector INDRA on two systems: {sup 36} Ar + {sup 58} Ni and {sup 129} Xe + {sup 119} Sn. A whole characterization (mass, composition, multiplicities and energy properties) of mid-rapidity emission has been done for the system {sup 36} Ar + {sup 58} Ni between 52 and 95 A.MeV. The amount of matter associated to this emission seems to be independent of the incident energy and directly linked with the centrality of the collision. The available energy per nucleon for the production of mid-rapidity products seems to be insensitive to the impact parameter. A systematic study of the nuclear matter in-plane flow has also been carried out. It has been established that the usual methods for reaction plane determination do not allow one to measure accurately the value of flow parameter at intermediate energies. Nevertheless, the inversion energy of the system {sup 36} Ar + {sup 58} Ni can be calculated for central collisions. This energy is independent of the nature of the products. Its value and the features of the mid-rapidity emission should allow one to extract in-medium nucleon-nucleon cross section by comparison with theoretical results. (author) 80 refs.

  20. Exclusive study of Ni+Ni and Ni+Au central collisions: phase coexistence and spinodal decomposition; Etude exclusive des collisions centrales Ni+Ni et Ni+Au: coexistence de phase et decomposition spinodale

    Energy Technology Data Exchange (ETDEWEB)

    Guiot, B

    2002-12-01

    The INDRA multidetector allowed us to study the Ni+Ni collisions at 32A MeV and the Ni+Au collisions at 52,4 MeV. Central collisions leading to 'quasi-fused' systems were isolated using multidimensional analysis techniques: the Discriminant Analysis and the Principal Component Analysis. Comparison with a statistical model shows that the selected events are compatible with thermodynamical equilibrium. The average thermal excitation energy is 5A MeV for both systems. Calculations of heat capacities show that the deexcitation of the hot sources are akin to a liquid-gas phase transition of nuclear matter. Indeed heat capacities exhibit a negative branch as expected for a phase transition of a finite system. The dynamics of this phase transition has been investigated by applying the charge correlation method. An enhanced production of events with equal-sized fragments has been evidenced for Ni+Au at 52A MeV. No signal was found for Ni+Ni at 32A MeV. Finally this method was improved by taking into account the total charge conservation. The signal is seen more clearly for Ni+Au at 52A MeV, but is ambiguous for Ni+Ni at 32A MeV. The path followed in the state diagram, or the involved time scales, seem to be different for these systems. (authors)

  1. Contribution to the study of {beta} disintegration and of nuclear structure using experiments on certain {beta}-{gamma} cascades: 198{sub Au}, 86{sub Rb}, 170{sub Tm}; Contribution a l'etude de la desintegration beta et a l'etude de la structure nucleaire a l'aide d'experiences sur certaines cascades beta-gamma: 198{sub Au}, 86{sub Rb}, 170{sub Tm}

    Energy Technology Data Exchange (ETDEWEB)

    Lachkar, J. [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes; Paris-11 Univ., fabulte des Sciences 91 - Orsay (France)

    1969-07-01

    {beta}{gamma} directional angular correlations and shapes of inner beta spectra leading to the first excited level of the final nucleus enable one to determine the nuclear matrix elements typical of the {beta} transition. In the three observed first forbidden cases: {sup 170}Tm, {sup 86}Rb, {sup 198}Au, these matrix elements do not confirm the independent shell model theory. Other hypotheses are then suggested and discussed. (author) [French] Les experiences de correlation angulaire {beta}{gamma} et l'etude du spectre {beta} conduisant au premier niveau excite du noyau final permettent de determiner les elements de matrices nucleaires caracteristiques de cette transition. Dans les trois cas etudies (transitions une fois interdites): {sup 170}Tm, {sup 86}Rb, {sup 198}Au, ces elements de matrices ne peuvent etre retrouves a l'aide du modele en couches et a particules independantes. D'autres hypotheses sont alors emises et discutees. (auteur)

  2. Contribution to the study of {beta} disintegration and of nuclear structure using experiments on certain {beta}-{gamma} cascades: 198{sub Au}, 86{sub Rb}, 170{sub Tm}; Contribution a l'etude de la desintegration beta et a l'etude de la structure nucleaire a l'aide d'experiences sur certaines cascades beta-gamma: 198{sub Au}, 86{sub Rb}, 170{sub Tm}

    Energy Technology Data Exchange (ETDEWEB)

    Lachkar, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes; Paris-11 Univ., fabulte des Sciences 91 - Orsay (France)

    1969-07-01

    {beta}{gamma} directional angular correlations and shapes of inner beta spectra leading to the first excited level of the final nucleus enable one to determine the nuclear matrix elements typical of the {beta} transition. In the three observed first forbidden cases: {sup 170}Tm, {sup 86}Rb, {sup 198}Au, these matrix elements do not confirm the independent shell model theory. Other hypotheses are then suggested and discussed. (author) [French] Les experiences de correlation angulaire {beta}{gamma} et l'etude du spectre {beta} conduisant au premier niveau excite du noyau final permettent de determiner les elements de matrices nucleaires caracteristiques de cette transition. Dans les trois cas etudies (transitions une fois interdites): {sup 170}Tm, {sup 86}Rb, {sup 198}Au, ces elements de matrices ne peuvent etre retrouves a l'aide du modele en couches et a particules independantes. D'autres hypotheses sont alors emises et discutees. (auteur)

  3. Quantitative measurements of small isotopic samples in gaseous mixtures by utilization of some nuclear properties; Etude des possibilites de mesures de faibles quantites de gaz radioactifs dans un melange en utilisant simultanement plusieurs proprietes nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Maragnon, J; Delperie, C

    1967-12-01

    The question is to define the characteristics of a group of measurements allowing the analysis of traces of radioactive rare gases in gas mixtures of different composition. To distinguish the radioactive isotopes from each other and the activity level reaching 10{sup 6} due to their nuclear properties, the method was chosen to use several nuclear properties: gamma radiation energy, beta particle energy, lifetime of excited states. The choice of a plastic scintillator as beta detector allows to answer satisfactorilly to this demand by measurement of nuclear constants because of the short de/excitation time of this detector. Another advantage is that it can be a reservoir for the sample without any destruction nor modification of the sample. The study has been based on the mixture of Kr-85, the analysis of other rare gases follwos immediately from the adopted principle. [French] Les auteurs ont oriente leur recherche vers une solution permettant de distinguer les isotopes radioactifs les uns des autres et dans des rapports d'activite pouvant atteindre 10{sup 6}, grace a plusieurs de leurs proprietes nucleaires, energie de rayonnement gamma, energie de la particule beta, temps de vie des niveaux excites. Le choix d'un scintillateur plastique comme detecteur beta permet de repondre d'une maniere satisfaisante a la mesure des constantes nucleaires en raison du temps de de/excitation rapide de ce scintillateur. Il offre en outre l'avantage de pouvoir servir de reservoir a l'echantillon sans entrainer aucune destruction ni modification de celui-ci. L'etude a ete basee sur la mixture de Kr-85, l'analyse des autre gaz rares decoulant immediatement du principe adopte. (auteur)

  4. Contribution to the study of radio toxicity of aromatic and medicinal plants using solid state nuclear track detectors; Contribution a l etude de la radio toxicite des plantes aromatiques et medicinales au moyen des detecteurs solides de traces nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Mortassim, A; Misdaq, M A; Naaman, A

    2009-07-01

    The concentrations of uranium (238 U), thorium (232 Th), radon (222 Rn) and thoron (220 Rn) were measured in twenty aromatic and medicinal plants in {sup f}ind a new method based on using solid state nuclear track detectors type Cr-39 and Rs-115. He emerges from this study that the verbena and salvia have higher levels of uranium (radon) higher than that of other plants while the leaves of olive and saturja have concentrations of thorium (thoron) higher than other plants therefore radio toxicity of these plants is higher than that of others and may pose a radiological hazard if the masses are incorporated by consumers high. [French] Les concentrations en uranium (238U), thorium (232Th), radon (222Rn), et thoron (220Rn) ont ete mesurees dans vingt plantes aromatiques et medicinales en utilsant une nouvelle methode basee sur l utilisation des detecteurs solides de traces nucleaires de types CR-39 et LR-115. Il en sort de cette etude que la verveine et la salvia presentent des teneurs en uranium (radon) superieurs a celle des autres plantes alors que les feuilles d olivier et la saturja presentent des concentrations en thorium (thoron) plus elevee que celles des autres plantes par consequent la radio toxicite de ces plantes est superieure a celles des autres et peuvent presenter un risque radiologique si les masses incorporees par les consommateurs sont elevees.

  5. Contribution to the study of the action of electromagnetic fields on the angular correlations of nuclear radiation (1960); Contribution a l'etude de l'action des champs electromagnetiques sur les correlations angulaires des rayonnements nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Lehmann, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-01-15

    This work deals with the study of interaction of E.M. fields with nuclear moments of nuclei emitting gamma rays. We describe first experiments on delayed angular correlation showing the role played by statistic quadrupole interaction. We have measured the magnetic moment of the second excited state of {sup 19}F using an external magnetic field. In the case of {sup 19}O, experiments of angular distributions and angular correlations of gamma -rays taking into account the possibility of perturbations, allow us to determine the spin and parities of the three first levels. (author) [French] Le present travail concerne l'etude de l'interaction des champs electromagnetiques et des moments nucleaires de noyaux emettant des rayonnements gamma. Nous decrivons des experiences de correlation angulaire differee dont l'interpretation met en coincidence le role joue par les interactions quadrupolaires statiques. Nous avons mesure le moment magnetique de {sup 19}F dans un etat excite en utilisant un champ magnetique exterieur a la source radioactive. Enfin, dans le cas de {sup 19}O, nous montrons l'utilite d'un examen des possibilites de perturbations dans l'interpretation des resultats fournis par des correlations ou des distributions angulaires. (auteur)

  6. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Dirian, G; Roth, E; Vignet, P; Platzer, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  7. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J.; Dirian, G.; Roth, E.; Vignet, P.; Platzer, R. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  8. Contribution to the study of the action of electromagnetic fields on the angular correlations of nuclear radiation (1960); Contribution a l'etude de l'action des champs electromagnetiques sur les correlations angulaires des rayonnements nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Lehmann, P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-01-15

    This work deals with the study of interaction of E.M. fields with nuclear moments of nuclei emitting gamma rays. We describe first experiments on delayed angular correlation showing the role played by statistic quadrupole interaction. We have measured the magnetic moment of the second excited state of {sup 19}F using an external magnetic field. In the case of {sup 19}O, experiments of angular distributions and angular correlations of gamma -rays taking into account the possibility of perturbations, allow us to determine the spin and parities of the three first levels. (author) [French] Le present travail concerne l'etude de l'interaction des champs electromagnetiques et des moments nucleaires de noyaux emettant des rayonnements gamma. Nous decrivons des experiences de correlation angulaire differee dont l'interpretation met en coincidence le role joue par les interactions quadrupolaires statiques. Nous avons mesure le moment magnetique de {sup 19}F dans un etat excite en utilisant un champ magnetique exterieur a la source radioactive. Enfin, dans le cas de {sup 19}O, nous montrons l'utilite d'un examen des possibilites de perturbations dans l'interpretation des resultats fournis par des correlations ou des distributions angulaires. (auteur)

  9. 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.

  10. Collective phenomena in non-central nuclear collisions

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

    1979-09-01

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

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

    OpenAIRE

    Vlcek, Tomas; Jirusek, Martin

    2015-01-01

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

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

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  14. Current experience with central-station nuclear cogeneration plants

    International Nuclear Information System (INIS)

    1981-10-01

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

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

    International Nuclear Information System (INIS)

    1992-12-01

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

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

    International Nuclear Information System (INIS)

    Buglova, E.; Crick, M.; Reed, J.; Winkler, G. L.; Martincic, R.

    2000-01-01

    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)

  17. Nuclear DNA content variation among central European Koeleria taxa

    Czech Academy of Sciences Publication Activity Database

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

    2006-01-01

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

  18. Nuclear magnetic resonance imaging of the central nervous system

    International Nuclear Information System (INIS)

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

    1989-01-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  20. AP1000, a nuclear central of advanced design

    International Nuclear Information System (INIS)

    Hernandez M, N.; Viais J, J.

    2005-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-06-15

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

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

    International Nuclear Information System (INIS)

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

    2000-06-01

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

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

    International Nuclear Information System (INIS)

    Paulin, Ph.

    2006-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  5. Platinoids and molybdenum in nuclear waste containment glasses: a structural study; Les platinoides et le molybdene dans des verres d'interet nucleaires: etude structurale

    Energy Technology Data Exchange (ETDEWEB)

    Le Grand, M. [CEA/VALRHO - site de Marcoule, Dept. de Recherche en Retraitement et en Vitrification (DRRV), 30 - Marcoule (France)]|[Paris-7 Univ., 75 (France)

    2000-07-01

    This work deals with the structure of borosilicate nuclear glasses and with some relationships between structure and macroscopic properties. Two types of elements which may disturb the industrial process - platinoids (Ru and Pd) and molybdenum - are central to this work. Platinoids induce weak modifications on the structure of the glass, causing a depolymerization of the glassy network, an increase of the {sup [3]}B/{sup [4]}B ratio and a modification of the medium range order around Si between 3.3 and 4.5 angstrom. The modifications of viscosity and density induced by platinoids in the glass are not due to the structural effect of the platinoids. The increase of viscosity is attributed to needle shaped RuO{sub 2}. It can be moderated by imposing reducing conditions during the elaboration of the glass. The slight difference between experimental and calculated densities is due to the increase of the volume percentage of bubbles in the glass with increasing platinoid content. Mo is either present in the glass as molybdic groupings, or mobilized in chemically complex molybdic crystalline phases. The chemical composition and mineralogy of these phases has been obtained using electronic microprobe data and XRD with Rietveld analysis. The distribution of the different elements between the crystalline phases and the glass is strongly influenced by the structural role of the various cations in the glass. The Mo present in the glass appears as MoO{sub 4} tetrahedra, independent of the borosilicate network. The formation of the crystalline phases can be explained by the existence of a precursor in which the MoO{sub 4} tetrahedra are concentrated in rich alkali and earth-alkali bearing areas of the glass. (author)

  6. Platinoids and molybdenum in nuclear waste containment glasses: a structural study; Les platinoides et le molybdene dans des verres d'interet nucleaires: etude structurale

    Energy Technology Data Exchange (ETDEWEB)

    Le Grand, M [CEA/VALRHO - site de Marcoule, Dept. de Recherche en Retraitement et en Vitrification (DRRV), 30 - Marcoule (France); [Paris-7 Univ., 75 (France)

    2000-07-01

    This work deals with the structure of borosilicate nuclear glasses and with some relationships between structure and macroscopic properties. Two types of elements which may disturb the industrial process - platinoids (Ru and Pd) and molybdenum - are central to this work. Platinoids induce weak modifications on the structure of the glass, causing a depolymerization of the glassy network, an increase of the {sup [3]}B/{sup [4]}B ratio and a modification of the medium range order around Si between 3.3 and 4.5 angstrom. The modifications of viscosity and density induced by platinoids in the glass are not due to the structural effect of the platinoids. The increase of viscosity is attributed to needle shaped RuO{sub 2}. It can be moderated by imposing reducing conditions during the elaboration of the glass. The slight difference between experimental and calculated densities is due to the increase of the volume percentage of bubbles in the glass with increasing platinoid content. Mo is either present in the glass as molybdic groupings, or mobilized in chemically complex molybdic crystalline phases. The chemical composition and mineralogy of these phases has been obtained using electronic microprobe data and XRD with Rietveld analysis. The distribution of the different elements between the crystalline phases and the glass is strongly influenced by the structural role of the various cations in the glass. The Mo present in the glass appears as MoO{sub 4} tetrahedra, independent of the borosilicate network. The formation of the crystalline phases can be explained by the existence of a precursor in which the MoO{sub 4} tetrahedra are concentrated in rich alkali and earth-alkali bearing areas of the glass. (author)

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

    International Nuclear Information System (INIS)

    1977-10-01

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

  8. Annual report 89. Central Bureau for nuclear measurements

    International Nuclear Information System (INIS)

    1990-01-01

    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

  9. Possible uses of nuclear energy in central heating of Ankara

    International Nuclear Information System (INIS)

    Agirsoy, L.

    1987-01-01

    In this master thesis, a study was carried out for the district heating of the plateau region where the population and air pollution densities are the highest. First the heat requirements of differently populated regions were calculated, then by taking different temperature decreases of hot water in buildings; flow rates, pipe diameters and pressure losses corres-ponding to these temperature decreases were obtained. An optimum division of total heat load as peak and base loads was studied and it was seen that the unit heat cost could be lowered by employing two stations for the heating of buildings. The optimum division and unit heat cost calculations were carried out for various alternative heating systems and it was seen that nuclear combined cycle base-load station and a peak-load station operating on fuel-oil was obtained to be the most advantageous system from an economic point of view. (author)

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

    International Nuclear Information System (INIS)

    Peltzer, P.

    1986-01-01

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

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

    Science.gov (United States)

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

    2017-08-01

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

  12. Contribution to the experimental survey of the nuclear isomerism. Application of the deferred coincidences method to research and to the survey of metastable states of short period; Contribution a l'etude experimentale de l'isomerie nucleaire. Application de la methode des coincidences differees a la recherche et a l'etude d'etats metastables de periode courte

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1953-06-15

    Various methods of the physics brought many informations on the nuclear elements which one can arrange some ponderable quantities, what is the case of the steady elements and some, unsteady elements, as most of natural radioelements. On the other hand, elements of shorter life duration, and notably those that are carried to an excited state, are more badly known, and one can get information to their consideration that by the mediator of the properties of the transitions that they undergo, when they give birth has best-known nuclear cash: among these transitions represent the isomeric transitions. The goal of this work is the survey of the isomeric transitions from metastable states of short period, included in the domain of the microsecond to some milliseconds. The method of the deferred coincidences has been put to the point and applied in this goal while using the advantages of the selectors to several channels, under two main aspects where the device to several channels was either a selector of time, either a selector of amplitudes. This method served to study the working of Geiger-Muller counter and to measure with precision the period of {sup 181}Ta{sup *} in of the varied experimental conditions. The adopted value is 17,2 {+-}0,2 {mu}s. This work also found an immediate practical application to the setting in evidence of very weak quantities of hafnium in zirconium, of which it constitutes a tenacious and difficult impurity to analyze by the ordinary ways. (M.B.) [French] Les diverses methodes de la physique ont apporte de nombreux renseignements sur les especes nucleaires dont on peut disposer en quantites ponderables, ce qui est le cas des especes stables et de certaines especes instables, comme la plupart des radioelements naturels. Par contre, les noyaux de duree de vie plus courte, et notamment ceux qui sont portes a un etat excite, sont plus mal connus, et on ne peut obtenir de renseignements a leur egard que par l'intermediaire des proprietes des

  13. 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)

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  15. Study of the central collisions in the reactions Ni + Al and Ni + Ni at 28 A.MeV; Etude des collisions centrales dans les reactions Ni + Al et Ni + Ni a 28 A.MeV

    Energy Technology Data Exchange (ETDEWEB)

    Lebreton, L.

    1995-12-01

    The work is in characterisation of mechanisms in the energy range of onset of multifragmentation (excitation energy of composed nucleus around 4 - 5 AMeV). This work focused on an experiment performed at the SARA facility, in Grenoble, using the AMPHORA multi detection array. I have been particularly interested in central collisions in the Ni + Al and Ni + Ni systems. The possibility to detect complete events for Ni + Al, and quasi-complete events for the Ni + Ni case, is the reason of this choice. Furthermore Ni + Ni presents the interest of a symmetrical system, for which the excitation energy per nucleon is maximum. The study of these reactions has been focused on the quasi-complete events (events for which at least 80 % of the total charge has been detected). Heavy ions produced in peripheral collisions are very likely emitted along the beam line or stopped in the plastic detectors, energy thresholds are too high for the quasi-target products detection, consequently by requiring complete or quasi-complete measurement of the total charge, we are able to detect mostly central events. The knowledge of informations like charge, energy or detection angles allows to isolate the source(s) and to reconstruct the size and the excitation energy of the source(s). Comparisons with simulations like sequential emission (GEMINI code), very deep inelastic collision or instantaneous emission (Berliner code) allows to characterise the first stage of the collision (binary collisions or central collisions) and the type of deexcitation of the source(s). Some calculations was also performed with the statistical model code MODGAN. Indeed azimuthal correlations seem to be a good tool in getting more information about involved reaction mechanisms. Comparisons with MODGAN provide information about angular momentum of the source and time delay between emissions of the two particles (separation between sequential or instantaneous process). (author). 69 refs.

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

    International Nuclear Information System (INIS)

    Potter, W.C.

    1997-01-01

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

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

    International Nuclear Information System (INIS)

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

    2011-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-12-15

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

  19. A study of the fluorescence of the rare gases excited by nuclear particles. Use of the principle for the detection of nuclear radiation by scintillation; Etude de la fluorescence des gaz rares excites par des particules nucleaires. Utilisation pour la detection des rayonnements nucleaires par scintillation

    Energy Technology Data Exchange (ETDEWEB)

    Koch, L [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-12-15

    In the first part is studied the properties of atoms excited by the passage of {alpha} particles through the various rare gases at atmospheric pressure. A spectral analysis of the emitted light showed that certain impurities play an important part in producing the fluorescence, and it has led to the conclusion that the light emission contains at least two components - one very short - lived due to the direct deexcitation of the rare gas, the other relatively slower due to the energy transfers to the impurity. The measurement of the life-time of the excited states has confirmed this foregoing hypothesis, the rapid part of the impulse is extremely short: less than 2,25.10{sup -9} s in the case of xenon; the slower part has a life-time depending directly on the nitrogen concentration, nitrogen being the impurity giving the largest effect in all cases. The study of rare gases under the influence of an electric field has made it possible to show that the amount of light produced by an {alpha} particle can be multiplied (by 60, for example, in a field of 600 V:cm) so that the luminescent efficiency is greater than in the case of INaTI. In the second part the characteristics of the rare gases acting as scintillators is examined, the most important property being the absence of fluorescence saturation when the intensity of the excitation incident on the gas is very large. This, together with the very short time of scintillation has made it possible to study a certain number of nuclear physical applications (heavy particle energy-measurements, kinetic studies on nuclear reactors, neutron spectroscopy). (author) [French] On etudie dans la premiere partie les proprietes des atomes excites par le passage de particules {alpha} dans les differents gaz rares a la pression atmospherique. L'etude spectrale de la lumiere emise a montre que certaines impuretes jouent un role considerable dans la fluorescence et on a ete amene a penser que l'emission de lumiere comporte au moins deux

  20. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann-Boutron, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

  1. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann-Boutron, F. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

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

  3. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Mirambel Boquera, J.

    2011-07-01

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

  5. The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

  6. Engineering for new-built nuclear power plant projects; Ingenieria para proyectos de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

    This article reviews the opportunities existing in the market (electrical utilities and reactor vendors) for an engineering company with the profile of Empresarios Agrupados (EA) in new-built nuclear power plant projects. To do this, reference is made to some representative examples of projects in which EA has been participating recently. the article concludes sharing with the reader some lessons learned from this participation. (Author)

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

    Goetzke, R.E.

    1987-01-01

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

  12. Contribution to the study of thermal mixing between nuclear spin systems; Contribution a l'etude du melange thermique entre systemes de spins nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Goldmann, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-02-15

    This work describes methods of dynamic nuclear polarization in solids based on the thermal mixing between nuclear spin systems. The description of the thermal mixing processes involves most of the fundamental aspects of the spin temperature theory. The experiments, conducted with paradichlorobenzene and para-dibromobenzene, yield a detailed confirmation of the theoretical predictions. (author) [French] Ce travail decrit des methodes de polarisation dynamique nucleaire dans les solides basees sur le melange thermique entre systemes de spins nucleaires. La description des processus de melange thermique met en jeu la plupart des aspects fondamentaux de la theorie de la temperature de spin. Les experiences, realisees avec du paradichlorobenzene et du paradibromobenzene, apportent une confirmation detaillee des previsions theoriques. (auteur)

  13. Study of the closure of the nuclear shells N = 16, 20, 28 and 40; Etudes des fermetures de couches nucleaires N=16, 20, 28 et 40

    Energy Technology Data Exchange (ETDEWEB)

    Sorlin, O

    2005-12-15

    There are 2 types of nuclear shell closures: one is associated to a number of the harmonic oscillator, typically N = 20 and 40, and the other is a consequence of the spin-orbital interaction that produces magic numbers such as N = 28, 50, 82 and N = 126. The first part of this work deals with the knowledge accumulated around the closure of the N = 28 shell. 3 means of investigation have been used: -) the study of beta decay nuclei (K{sup 47}, Ar{sup 46}, S{sup 44}, Si{sup 42} and Cl{sup 45}), -) the on-line spectroscopy of nuclei around N = 28, and -) the study of Ar{sup 45} and Ar{sup 47} through transfer reactions. The second part is dedicated to results concerning the nuclear structure of nuclei around N = 14-20 and around N = 40. (A.C.)

  14. Heavy particle scattering by atomic and nuclear systems; Etude de la diffusion de particules lourdes sur des systemes atomiques et nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Lazauskas, R

    2003-10-01

    In this thesis quantum mechanical non-relativistic few-body problem is discussed. Basing on fundamentals ideas from Faddeev and Yakubovski three and four body equations are formulated and solved for fermionic atomic and nuclear systems. Former equations are modified to include long range interactions. Original results for nuclear and molecular physics were obtained: -) positively charged particle scattering on hydrogen atoms was considered; predictions for {pi}{sup +} {yields} H, {mu}{sup +} {yields} H and p{sup +} {yields} H scattering lengths were given. Existence of an unknown, very weakly bound H{sup +}{sub 2} bound state was predicted. -) Motivated by the possible observation of bound four neutron structure at GANIL we have studied compatibility of such an existence within the current nuclear interaction models. -) 4 nucleon scattering at low energies was investigated. Results for n {yields} {sup 3}H, p {yields} {sup 3}H and p {yields} {sup 3}He systems were compared with the experimental data. Validity of realistic nucleon-nucleon interaction models is questioned. (author)

  15. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes; Etude par spectroscopie atomique de proprietes nucleaires d'isotopes de francium et de cesium

    Energy Technology Data Exchange (ETDEWEB)

    Coc, A

    1986-04-15

    This work is based on the study of cesium ({sup 118,146}Cs) and francium ({sup 207-213}Fr,{sup 220-228}Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  16. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes; Etude par spectroscopie atomique de proprietes nucleaires d'isotopes de francium et de cesium

    Energy Technology Data Exchange (ETDEWEB)

    Coc, A

    1986-04-15

    This work is based on the study of cesium ({sup 118,146}Cs) and francium ({sup 207-213}Fr,{sup 220-228}Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  17. Asco 2044 nuclear power plant: management system; Central nuclear Asco 2044: sistema de gestion

    Energy Technology Data Exchange (ETDEWEB)

    Ramos Pellejero, J.L.

    2010-07-01

    Due to their complexity and involvement in safety related matters, Nuclear Power Plants have highly eliable management organisations where safety is top priority. To achive this, there are many elements specific to this type of organisation that are available and which are integrated within a Management System that comprises the necessary meassures to ensure and adequate level of safety in the facility, in such a way that it promotes continual improvement, a strengthening of the safety culture and good results in this field. (Author).

  18. 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)

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

    International Nuclear Information System (INIS)

    Zafer, A.

    2006-01-01

    Full text: On the first call for expanding peaceful uses of nuclear energy, Turkey was one of the first countries to start activities in the nuclear field. Turkish Atomic Energy Authority (TAEK) was established in 1956 and became the member of the International Atomic Energy Agency (IAEA) established in 1957 by the United Nations for spreading the use of nuclear energy to contribute peace, health and prosperity throughout the world, in the same year. TAEK was established to support, co-ordinate and perform the activities in peaceful uses of nuclear energy and act as a regulatory body and establish cooperation with other countries and international organizations. In the late 1990's, TAEK, besides building cooperation with various countries, has involved in cooperating with related institutes of Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan for establishment of bilateral and multilateral scientific and technical cooperation in peaceful use of nuclear energy and signed protocols with Academy of Science of Azerbaijan, Nuclear Physics Institute of Kazakhstan, National Academy of Science of Kyrgyzstan and Institute of Nuclear Physics of Uzbekistan Academy of Science. Turkey is a candidate state to join the European Union and has already signed Custom Union Agreement, also part of the Eurasia Region. So, there are significant developments in the cultural, social, technical, economical and trade relations owing to our common historical and cultural values with the countries in the region and Central Asia. These protocols enable parties to organize joint projects, conferences, seminars, training programs, establish laboratories for the joint studies and make joint efforts to seek support from their governments and international organizations for these activities. The joint activities carried out mainly are given as follows: Eurasia Conference on Nuclear Science and Its Application - First Conference organized in the year 2000 in Turkey, Second Conference at Almaty? in

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

    International Nuclear Information System (INIS)

    Pande, Savita

    1998-01-01

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

  1. Study of some continuous spectra produced by nuclear reactions with light nuclei; Etude de quelques spectres continus produits par reactions nucleaires avec des noyaux legers

    Energy Technology Data Exchange (ETDEWEB)

    Marquez, L

    1966-07-01

    The continuous spectra coming from several nuclear reactions with light nuclei were measured. The spectra can be explained by a two-step reaction mechanism; however, the reactions produced by {sup 6}Li are different. A mechanism was proposed to explain their spectra based on the following assumptions: {sup 6}Li makes a nuclear molecule with the target which subsequently breaks up in such a way that an {alpha} particle comes out with the kinetic energy that it has in the molecule. The calculated spectra and those measured are in good agreement. (author) [French] Nous avons mesure les spectres continus produits dans plusieurs reactions nucleaires avec des noyaux legers. A l'exception des spectres produits par {sup 6}Li, on a trouve qu'on pouvait expliquer ces spectres par le mecanisme des reactions en deux etapes. Nous avons propose un mecanisme pour expliquer les spectres produits par {sup 6}Li. On suppose que {sup 6}Li forme une molecule nucleaire avec la cible qui eclate ensuite de facon telle qu'une particule alpha de la molecule sort avec l'energie cinetique de son mouvement propre dans la molecule. Les spectres calcules avec ces hypotheses et les spectres mesures sont en bon accord. (auteur)

  2. Theoretical study of trivalent element complexes for the nuclear waste reprocessing; Etude theorique de complexes d'elements f trivalents pour le retraitement des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Petit, L

    2007-10-15

    Current energetic and environmental concerns have made the nuclear waste reprocessing to be a major issue in numerous countries. One avenue to treat nuclear spent fuel requires separating selectively trivalent minor actinides An (Am{sup 3+}, Cm{sup 3+}) from lanthanides Ln. In this regard, nitrogen extractants are under study. Their selectivity toward actinides is still unclear, but could be the result of enhanced covalency effects with trivalent minor actinides with respect to lanthanides (III). In this thesis, we have performed DFT calculations (Density Functional Theory) to study covalency effects within the actinide-ligand bond, following three main axes of research: advanced study of the nature of the chemical bonding, spectroscopic characterization of covalency, and preliminary tests of ab initio molecular dynamics for future calculations in solvent. Methods that are not regularly applied to trivalent actinides complexes have been used: topological methods, TDDFT, LDDFT, ab initio molecular dynamics. We have managed to show that the selectivity of the BTP ligand - the most effective An/Ln extractant to date - comes at least for a part from stronger covalency effects within the An-BTP bond with respect to the Ln-BTP bond, which has never been proved before. (author)

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

    International Nuclear Information System (INIS)

    Schmid, J.

    1991-04-01

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

  4. Contribution to the study and use of ionisation chambers for nuclear reactor control (1965); Contribution a l'etude et a l'utilisation des chambres d'ionisation pour le controle des reacteurs nucleaires (1965)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-02-15

    At the moment ionisation chambers are the detectors which are best suited to the task of nuclear reactor control by neutronic measurements. We have thought it wise to state some generalities concerning reactor dynamics, the various neutron detection methods, the working of ionisation chambers and the measurement methods used. Our contribution to reactor control techniques consists on the one hand in an attempt to make a synthesis of the factors influencing the operation of ionisation chambers, the study of these factors, and on the other hand in the development of ionisation chambers of the fission and boron types, making it possible to follow the working of a reactor from the moment it starts up until maximum power is attained. In the field of fission chambers, we have in particular improved the technique for depositing uranium oxide on aluminium and have perfected the electrolytic deposition process on other metals: stainless steel, copper, molybdenum, nickel, tantalum, titanium, kovar, tungsten and beryllium. We have developed several types of fission chambers used during the start-up of reactors: one type of medium performance now in use in French piles one high-sensitivity type one high-temperature type which has operated up to 600 deg. C. As far as boron chambers are concerned, we have studied the perturbations caused to the measurement by the exposure of the chamber to high neutron flux and to a very strong {gamma} radiation. This exposure brings about a modification of the properties of the constituent materials and causes a background noise in the chamber which can seriously handicap the neutron measurements. We have shown that the compensation technique makes it possible to limit this noise and to thereby increase the range of measurement of conventional ionisation chambers intended for power measurements. Finally, we have built two types of compensation chambers used in the French reactors and have begun the study of a third type of high sensitivity for

  5. A study of switch circuits for use as safety devices in nuclear reactors; Etude de circuits de commutation destines a la securite des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Hantcherian, V [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1960-12-15

    The author reviews briefly a few basic assemblies using electromagnetic relays for safety circuits in nuclear reactors; he then studies the use of static relays with a shorter time of response, based on impedance changes in a self-inductance consisting of a coil with a magnetic core having a rectangular hysteresis cycle. The author examines in particular the way in which it functions and the method of determining the parameters. (author) [French] L'auteur apres avoir examine sommairement en revue quelques montages de base des circuits de securite des reacteurs nucleaires utilisant des relais electromecaniques, etudie l'emploi des relais statiques a plus grande vitesse de reponse bases sur la variation d'impedance que presente une self-inductance realisee a l'aide d'une bobine enroulee autour d'un noyau magnetique a cycle d'hysteresis rectangulaire. En particulier, il en examine le mode de fonctionnement et la determination des parametres. (auteur)

  6. Contributions to safety studies for new concepts of nuclear reactors; Contributions aux etudes de surete pour des filieres innovantes de reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Perdu, F

    2003-12-01

    The complete study of molten salt reactors, designed for a massive and durable nuclear energy production, must include neutronics, hydraulics and thermal effects. This coupled study, using the MCNP and Trio{sub U} codes, is undertaken in the case of the MSRE (molten salt reactor experiment) prototype. The obtained results fit very well the experiment. Their extrapolation suggests ways of improving the safety coefficients of power molten salt reactors. A second part is devoted to accelerator driven subcritical reactors, developed to incinerate radioactive waste.We propose a method to measure the prompt reactivity from the decay following a neutron pulse. It relies only on the distribution of times between generations, which is a characteristic of the reactor. This method is implemented on the results of the MUSE 4 experiment, and the obtained reactivity is accurate within 5%. (author)

  7. Application of wavelet analysis to the nuclear phase space study; Application de l`analyse en ondelettes a l`etude de l`espace des phases nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Jouault, B. [Nantes Univ., 44 (France)

    1996-11-22

    The objective of this thesis is to present a methodology, based on the projection methods used in statistical physics and on the wavelet approach, which allows to obtain various classes of information. A coherent modelling was elaborated as the tools used for generating and solving the evolution equations, expressed in terms of pertinent variables, are based on common concepts. The property of scale separation of the wavelet analysis allows an approximation hierarchy based on the geometrical structure of phase space to be defined. This information structuration offers the opportunity of solving the evolution equations with various degrees of precision by controlling the information loss and avoiding the sampling methods of Monte Carlo type. The application of this methodology to the case of heavy ion collisions needs an entirely numerical treatment of the density matrix evolution equation. This implies a very precise level of description in order to take into account the important dissipation effects occurring in intermediate energy nuclear dynamics. A proper solution less expensive was adopted by using the wavelets analytically expressed, this entailing also the testing of model validity by comparing its results with the analytical solutions. This model takes into account the structure of the system wave functions, thus conserving the microscopical information. The present methodology can be applied also at other energy domains providing the nuclear systems are subject to transient non steady-state regimes. The wavelet analysis was used extensively in the field of signal processing particularly to extract from background a physical signal and also in the field of turbulence phenomena 152 refs.

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

    International Nuclear Information System (INIS)

    Sychou, A.

    1997-01-01

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

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

    International Nuclear Information System (INIS)

    Ventura, M.

    2006-01-01

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

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

    International Nuclear Information System (INIS)

    Tomik, L.; Kichev, E.

    2003-01-01

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

  11. Study of nuclear glasses alteration gel and synthesis of some model gels; Etude du gel d`alteration des verres nucleaires et synthese de gels modeles

    Energy Technology Data Exchange (ETDEWEB)

    Ricol, S

    1995-10-05

    This work deals with the general problem of alteration of the reference nuclear glass R7T7. Attention is paid particularly to the altered layer formed at the glass surface during alteration process. In opposition to previous works, related essentially to glass dissolution kinetics based on chemical analyses of lixiviated elements, this thesis deals with alteration problems through structural studies of the reference glass and derived gel. This approach allows the determination of mechanisms for the gel formation and a better understanding of the behaviour of glasses towards lixiviation. Both approaches appeared complementary. Based on several spectroscopic techniques, this work showed the particular role of cations such as calcium, zirconium and iron. Studies of silica-based synthetic gels showed the synergic effect of formers cation and of one highly coordinated cation. The variation of the wavenumber related to Si-O-Si asymmetric stretching vibration can be correlated to O/Si ratio for ternary systems Si/Na/Zr. On the contrary, the Si losses of the materials depend on the number of non-bridging oxygen atoms. In the perspective of long-term behaviour, the alteration gel presents better characteristics than initial glass. It is therefore a highly stable material in static conditions. In the same way, synthetic gels are materials with very low solubilities (much lower than the alteration gel) and could be used as confining matrices. (authors). refs., 71 figs., 37 tabs.

  12. Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

    Robert, C. [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1962-07-01

    Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

  13. Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

    Robert, C [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1962-07-01

    Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Hendricks, J.R.

    1996-01-01

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

  16. Thermal stability of the French nuclear waste glass - long term behavior modeling; Etude de la stabilite thermique du verre nucleaire. Modelisation de son evolution a long terme

    Energy Technology Data Exchange (ETDEWEB)

    Orlhac, X

    2000-07-01

    The thermal stability of the French nuclear waste glass was investigated experimentally and by modeling to predict its long-term evolution at low temperature. The crystallization mechanisms were analyzed by studying devitrification in the supercooled liquid. Three main crystalline phases were characterized (CaMoO{sub 4}, CeCO{sub 2}, ZnCr{sub 2}O{sub 4}). Their crystallisation was TO 4.24 wt%, due to the low concentration of the constituent elements. The nucleation and growth curves showed that platinoid elements catalysed nucleation but did not affect growth, which was governed by volume diffusion. The criteria of classic nucleation theory were applied to determine the thermodynamic and diffusional activation energies. Viscosity measurements illustrate the analogy between the activation energy of viscous flow and diffusion, indicating control of crystallization by viscous flow phenomena. The combined action of nucleation and growth was assessed by TTT plots, revealing a crystallization equilibrium line that enables the crystallized fractions to be predicted over the long term. The authors show that hetero-genetics catalyze the transformation without modifying the maximum crystallized fraction. A kinetic model was developed to describe devitrification in the glass based on the nucleation and growth curves alone. The authors show that the low-temperature growth exhibits scale behavior (between time and temperature) similar to thermo-rheological simplicity. The analogy between the resulting activation energy and that of the viscosity was used to model growth on the basis of viscosity. After validation with a simplified (BaO{sub 2}SiO{sub 2}) glass, the model was applied to the containment glass. The result indicated that the glass remained completely vitreous after a cooling scenario with the one measured at the glass core. Under isothermal conditions, several million years would be required to reach the maximum theoretical crystallization fraction. (author)

  17. Contribution to the study of thermal-hydraulic problems in nuclear reactors; Contribution a l`etude de problemes de thermohydraulique dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Cognet, G

    1998-07-07

    In nuclear reactors, whatever the type considered, Pressurized Water Water Reactors (PWRs), Fast Breeder reactors (FBRs)..., thermal-hydraulics, the science of fluid mechanics and thermal behaviour, plays an essential role, both in nominal operating and accidental conditions. Fluid can either be the primary fluid (liquid or gas) or a very specific fluid called corium, which, in case of severe accident, could result from core and environning structure melting. The work reported here represents a 20-year contribution to thermal-hydraulic issues which could occur in FBRs and PWRs. Working on these two types of reactors, both in nominal and severe accident situations, has allowed me to compare the problems and to realize the importance of communication between research teams. The evolution in the complexity of studied problems, unavoidable in order to reduce costs and significantly improve safety, has led me from numerical modelling of single-phase flow turbulence to high temperature real melt experiments. The difficulties encountered in understanding the observed phenomena and in increasing experimental databases for computer code qualification have often entailed my participation in specific measurement device developments or adaptations, in particular non-intrusive devices generally based on optical techniques. Being concerned about the end-use of this research work, I actively participated in `in-situ` thermalhydraulic experiments in the FBRs: Phenix and Super-Phenix, of which I appreciated their undeniable scientific contribution. In my opinion, the thermal-hydraulic questions related to severe accidents are the most complex as they are at the cross-roads of several scientific specialities. Consequently, they require a multi-disciplinary approach and a continuous see-saw motion between experimentalists and modelling teams. After a brief description of the various problems encountered, the main ones are reported. Finally, the importance for research teams to

  18. The design and construction of a nuclear free-precession magnetometer; Etude et realisation d'un magnetometre a precession libre nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Baconnier, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1960-10-15

    After presenting the advantages of nuclear magnetic resonance with respect to electromagnetic processes, as far as the measurement of the earths' magnetic field is concerned, we deal with the macroscopic theory for the Bloch model and analyse Packard and Varions' experiment. The development of a particular absolute free-precession magnetometer is studied, and the conditions are determined for obtaining a maximum amplitude signal as a function of the geometrical form of the detector coil, of the method of cut-off, and of the coupling between various parts of the system. After having described in detail the technology of amplifiers, we consider the problem of the measurement of the frequency of precession for which an original solution, of analogy form, is proposed and discussed. Complete plans of the equipment are given in an appendix. (author) [French] Apres avoir presente les avantages de la resonance magnetique nucleaire relativement aux procedes electromagnetiques, en ce qui concerne la mesure du champ magnetique terrestre, on traite de la theorie macroscopique dans le modele de Bloch et analyse l'experience de Packard et Varian. On etudie une realisation particuliere d'un magnetometre absolu a precession libre et determine les conditions d'obtention d'un signal d'amplitude maximale en fonction de la forme geometrique du bobinage detecteur, de la methode de coupure, et du couplage entre les differents elements du montage. Apres avoir decrit en detail la technologie des amplificateurs, on aborde le probleme de la mesure de la frequence de precession, pour laquelle une solution originale, sous forme analogique, est proposee et discutee. En annexe est joint un dossier complet des plans de la realisation. (auteur)

  19. Contribution to the study of nuclear fuel materials with a metallic uranium base; Contribution a l'etude des materiaux combustibles nucleaires a base d'uranium metallique

    Energy Technology Data Exchange (ETDEWEB)

    Englander, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-11-15

    In a power reactor destined to supply industrially recoverable thermal energy, the most economical source of heat still consists of natural metallic uranium. However, the nuclear fuel material, most often employed in the form of rods of 20 to 40 mm diameter, is subjected to a series of stresses which lead to irreversible distortions usually incompatible with the substructure of the reactor. As a result the fuel material must possess at the outset a certain number of qualities which must be determined. Investigations have therefore been carried out, first on the technological characters peculiar to each of the three allotropic phases of pure uranium metal, and on their interactions on the stabilisation of the material which consists of either cast uranium or uranium pile-treated in the {gamma} phase. (author) [French] Dans un reacteur de puissance destine a fournir de l'energie thermique industriellement recuperable, la source de chaleur la plus economique reste constituee par de l'uranium metallique naturel. Or, le materiau combustible nucleaire, employe le plus souvent sous forme de barreaux de 20 a 40 mm de diametre, se trouve soumis a un ensemble de contraintes qui provoque des deformations irreversibles, le plus souvent incompatibles avec l'infrastructure du reacteur. Par consequent, le materiau combustible doit presenter a l'origine un certain nombre de qualites qu'il est necessaire de determiner. Aussi a-t-on d'abord etudie les caracteres technologiques propres a chacune des trois phases allotropiques de l'uranium-metal pur et leurs interactions sur la stabilisation du materiau constitue soit par de l'uranium coule, soit par de l'uranium traite en pile en phase {gamma}. (auteur)

  20. Contribution to the study of solid helium-3 by nuclear magnetic resonance; Contribution a l'etude de l'helium trois solide par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Landesman, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    Due to the unusually large zero point motion of helium three atoms in the solid, the overlap of the atomic wave functions is very important. As a consequence, there are exchange interactions, the theoretical calculation and the experimental measurement of which are discussed. Nuclear magnetic resonance is especially well suited for the latter.A detailed theory is given for both exchange narrowing and Zeeman-exchange cross relaxation, which phenomena are used to measure the exchange interaction as a function of molar volume. The alignment temperature is thus known; it goes down when the pressure goes up and is never higher than three milli degrees. An influence of helium four impurities on the exchange interactions between helium three atoms which are neighbours of the substitutional He is shown. (author) [French] Par suite de l'amplitude exceptionnelle des mouvements de point zero dans l'helium trois solide, le recouvrement des fonctions d'onde atomiques est tres important. Il en resulte des interactions d' echange dont on discute l'evaluation theorique et la mise en evidence experimentale. Cette derniere peut se faire par resonance magnetique; on etudie theoriquement les phenomenes de retrecissement par echange et de relaxation Zeeman-echange que l'on met a profit pour determiner les interactions d'echange en fonction du volume molaire. On en deduit que la temperature d'alignement nucleaire diminue quand on comprime le solide et est au plus de 3x10{sup -3} K. L'influence des impuretes d'helium quatre sur les interactions d'echange entre atomes {sup 3}He voisins de {sup 4}He est mise en evidence. (auteur)

  1. Magnetic resonance studies of solid polymers; Etude des polymeres solides par resonance magnetique

    Energy Technology Data Exchange (ETDEWEB)

    Lenk, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-07-01

    This paper is a review of the application of nuclear magnetic resonance (NMR) to solid polymers. In the first, theoretical part, the elements of the theory of NMR, which are necessary for the study of the properties of solid polymers are discussed: the moments method, nuclear relaxation and the distribution of correlation times. In the second part the experimental results are presented. (author) [French] Cette etude est une recherche bibliographique sur l'application de la resonance magnetique nucleaire (RMN) aux polymeres solides. Dans la premiere partie theorique on discute les elements de la theorie de RMN, necessaires pour l'etude des proprietes des polymeres solides: la methode des moments, la relaxation nucleaire et la distribution des temps de correlation. La deuxieme partie presente les resultats des experiences. (auteur)

  2. Case Study in Internal Audit of Nuclear Material; Etude d'un Systeme de Verification Comptable Interne des Matieres Nucleaires; Izuchenie primera organizatsii vnutrennego ucheta yadernykh materialov na predpriyatii; Estudio de la Fiscalizacion Interna de los Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kops, S. [United States Atomic Energy Commission, Argonne, IL (United States)

    1966-02-15

    The general need for the internal audit function and the basic principles of management underlying this need are briefly discussed. The size, complexity and degree of centralization, or decentralization, are usually the main factors in determining the need for a conventional internal audit. Here, the more specialized needs and characteristics of an internal audit peculiar to an organization handling source or special fissionable material (nuclear material) are discussed and contrasted with an audit of the standard type. The necessity of a special audit, because of the high monetary and strategic value, is demonstrated. Planning the internal audit within a production plant is discussed in detail. This includes the rationale of timing the review together with the records and physical inventory to be tested and verified. Quality and types of professional skills of the personnel to be used in internal audit are also discussed. A qualified statistical plan in choosing the items to be tested is discussed. The application of the plans in the actual performance of the internal audit are described in detail. Possible variances from a recognized norm and possible approaches to audit resolution are discussed. Although in many other manufacturing situations there are variations in the methods of verifying inventories without physically doing so, the necessity for physically testing inventories of nuclear material is demonstrated. The various means of reporting the results of the internal audit are presented. The needs of individual groups within the organization are considered in determining the format of the report, as well as the basic content. Distribution of the report and its variations are discussed. (author) [French] L'auteur etudie brievement la necessite de la verification comptable interne en general, et les principes essentiels de gestion auxquels repond cette necessite. La taille de l'installation, la complexite et le degre de centralisation ou de decentralisation

  3. Contribution to the study of several chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses; Contribution a l'etude de quelques nuisances chimiques au centre d'etudes nucleaires de Fontenay-aux-Roses

    Energy Technology Data Exchange (ETDEWEB)

    Megemont, C; Grau, C [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-10-01

    From the checking of 2750 index cards of hazards, the study relates the distribution of the chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses. Those concerning the greatest number of agents in the Centre are classified according to the categories corresponding to the different conditions of working. Thus, the most important are put forward. Then, the authors rapidly make a review of hazards which may have some special interest because they appear more specific of the nuclear energy or because they are the most frequently noted on the index cards of hazards. The case of the tributylphosphate is studied more precisely. (authors) [French] A partir de l'examen de 2750 fiches de nuisances, l'etude porte sur la repartition des nuisances chimiques au Centre d'Etudes Nucleaires de Fontenay-aux-Roses. Celles qui concernent le plus grand nombre d'agents du Centre sont classees selon les categories correspondant aux differentes conditions de travail. Les plus importantes d'entre elles sont ainsi mises en evidence. | Les auteurs passent ensuite en revue, rapidement, les nuisances qui peuvent presenter un interet particulier soit parce qu'elles semblent plus specifiques de l'Energie Nucleaire, soit parce qu'on les rencontre le plus frequemment sur les fiches de nuisances. Le cas du tributylphosphate est envisage de facon plus detaillee. (auteurs)

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

    International Nuclear Information System (INIS)

    Getzner, M.

    2003-01-01

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

  5. The First Two Years of Operating Experience of the Kahl Nuclear Power Station; Experience acquise pendant les deux premieres annees de fonctionnement de la centrale nucleaire de Kahl; Opyt pervykh dvukh let ehkspluatatsii atomnoj ehlektrostantsii v Kale; Experiencia adquirida en los primeros cuatro anos de funcionamiento de la central nucleoelectrica de Kahl

    Energy Technology Data Exchange (ETDEWEB)

    Bruchner, H. J. [Aeg-Kernenergieanlagen, Frankfurt-am-Main (Germany); Weckesser, A. [Versuchs-Atomkraftwerk Kahl Gmbh, Kahl (Germany)

    1963-10-15

    , une boucle experimentale destinee a l'etude de la surchauffe nucleaire. (author) [Spanish] La central de Kahl constituye la primera central nucleoelectrica europea de propiedad privada, y funciona en carga desde junio de 1961. Esta equipada con un reactor de agua hi que trabaja en ciclo indirecto por circulacion natural. Su capacidad electrica neta asciende a 15 MW y hasta febrero de 1963 habia producido 140 millones de kWh. La memoria revisara la experiencia adquirida durante su funcionamiento, ante todo con el extenso programa de ensayos sobre el comportamiento transitorio y la exploracion gamma. Presentara datos acerca del resultado que han dado en funcionamiento ciertas partes de la central, tales como el dispositivo de accionamiento de las barras de control, el sistema de purificacion de los gases de escape y la turbina. Una vez terminado el programa de ensayos, la planta se exploto en carga basica durante algun tiempo a fin de reunir datos sobre el rendimiento del combustible en la ptactica. Una vez completada esta fase, se instalara en el reactor de Kahl un circuito experimental de sobrecalentamiento nuclear. (author) [Russian] Atomnaya ehlektrostantsiya v Kale, pervaya v Evrope chastnaya atomnaya ehlektrostantsiya, ehkspluatiruetsya pod nagruzkoj s iyunya 1961 goda. Na ehlektrostantsii ustanovlen reaktor s kipyashchej vodoj, kosvennym tsiklom i estestvennoj tsirkulyatsiej. Chistaya ehlektricheskaya moshchnost' reaktora sostavlyaet 15 mgvt. Do fevralya 1963 goda kolichestvo poluchennoj ehnergii sostavilo 140 mln. kvt.ch. Rassmotren opyt ehkspluatatsii, v chastnosti rasshirennaya programma ispytanij: naprimer,povedenie reaktora pri perekhodnom protsesse i kontrol' gamma-izlucheniya. Budut predstavleny rezul'taty izucheniya ehkspluatatsionnoj kharakteristiki nekotorykh komponentov ustanovki, naprimer sistemy privoda reguliruptsikh sterzhnej, sistemy udaleniya gaza i turbiny. Posle osushchestvleniya ehtoj programmy ispytanij ustanovka v techenie nekotorogo vremeni

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-15

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-15

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

  10. 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.

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

    International Nuclear Information System (INIS)

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

    2006-02-01

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

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

    International Nuclear Information System (INIS)

    Nakayama, Naoki

    1998-01-01

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

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

    An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author) [French] Le memoire donne un apercu de l'organigramme d'une centrale nucleaire du CEGB et des conditions auxquelles doit satisfaire le personnel (formation, qualifications requises pour la fonction d'operateur). Il rend compte egalement de l'experience acquise a ce jour quant a l'interet qu'il y a a former le personnel au prealable et a etablir des plans d'operation detailles. (author) [Spanish] La memoria informa sobre la organizacion de las centrales nucleoelectricas de la CEGB y sobre la plantilla de personal que estas requieren. Discute la formacion del personal y los requisitos para obtener la licencia de operador de reactores. Describe la experiencia adquirida hasta el presente en materia de formacion previa del personal y de organizacion detallada de las operaciones. (author) [Russian] Daetsya otchet o trebovaniyakh, pred{sup y}avlyaemykh k personalu, i organizatsiya nabora personala na atomnykh ehlektrostantsiyakh Tsentral'nogo upravleniya proizvodstva ehlektroehnergii (CEGB). Obsuzhdayutsya voprosy podgotovki personala i normativnykh trebovanij, pred{sup y}avlyaemykh k ehkspluatatsionnomu personalu. Izlagaetsya opyt, nakoplennyj k nastoyashchemu vremeni v rezul'tate osushchestvleniya predehkspluatatsionnoj podgotovki i podrobnogo planirovaniya v usloviyakh ehkspluatatsii. (author)

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

    International Nuclear Information System (INIS)

    Gortnar, O.; Stritar, A.

    1999-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Chris Looney

    2014-04-01

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

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

    Science.gov (United States)

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

    2014-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  19. 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.

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

    International Nuclear Information System (INIS)

    Aguiar, J.C.; Fernandez, J.

    2006-01-01

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

  1. 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

  2. ETUDE - European Trade Union Distance Education.

    Science.gov (United States)

    Creanor, Linda; Walker, Steve

    2000-01-01

    Describes transnational distance learning activities among European trade union educators carried out as part of the European Trade Union Distance Education (ETUDE) project, supported by the European Commission. Highlights include the context of international trade union distance education; tutor training course; tutors' experiences; and…

  3. Internet applications in nuclear power plant operation management; Aplicaciones de internet en la gestion de la explotacion de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Munoz, M. [Empresarios Agrupados, A. I. E. Madrid (Spain)

    2000-07-01

    The use of the Internet is quickly becoming widespread in practically all areas of business and industry. The nuclear industry should not remain indifferent to this new trend. This paper analyses some of the Internet applications that can be easily adapted to nuclear power plant operation management, including. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

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

  5. 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.)

  6. The dynamic behaviour of heat exchangers; Etude du comportement dynamique des echangeurs de chaleur

    Energy Technology Data Exchange (ETDEWEB)

    Fonteray, J; Rozenholc, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-07-01

    In order to study the dynamics of nuclear power plants, one needs mathematical models made up of ordinary differential equations. This report deals with models for heat exchangers. These models allow exact evaluations of the temperatures for any steady state. The deformation of the temperature maps during transients is taken into account. To do this, average temperatures are evaluated keeping In mind, on one hand the partial differential equations, on the other hand, the physical phenomenons which are involved. Seven ordinary differential equations at most, are necessary for one heat exchanger. Theses models were compared with mathematically exact ones and also with experimental results, that EDF was able to measure on EDF-1 heat exchangers. The results appear to be correct. (authors) [French] Les etudes de dynamique sur les centrales nucleaires exigent l'elaboration de modeles apparaissant sous forme d'equations differentlelles ordinaires. Ce rapport est consacre a la recherche de modeles d'echangeurs. Dans ces modeles les temperatures sont calculees exactement pour n'importe quel regime permanent. Pour tenir compte de la deformation des distributions de temperature en regime transitoire, on evalue les temperatures moyennes dans l'echangeur en s'appuyant, d'une part, sur les equations aux derivees partielles et, d'autre part, sur une analyse des phenomenes physiques. Les modeles contiennent au plus sept equations differentielles ordinaires. Ces modeles ont ete compares aux modeles mathematiques exacts et aussi a des resultats experimentaux, obtenus par l'EDF, sur les echangeurs d'EDF-1. Les resultats paraissent satisfaisants. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

    Esteban, G.

    2014-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

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

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

    International Nuclear Information System (INIS)

    Peltzer, P.

    1983-01-01

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

  10. US central station nuclear electric generating units: significant milestones (status as of January 1, 1979)

    International Nuclear Information System (INIS)

    1979-03-01

    Construction and operational milestones are tabulated for US nuclear power plants. Data are presented on nuclear steam supply system orders. A schedule of commercial operation and projected capital costs through 1990 is given

  11. Phylogenetics of Ogyges Kaup and the biogeography of Nuclear Central America (Coleoptera, Passalidae)

    Science.gov (United States)

    Cano, Enio B.; Schuster, Jack C.; Morrone, Juan J.

    2018-01-01

    Abstract A phylogenetic morphological analysis of the genus Ogyges Kaup, distributed in Nuclear Central America, from Chiapas, Mexico, to northwestern Nicaragua was undertaken. Five species of Proculejus Kaup, distributed north of the Isthmus of Tehuantepec in Mexico, were selected as outgroup. Ogyges was recovered as monophyletic with three species groups: championi, laevissimus, and crassulus. Each species group shows a distinct, generally allopatric distribution. The O. championi species group, with ten species, is distributed in the Maya block, more specifically in the mountainous system north of the Motozintla-Comaltitlán fault in Chiapas, and north of the dry valleys of the Cuilco and Motagua rivers in Guatemala. The two remaining species groups are distributed in the Chortis block. The O. laevissimus species group, including seven species, ranges mostly along the Pacific Volcanic Chain from Guatemala to El Salvador, and from southeastern Honduras to the northwestern area of Nicaragua. The O. crassulus species group, with ten species, is distributed from northeastern Guatemala (Merendón) to northern Honduras. The Isthmus of Tehuantepec in Mexico, the Motagua-Cuilco and Motozintla-Comaltitlán sutures zones in Chiapas and Guatemala, the lowland valleys of Colón and Comalí rivers between Nicaragua and Honduras (or, perhaps, the northern suture of the Siuna Terrane in Nicaragua), the Guayape fault system in Honduras, and the intricate dry valleys of Ulúa-Chamelecón-Olancho in Honduras, are hypothesized to have acted as barriers that affected the geographical distribution of Ogyges, as well as probably other montane organisms. PMID:29674874

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

    Directory of Open Access Journals (Sweden)

    João Batista Araujo Figueiredo

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

  13. 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)

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  15. 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)

  16. 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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  18. 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)

  19. Study of the molecular structure of uranium hexafluoride; Contribution a l'etude de la structure moleculaire de l'hexafluorure d'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Bougon, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-06-01

    The vibrational spectrum of uranium hexafluoride has been studied in both the gaseous and solid states. The study of gaseous UF{sub 6} confirms the regular octahedral structure of the fluorine atoms around the central U atom and makes it possible to evaluate some of the vibrational frequencies. From these, some new force constants have been determined. A tetragonal distortion is observed on solid UF{sub 6}; this distortion has only observed up till now by means of X-ray diffraction and nuclear magnetic resonance techniques. (author) [French] Le spectre de vibration de l'hexafluorure d'uranium UF{sub 6} est etudie sous les formes gazeuse et solide. L'etude de l'UF{sub 6} gaz confirme la structure d'octaedre regulier d'atomes de fluor autour de l'atome central d'uranium et apporte une precision sur certaines frequences de vibration. A partir de ces valeurs, de nouvelles determinations de constantes de force ont ete realisees. L'observation de UF{sub 6} solide confirme la deformation tetragonale de l'octaedre, deformation observee jusqu'a present par les seules methodes de resonance magnetique nucleaire et diffraction des rayons X. (auteur)

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

    International Nuclear Information System (INIS)

    Ritch, J.

    2006-01-01

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

  1. 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.

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

    Science.gov (United States)

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

    2010-09-13

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

  3. Conference day - Dissuasion, proliferation, disarmament: the nuclear debate beyond 2010. Conference proceedings; Journee d'etude - Dissuasion, proliferation, desarmement: le debat nucleaire apres 2010. Actes de la conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-09-15

    A first set of contributions (round tables) addresses the relationship between NATO, nuclear deterrence and antimissile defence. The second set of contributions addresses nuclear policies of emerging powers (Russia, China, Iran...) and proliferation risks. The third one addresses the perspectives of non proliferation, civil nuclear energy actors, and disarmament

  4. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    Science.gov (United States)

    2010-03-03

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

  5. 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.)

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

    International Nuclear Information System (INIS)

    1980-09-01

    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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  8. The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay

    International Nuclear Information System (INIS)

    Debiesse, J.

    1958-01-01

    The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' was created (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author) [fr

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

    International Nuclear Information System (INIS)

    Bendarag, A.

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Wang Feng

    2010-01-01

    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)

  11. 1989 annual report of the Rossendorf Central Institute of Nuclear Research

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  12. Comparing flowmeter, aquifer test, and surface nuclear magnetic resonance data in Central Nebraska

    Science.gov (United States)

    Irons, T.; Abraham, J. D.; Cannia, J. C.; Steele, G.; Hobza, C. M.; Li, Y.; McKenna, J. R.

    2011-12-01

    Traditionally the only means of estimating the hydraulic properties of aquifers has involved drilling boreholes. The logistical and economic requirements of aquifer tests has limited the ability of hydrologists to construct the detailed groundwater models needed for resource management. As such, water policy decisions are often based on sparse aquifer tests combined with geologic interpretation and extrapolation. When dealing with complicated groundwater systems these extrapolations are often not accurate at the scale required to characterize the groundwater system, and additional information is needed to make better informed resource decisions. Surface nuclear magnetic resonance (SNMR) is a geophysical technique which allows for non-invasive estimates of hydraulic permeability and transmissivity. Protons in a volume of liquid water form a weak bulk magnetic moment as they align and precess about the earth's magnetic field. This moment is too small to be measured directly but may be observed by tipping it away from equilibrium using radio-frequency pulses oscillating at the same frequency as its precession (the Larmor frequency). After a short tipping pulse, the moment continues to precess around the static field, although at a tipped angle, slowly returning to its equilibrium state. The decay of these spinning magnetic moments can be observed inductively using loops of wire on the surface of the earth. In the simplest experiment a time series is recorded after a single tipping pulse. By varying the strength of the tipping pulse, different regions of the subsurface can be probed. The amplitude of the signal is directly proportional to the amount of water in the investigated volume. The decay rate of the signal is related to pore geometry and interconnectivity and can be used to estimate hydraulic conductivity. However, this relationship cannot be universally defined as it is affected by additional factors including the mineralogy of the host rock and homogeneity of

  13. 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)

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

    International Nuclear Information System (INIS)

    Gillen, V.

    1993-12-01

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

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

    International Nuclear Information System (INIS)

    Humphrey, J.C.

    1985-01-01

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

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

    International Nuclear Information System (INIS)

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

    1987-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Mohammad Ayaz Ahmad

    2017-12-01

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

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  19. 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'une des trois filieres suivantes: - filiere uranium

  20. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Reis Martins Junior, L.L. dos.

    1980-01-01

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

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

    International Nuclear Information System (INIS)

    1973-01-01

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

  3. Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition); Realizacion de operaciones en centrales nucleares. Guia de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

  4. Centrality Dependence of Hadron Multiplicities in Nuclear Collisions in the Dual Parton Model

    CERN Document Server

    Capella, A

    2001-01-01

    We show that, even in purely soft processes, the hadronic multiplicity in nucleus-nucleus interactions contains a term that scales with the number of binary collisions. In the absence of shadowing corrections, this term dominates at mid rapidities and high energies. Shadowing corrections are calculated as a function of impact parameter and the centrality dependence of mid-rapidity multiplicities is determined. The multiplicity per participant increases with centrality with a rate that increases between SPS and RHIC energies, in agreement with experiment.

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

    International Nuclear Information System (INIS)

    Knee, H.E.

    1991-01-01

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

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

    International Nuclear Information System (INIS)

    1979-01-01

    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

  7. 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)

  8. Instrumental performance of an etude after three methods of practice.

    Science.gov (United States)

    Vanden Ark, S

    1997-12-01

    For 80 fifth-grade students three practice conditions (mental, mental with physical simulation, and physical with singing) produced significant mean differences in instrumental performance of an etude. No significant differences were found for traditional, physical practice.

  9. Consequences of the nuclear energy moratorium as demanded by the F.D.P. central committee

    International Nuclear Information System (INIS)

    1977-08-01

    If the construction of nuclear power plants is to be tied to the first partial construction licence for the Germany reprocessing centre, as the F.D.P. especially demands lately (note: superseded since the Party Congress) then this would lead unavoidably to a 3- to 10-year nuclear energy moratorium with extremely serious consequences for the electricity supply and the employment situation in the FRG. In view of the significance of the impending energy policy decisions, the Deutsches Atomforum urges all those responsible in Bund and Laender, to take these interconnections very seriously. Only by solving the apparent conflict between further nuclear energy expansion and reprocessing, can preconditions be created for the realization of an adequate electricity supply which, at the same time, is not harmful to the environment, without serious consequences for energy and employment policies. The fact that these consequences will not be visible until in the eighties, may not be a reason for postponing decisions which have to be taken now. (orig./HP) [de

  10. NATO Nuclear Reductions and the Assurance of Central and Eastern European Allies

    Science.gov (United States)

    2013-10-01

    Founding Act on Mutual Relations, Cooperation and Security Between NATO and the Russian Federation, signed in Paris , May 27, 1997, Section IV. Political...in Central Europe,” in Bruno Tertrais, ed., Perspectives on Extended Deterrence, Researches and Documents No. 3 ( Paris : Fondation pour la Rescherche...I. • • • • • • Wrodaw 0 Lo~t Radom L bl’ o u 1n ·= ... 0 Brest 0 Pinsk

  11. Qualified Coatings in Nuclear Power Plants. Commercial products; Qualified Coatings in Nuclear Power Plants. Commercial products. Pinturas homologadas en centrales nucleares. Productos comerciales

    Energy Technology Data Exchange (ETDEWEB)

    Barcena, J.; Nunez, B.; Romero, M.; Baladiam, M.

    2014-07-01

    Recently, the supplier of paints that were qualified for use in nuclear applications as protective coatings have ceased to supply in Spain the paints that was used in areas or components with special requirements for nuclear power plants (NPPs). This lack of the common commercial products called for the search for and homologation of other products. A study was performed on the current status of the homologation of commercial products for NPPs and on the codes and standards governing them. The criteria to be met have been defined and the results of the tests performed on the selected paints have been compared against the established criteria so as to allow the homologation of the paints. (Author)

  12. Licence prolongations of US nuclear power plants; Les prolongations de licence des centrales nucleaires americaines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-04-01

    Licences of US nuclear reactors were initially attributed for a 40 years duration. However, the vast majority of the reactors can benefit of a licence prolongation for a period of 20 years maximum. This article recalls first the procedure to follow for the licence prolongation demands (safety analysis, components aging, environmental impact statement), and then it makes a status of the accepted prolongations, of the demands under examination, and of the demands that should be presented in the next 5 years. (J.S.)

  13. NRPA develops regulatory cooperation with Central Asian authorities for nuclear safety and radiation protection

    International Nuclear Information System (INIS)

    2009-01-01

    With the support of the Norwegian Ministry of Foreign Affairs, the NRPA has initiated a regional regulatory cooperation project with Kazakhstan, Kyrgyzstan and Tajikistan to improve regulations on nuclear safety, radiation protection and environmental issues, and assist the countries in re mediating radioactively contaminated sites. There is a critical lack in the regulatory basis for carrying out such remediation work, including a lack of relevant radiation and environmental safety norms and standards, licensing procedures and requirements for monitoring, as well as expertise to transform such a basis into practice. (Author)

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

    International Nuclear Information System (INIS)

    Marconi G, J.F.; Tarazaga, A.E.; Romero, L.D.

    2007-01-01

    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)

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

    International Nuclear Information System (INIS)

    Novara, Oscar; LaFuente, Jose; Large, Steve; Andes, Trent; Messick, Charles

    2000-01-01

    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. Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Ibrahim, Maslina Mohd; Yussup, Nolida; Haris, Mohd Fauzi; Soh @ Shaari, Syirrazie Che; Azman, Azraf; Razalim, Faizal Azrin B. Abdul; Yapp, Raymond; Hasim, Harzawardi; Aslan, Mohd Dzul Aiman

    2017-01-01

    One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and monitor the radiation level for each radiation detectors at real time online. The web design also included a query feature for history data from various locations online. The communication between the server's software and web server is discussed in detail in this paper.

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

    International Nuclear Information System (INIS)

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

    1986-01-01

    A cosmic-ray induced nuclear event detected in the emulsion chamber is described. The event consists of 217 shower cores with ΣEγ = 1,275 TeV. In log scale, energy and particles are emitted most densely at the small lateral distance corresponding to 0.5 mm; 77 % of the total energy and 61 % of the total multiplicity are inside the radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and non-isotropic azimuthal distribution. This event indicates a possibility that phenomena of large transverse momentum could happen to produce a strong concentration of energy and particles in the very forward direction. (Authors) [pt

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

    International Nuclear Information System (INIS)

    Murata, Takashi

    1999-01-01

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

  19. New instrument for the confirmation of declared power histories of central station nuclear power plants

    International Nuclear Information System (INIS)

    Dowdy, E.J.; Robba, A.A.; Hastings, R.D.; France, S.W.

    1979-01-01

    An operationally simple, portable, microprocessor-based, unattended reactor power monitor was developed for International Atomic Energy Agency inspector use in confirming operator records of the power history of nuclear power plants. The monitor is based on the principle that the leakage neutron flux outside the biological shield is proportional to the thermal power level. The leakage flux is detected and compared with the leakage flux from the same reactor for a confirmed calibration period. Several output options are available, and a record of more than three months of hourly measurements of the themal power of the plant can be obtained. The monitor has battery backup power for interruptions of host power of duration up to 18 hours

  20. Mitochondrial content is central to nuclear gene expression: Profound implications for human health.

    Science.gov (United States)

    Muir, Rebecca; Diot, Alan; Poulton, Joanna

    2016-02-01

    We review a recent paper in Genome Research by Guantes et al. showing that nuclear gene expression is influenced by the bioenergetic status of the mitochondria. The amount of energy that mitochondria make available for gene expression varies considerably. It depends on: the energetic demands of the tissue; the mitochondrial DNA (mtDNA) mutant load; the number of mitochondria; stressors present in the cell. Hence, when failing mitochondria place the cell in energy crisis there are major effects on gene expression affecting the risk of degenerative diseases, cancer and ageing. In 2015 the UK parliament approved a change in the regulation of IVF techniques, allowing "Mitochondrial replacement therapy" to become a reproductive choice for women at risk of transmitting mitochondrial disease to their children. This is the first time that this technique will be available. Therefore understanding the interaction between mitochondria and the nucleus has never been more important. © 2015 The Authors. BioEssays Published by WILEY Periodicals, Inc.

  1. Suicide plane crash against nuclear power plants; Avion suicide contre centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Richard, A

    2002-12-01

    Cea (French atomic energy commission) and EDF (Electricity of France) are reassessing their safety standards concerning suicide plane attacks against nuclear facilities. The general idea is to study the non-linear behaviour of reinforced concrete in case of mechanical impact. American studies carried out in 1988 show that a F-14 phantom crashing into a 3,6 meter thick wall at a speed of 774 km/h penetrates only the first 5 cm of the wall. More recent studies performed in Germany and based on computerized simulations show that the reactor containment can sustain impacts from a F15 plane or even from a 747-Boeing but contiguous buildings like the one which houses spent fuels might be more easily damaged because of their metal roofing. (A.C.)

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

    OpenAIRE

    Belinchón Vergara, Julio Angel

    2016-01-01

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

  3. Study of potential of nuclear waste transmutation and safety characteristics of an hybrid system: sub critical accelerator reactor; Etude du potentiel de transmutation et des caracteristiques de surete d`un systeme hybride: accelerateur reacteur sous critique

    Energy Technology Data Exchange (ETDEWEB)

    Tchistiakov, A

    1998-04-01

    The study of potential of nuclear waste transmutation for the new reactor systems - hybrid reactors - was the object of this work. Global review of different projects is presented. The basic physical parameters definitions, as neutron surplus and relative importance of external source neutrons, are introduced and explained. For these parameters, numerical values are obtained. The advantage in neutron surplus of fast system is noted. Equilibrium model and corresponding toxicities of different isotopes nd nuclear cycles are presented. Numerical analysis for equilibrium model converge validation are performed also. The study of neutron consumption by `transmutable` Long-Lived Fission Products (Tc, I and Cs) show the possibility of their incineration in dedicated fast hybrid reactors. Equilibrium model shown the influence of reprocessing losses level to cycle toxicity level. Relations between specific fuel inventories (mass normalised by power unit) for thermal and fast spectra are examined. The differences are relatively small. Finally, few hybrid reactor concepts with different objects were analysed. These studies confirm that in frameworks of certain Nuclear Energy scenarios the fast hybrid systems can reduce significantly the radio-toxicity of fuel cycle. Preliminary analyses of sub-critical reactor behaviour show big potential of this reactor type in `Transient of Power` kind of accident, even if more detailed study is necessary. (author)

  4. Insights from Siting New Nuclear Power Plants in the Central and Eastern United States

    International Nuclear Information System (INIS)

    Munson, Clifford G.; Kugler, Andrew J.

    2011-01-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its review for four early site permits and for four standard reactor designs. It is currently reviewing applications for fourteen combined license applications and three additional reactor designs. The staff is applying lessons it has learned from the reviews to date to the review work going forward. The licensing process being used by current applicants differs significantly from that used by the current operating fleet. The previous process required two steps. First an applicant had to obtain a construction permit to build the plant. Then, near the end of construction, the applicant had to obtain an operating license. Under the process in Part 52, an applicant can apply for a combined license (COL) that allows construction and (once certain conditions are met) operation of a new plant - a one-step process. An applicant for a COL may reference an early site permit (ESP13), a standard design certification, both, or neither. In addition to developing Part 52, the NRC also revised CFR Part 100 by adding Subpart B, which includes sections 100.21, 'Non-seismic siting criteria', and 100.23, 'Geologic and seismic siting criteria'. The NRC staff also revised the Standard Review Plan (NUREG-0800) and developed Regulatory Guide (RG) 1.206, 'Combined License Applications for Nuclear Power Plants (LWR Edition).' The NRC staff incorporated into the revision of NUREG-0800 and development of RG 1.206 some early lessons learned from its review of the first three ESPs. Staff work begins before the application is received, as the staff interacts with the applicant to identify issues that will require special treatment or specific staff resources. After the application is submitted, if the NRC finds the application acceptable, the safety and environmental reviews begin, proceeding in parallel. The safety review culminates in the issuance of a safety evaluation report (SER) after it

  5. Study and Construction of the Metal Vessels for the Reactors of the EDF1 and EDF2 Sectors at Chinon; Etude et construction des caissons metalliques des reacteurs des tranches EDF1 et EDF2 de la centrale de Chinon; Izuchenie i konstruktsiya metallicheskikh korpusov reaktorov pervoj i vtoroj chasti programm ehlektrostantsij; Estudio y construccion de los recipientes metalicos de los reactores EDF1 y EDF2 de la central de Chinon

    Energy Technology Data Exchange (ETDEWEB)

    Lamiral, G.; Millot, R.; Passerieux, P. [Electricite de France, Clamart, Seine (France)

    1963-10-15

    The first two natural uranium-graphite-C0{sub 2} reactors at the Chinon station have metal vessels of thick manganese-molybdenum steel plate. The studies carried out on these vessels raised certain problems, particularly in connection with the design and dimensions of the port reinforcements. The reinforcements for the control-rod channels and fuel ports were studied on mock-ups and the results obtained were checked on the completed reactors during hydraulic tests. The type of construction initially used for the EDF1 vessel was relatively simple. The plates to be welded were locally preheated, and the vessel was not supposed to undergo more than one stress-relief heat treatment after completion of all the welding. Serious cracks developed, however, and it became necessary to alter the whole method of construction. In particular, the welding was now done after overall preheating and the vessel was subjected to multiple stress-relief treatments. This made it possible to fabricate the vessels for EDF1 and EDF2, but at the same time imposed certain limitations which considerably complicated work on the site. (author) [French] Les reacteurs a uranium naturel, graphite et gaz carbonique des deux premieres tranches de la Centrale de Chinon comportent des caissons metalliques realises a partir de toles de fortes epaisseurs, en acier au manganese-molybdene. Les etudes de ces paissons ont pose certains problemes, notamment en ce qui concerne les renforts d'ouvertures. Les renforts des passages des barres de controle et des orifices de chargement ont ete etudies sur maquette et les resultats obtenus ont ete controles sur les ouvrages termines lors des epreuves hydrauliques. Le mode de construction initialement utilise pour le caisson de la tranche EDF1 etait relativement simple; les toles a souder etaient prechauffees localement et le caisson ne devait subir qu'un seul traitement thermique de detente, apres execution de toutes les soudures. Une fissuration importante en cours

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  7. Study of stochastic approaches of the n-bodies problem: application to the nuclear fragmentation; Etude des approches stochastiques du probleme a N corps: application a la multifragmentation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guarnera, A.

    1996-07-09

    In the last decade nuclear physics research has found, with the observation of phenomena such as multifragmentation or vaporization, the possibility to get a deeper insight into the nuclear matter phase diagram. For example, a spinodal decomposition scenario has been proposed to explain the multifragmentation: because of the initial compression, the system may enter a region, the spinodal zone, in which the nuclear matter is no longer stable, and so any fluctuation leads to the formation of fragments. This thesis deals with spinodal decomposition within the theoretical framework of stochastic mean filed approaches, in which the one-body density function may experience a stochastic evolution. We have shown that these approaches are able to describe phenomena, such as first order phase transitions, in which fluctuations and many-body correlations plan an important role. In the framework of stochastic mean-filed approaches we have shown that the fragment production by spinodal decomposition is characterized by typical time scales of the order of 100 fm/c and by typical size scales around the Neon mass. We have also shown that these features are robust and that they are not affected significantly by a possible expansion of the system or by the finite size of nuclei. We have proposed as a signature of the spinodal decomposition some typical partition of the largest fragments. The study and the comparison with experimental data, performed for the reactions Xe + Cu at 45 MeV/A and Xe + Sn at 50 MeV/A, have shown a remarkable agreement. Moreover we would like to stress that the theory does not contain any adjustable parameter. These results seem to give a strong indication of the possibility to observe a spinodal decomposition of nuclei. (author).

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

    International Nuclear Information System (INIS)

    Bellaize, N.

    2000-01-01

    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)

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

    Science.gov (United States)

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

    2012-01-01

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

  10. Studies of neo-formed phases occurring during spent nuclear fuel dissolution in geological repository: influence of silicate ions; Etude des phases neoformees lors de la dissolution du combustible nucleaire en condition de stockage geologique: influence des ions silicate

    Energy Technology Data Exchange (ETDEWEB)

    Robit-Pointeau, V

    2005-12-15

    Spent nuclear fuel alteration in deep storage conditions may proceed by local oxidising conditions at the fuel / water interface under influence of alpha irradiation. However, due to the strong redox buffer capacity of the near-field materials (especially the canister and the geological media), most of the near-field environment will remain reducing. Due to the relative high concentration in silica in such system, coffinite USiO{sub 4}.n(H{sub 2}O) may be a relevant phase to consider as it has been suggested from the natural analogues observations (Oklo). The aim of this work was to assess the relevance of coffinitisation of the spent fuel phenomena. The results of the experimental work contest the thermodynamic predictions. Instead of coffinite, a new U(IV)-Si phase has been observed in water simulating storage conditions. The thermodynamic data on coffinite validated by OECD are based on the average concentration of dissolved silica present in natural system containing uraninite and quartz. As the silica concentration in natural groundwaters is more probably controlled by minerals like chalcedony or silica gel, the coffinite present with uraninite in such systems, is probably not in equilibrium even in 2-billion years- old geological sites. Based on the results of this study, coffinitisation of the spent nuclear fuel in deep geological disposal is not anticipated to be a dominant short term process. (author)

  11. The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay; Formation des scientifiques et des techniciens au Centre d'Etudes Nucleaires de Saclay

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' waeated (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author)Fren. [French] Les besoins considerables actuels et previsibles en chercheurs et scientifiques necessites par l'avevement de l'energie nucleaire imposaient au Commissariat a I'Energie atomique un effort particulier pour augmenter la formation quantitative et qualitative des scientifiques. Les moyens les plus divers ont ete mis en oeuvre: 1- Creation de l'Institut National des Sciences et Techniques Nucleaires par decret de la Presidence du Conseil et de l'Education Nationale en date du 18.6.57. Cet Institut d'Enseignement Superieur (250 etudiants) donne des cours en: genie atomique, mecanique quantique, theorie et technique des Accelerateurs de particules, metallurgie speciale, radiobiologie

  12. Contribution to the study of the effects of {alpha}-irradiation in nuclear glasses; Contribution a l'etude des effets de l'irradiation {alpha} sur les verres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Abbas, A

    2001-07-01

    The main topic of this work is to characterise the effects of {alpha}-disintegration in nuclear waste glasses. Experimental and numerical approaches have been considered. The structure of the French nuclear waste glass (R7T7) has been simulated using four- and six-oxides simplified glasses which contain the main elements of the R7T7 glass: SiO{sub 2}, B{sub 2}O{sub 3}, Na{sub 2}O, ZrO{sub 2}, Al{sub 2}O{sub 3} and CaO. Four- and six-oxides glasses have been irradiated with 1 MeV-He{sup +} (ionisation) and 2.1 MeV-Kr{sup 3+} (ionisation and atomic collisions) ions in order to reproduce the effects of the {alpha}-particle and of the recoil nucleus emitted during {alpha}-disintegration of actinides, and also to differentiate electronic and ballistic effects. Irradiated glasses have been characterised using several techniques, which have been adapted to the peculiarities of our samples (isolated material, small irradiated depth). The results point out the salient role of sodium in the observed modifications: depth concentration profiles obtained with RBS show an accumulation of sodium at the irradiated surface. We found a apparent acceleration of sodium release in leaching experiments which confirm that point. Modifications observed in Raman spectra of irradiated glasses show an increase of the polymerisation (increase of Q{sub 3}/Q{sub 2} ratio) due to sodium migration. In simplified glasses we have found that the modifications of mechanical properties by external irradiations reproduce the modifications observed in actinide doped nuclear glass (decrease of hardness and increase of fracture toughness). At the same time, we performed Molecular Dynamics simulations of a six-oxides glass. We have shown that the surface modifies the glass structure down to a depth of 10 Angstrom: modification of depth concentration profiles, decrease of the atomic coordination number (A1, B and Si). During cascades, we found that atomic displacements are easier near the surface. This

  13. Contribution of prototypic material tests on the Plinius platform to the study of nuclear reactor severe accident; Contribution des essais en materiaux prototypiques sur la plate-forme Plinius a l'etude des accidents graves de reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Journeau, Ch

    2008-01-15

    The PLINIUS experimental platform at CEA Cadarache is dedicated to the experimental study of nuclear reactor severe accidents thanks to experiments between 2000 and 3500 K with prototypic corium. Corium is the mixture that would be formed by an hypothetical core melting and its mixing with structural materials. Prototypical corium has the same chemical composition as the corium corresponding to a given accident scenario but has a different isotopic composition (use of depleted uranium,...). Research programs and test series have been performed to study corium thermophysical properties, fission product behaviour, corium spreading, solidification and interaction with concrete as well as its coolability. It was the frame of research training of many students and was realized within national, European and international collaborations. (author)

  14. Study of the relationships between nuclear decontamination foams stability and their physicochemical properties; Etude des relations entre la stabilite des mousses de decontamination nucleaire et leurs proprietes physico-chimiques

    Energy Technology Data Exchange (ETDEWEB)

    Dame, C

    2006-03-15

    The LPAD (French Atomic Energy Commission) develops innovative processes in the frame of the future dismantling of nuclear facilities. Formulations were developed using high viscosified foams stabilized by biodegradable nonionic surfactants: alkyl poly-glucosides and viscosifiers (xanthan gum), which allow us to increase the foam lifetime and thus contact time of chemical reactants with the facility walls. We have considered the relationships between physicochemical properties and foam stability through the exploration of the foam at three different scales: from the molecular range (micelles, surface tension and visco-elasticity), to the film and Plateau border range (XR reflectivity, surface shear viscosity) and to macroscopic range, meaning the whole foam (foaminess, liquid fraction and wall film thickness evolution). Finally, exploratory study is presented concerning simultaneous foam three scales characterisation by small angle neutron scattering. (author)

  15. The influence of the PDMS technique in the study of the induced modifications of polymers used in nuclear environment; Apport de la technique PDMS a l`etude des modifications induites dans des polymeres utilises en ambiance nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Nsouli, B [Lyon-1 Univ., 69 - Villeurbanne (France). Inst. de Physique Nucleaire

    1995-07-20

    The PDMS technique (Particle Induced Desorption Mass Spectrometry) combined with a TOF detection (Time of Flight) is the main tool used in this study of polymer degradation in nuclear environment. Ar{sup 3+} ions with a 9 MeV energy have been used to induce the secondary ion emission, and the study was devoted to two stresses typical of this type of environment. The first part of the work concerned with the structural modifications induced by gamma irradiation on ion exchange resin, used for nuclear effluents reprocessing, namely the poly(4-vinylpyridine), or P-4PV. For such a material, the negative fragment emission is particularly sensitive to structural modifications. Difficult physical measurements in such an insoluble and infusible material (IR, UV - Vis, EPR, TGA, dielectric measurements) became consistent after the degradation mechanisms were elucidated. These effects, interpreted in terms of scissions and recombinations, enabled us to explicit different modes of energy deposition, and shed light on some discrepancies between SIMS and PDMS. The second part of the study is devoted to the thermal ageing of an elastomer, used in fabrication of valve gaskets submitted to high temperatures. First of all, we studied the constituents of the polymeric material, i. e. copolymer, homo polymers, and also additives. This last component proved useful to analyze, as a superficial lubricant layer can mask the conformational rearrangements which seem to occur after few hours of thermal treatment (PE blocks are prevailing at the surface). Here too, the PDMS information is important to account for static SIMS and ESCA results, as its probed layer thickness lies in-between. (author) 187 refs.

  16. The nuclear bomb carbon curve recorded in tree-rings and lake sediments near Taal Volcano, Central Philippines

    Science.gov (United States)

    Liou, M. S.; Li, H. C.; Huang, S. K.; Guan, B. T.

    2017-12-01

    Dendrochronologies built from precisely dated annual rings have shown to record the regional bomb pulse and the C-14 concentration variations caused by local events. In this study, we collected teak trees Tectona grandis near the Lake Taal, Central Philippines in 2011 for dendrochronological analysis and radiocarbon dating. The tree-ring sample contains 90 rings dated from 1922 to 2011. Currently, 28 selected subsamples have been measured by AMS 14C on bulk carbon with a few samples on holocellulose. The 14C results of the samples indicate that: 1) the results of AMS 14C dating between holocellulose and whole wood from the same ring are similar, so we select whole wood for AMS 14C dating. 2) The nuclear bomb 14C pulse was clearly recorded in the Tectona grandis growth rings. The Δ14C values rose dramatically in 1960 and reached a maximum of 692‰ in 1966. The magnitude and the peak year of the bomb curve in the Tectona grandis tree-ring record are comparable to other published tree-ring records in the tropical regions. 3) The Δ14C values suddenly dropped in 1950, 1964 and 1968, probably affected by CO2 gas releasing due to the Taal volcanic activities. Further study on the tree-ring 14C dating will allow us to evaluate the bomb pulse trends more precisely, and the volcanic activities of Pinatubo and Taal Volcanoes. The tree-ring Δ14C record not only confirms existence of the bomb curve in Taal Lake area, but also allows us compare to the Δ14C record in the lake sediment for chronological construction. A 120-cm gravity core, TLS-2, collected from Lake Taal in 2008, shows the nuclear bomb carbon curve in the TOC of the core. However, the magnitude of the nuclear bomb 14C pulse in the TOC of TLS-2 is much lower than that in the tree-ring records, due to mixing effect of different organic carbon sources, smoothing effect of 14CO2 in multiple years plant growths, local old CO2 emission from volcanic activity, degassing from the lake bottom, and industrial and city

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

    International Nuclear Information System (INIS)

    Malek, Z.; Sus, F.

    2002-01-01

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

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

    International Nuclear Information System (INIS)

    1973-01-01

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

  19. Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques

    Energy Technology Data Exchange (ETDEWEB)

    Kryger, B [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-10-01

    In order to study the effect of an external pressure on the limitation of swelling due to fission-gas precipitation, some irradiations have been carried out at burn-ups of about 35.000 MWd/ton, and at average sample temperatures of 575 Celsius degrees, of non-alloyed uranium and uranium 8 per cent molybdenum gained in a thick stainless steel can. A cylindrical central hole allows a fuel swelling from 20 to 33 per cent according to the experiment. After irradiation, the uranium samples showed two types of can rupture: one is due to the fuel swelling, and the other, to the pressure of the fission gases, released through a network of microcracks. The cans of the uranium-molybdenum samples are all undamaged and it is shown that the gas release occurs by interconnection of the bubbles for swelling values higher than those obtained in the case of uranium. For each type of fuel, a swelling-fission gas release relationship is established. The results suggest that good performances with a metallic fuel intended for use in fast reactor conditions can be obtained. (author) [French] Afin d'etudier l'effet d'une pression exterieure sur la limitation du gonflement due a la precipitation des gaz de fission, on a irradie a des taux de combustion d'environ 35.000 MWj/t et a des temperatures moyennes de 575 degres des echantillons d'uranium non allie et d'uranium-molybdene 8 pour cent contenus dans une gaine en acier inoxydable epaisse. Un trou cylindrique central permet au combustible de gonfler librement de 20 a 33 pour cent suivant les cas. Apres irradiation les echantillons d'uranium presentent deux types de ruptures de gaine: l'une due au gonflement du combustible, l'autre a la pression des gaz degages, ce degagement des gaz etant provoque par un reseau de micro-fissures. Les gaines des echantillons d'alliage uranium-molybdene sont toutes intactes et l'on montre que le relachement des gaz opere par interconnexion des bulles pour des valeurs de gonflement plus elevees que dans

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

    International Nuclear Information System (INIS)

    Carpenter, A.V.; Flanders, W.D.; Frome, E.L.; Crawford-Brown, D.J.; Fry, S.A.

    1987-03-01

    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

  1. 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.

  2. 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)

    1997-12-31

    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.

  3. Relationships between nuclear magnetic resonance parameters used to characterize weathering spilled oil and soil toxicity in central Patagonia.

    Science.gov (United States)

    Ríos, Stella Maris; Barquin, Mercedes; Katusich, Ofelia; Nudelman, Norma

    2014-01-01

    Oil spill in the Central Patagonian zone was studied to evaluate if any relationship exists between the parameters used to characterize weathering spilled oil and soil toxicity for two plant species and to evaluate if the phytotoxicity to local species would be a good index for the soil contamination. Nuclear magnetic resonance (NMR) structural indexes and column chromatography compositional indexes were determined to characterize the oil spill in the soil samples. Bioassays were also carried out using Lactuca sativa L (reference) and Atriplex lampa (native species) as test organisms. Measurements of the total petroleum hydrocarbon (TPH) and the electrical conductivity (EC) of the soil were carried out to evaluate the effect on the bioassays. The principal components analysis of the parameters determined by NMR, compositional indexes, EC, TPH, and toxicology data shows that the first three principal components accounted for the 78% of the total variance (40%, 25%, and 13% for the first, second, and third PC, respectively). A good agreement was found between information obtained by compositional indexes and NMR structural indexes. Soil toxicity increases with the increase of EC and TPH. Other factors, such as, the presence of branched and aromatic hydrocarbons is also significant. The statistical evaluation showed that the Euclidean distances (3D) between the background and each one of the samples might be a better indicator of the soil contamination, compared with chemical criterion of TPH.

  4. Study of the tributyl phosphate - 30% dodecane solvent; Etude du solvant phosphate tributylique - 30 % dodecane

    Energy Technology Data Exchange (ETDEWEB)

    Leroy, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses. Centre d' Etudes Nucleaires, 92 (France)

    1967-07-01

    This study, originating mainly from a literature survey, gives the principal chemical and physical features of the tributyl-phosphate (TBP) agent diluted at 30 volumes per cent in dodecane. The mixture is a very commonly used extractant in nuclear fuel processing. In this paper, the main following points are reported: -) the components (TBP and diluents) -) the TBP-diluents systems (non-loaded), -) the TBP-diluents-water systems, -) TBP-diluents-water-nitric acid systems, and -) industrial solvents. (author) [French] Cette etude, d'origine bibliographique, regroupe les caracteristiques physico-chimiques essentielles du phosphate tributylique (TBP) dilue a 30% en volume dans du dodecane. Ce melange constitue un agent d'extraction tres utilise dans le traitement des combustibles nucleaires. Les principaux points traites sont les suivants: -) les constituants (TBP et diluants), -) les systemes TBP-diluants non charges, -) les systemes TBP-diluants-eau, -) les systemes TBP-diluants-eau-acide nitrique, et -) les solvants industriels. (auteur)

  5. Study of the dispersion phenomena connected with the absorption by recoilless nuclear resonance fluorescence; Etude des phenomenes de dispersion lies a l'absorption resonnante sans recul des noyaux atomiques

    Energy Technology Data Exchange (ETDEWEB)

    Imbert, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-12-01

    In nuclear resonance fluorescence as in the optical field abnormal dispersion curves are related to the absorption lines. It is possible, by using quadrupolar or magnetic splitting of the line in the case of recoilless resonance fluorescence (Moessbauer effect) to obtain differential dispersion effects between the two orthogonal linear or the two inverse circular components of the incident gamma radiation. These effects induce bi-refraction phenomena or Faraday rotation on the gamma beam, which have been studied on Fe-57 enriched absorbers. (author) [French] Comme dans le domaine optique, aux raies d'absorption de fluorescence resonnante des noyaux atomiques sont associees des courbes de dispersion anormale. Les decompositions des raies d'absorption de fluorescence resonnante sans recul (raies Moessbauer) par couplage quadrupolaire ou effet Zeeman permettent d'obtenir des effets dispersifs differentiels entre composantes lineaires orthogonales ou circulaires inverses du rayonnement gamma incident. Ces effets se traduisent par des phenomenes de birefringence ou de rotation Faraday, qui ont pu etre etudies sur des milieux enrichis en fer-57. (auteur)

  6. Study of the actinide-lanthanide separation from nuclear waste by a new pyrochemical process; Etude de la separation actinides-lanthanides des dechets nucleaires par un procede pyrochimique nouveau

    Energy Technology Data Exchange (ETDEWEB)

    Lemort, F. [CEA Marcoule, Departement de Retraitement, des Dechets et du Demantelement, 30 - Bagnols-sur-Ceze (France)]|[Institut National Polytechnique, 38 - Grenoble (France)

    1997-01-01

    The theoretical extraction and separation of platinoids, actinides and lanthanides is allowed by thermodynamic using two adapted reducing agents: zinc and magnesium. Thereby, a pyrochemical method for the nuclear waste processing has been devised. The high temperature handling of the elements in fluoride forms and their processing by a reactive metallic phase required special precautions. The study of the behavior of matter in exploratory systems allowed the development of an experimental technology for the treatment and contacting of phases. The thermodynamical analysis of the experimental results shows the feasibility of the process. A model was developed to predict the distribution coefficients of zirconium, uranium and lanthanum as a function of the system composition. An estimation method was proposed in order to evaluate the distribution coefficients in diluted solution of all the actinides and lanthanides existing in the fission products between LiF CaF{sub 2} and Zn-Mg at 720 deg C. Coupled with the experimental results, the estimates results may be extrapolated to concentrated solutions allowing predictions of the separation of all actinides and lanthanides. The rapidity of element transfer is induced by a thermal effect caused by the high exothermicity of the reduction by magnesium. The kinetic coefficients have been linked with the reduction enthalpy of each element. Moreover, the kinetics seem limited by chemical reaction and not by mass transfer. (author) 66 refs.

  7. Experimental apparatus for in-pile studies of: creep of nuclear fuels, and Young's-modulus of structural materials; Dispositifs experimentaux pour etudes en pile du fluage des materiaux combustibles, et du module d'elasticite des materiaux de structure

    Energy Technology Data Exchange (ETDEWEB)

    Gautier, A; Le Bret, P; Alfille, L; Pesenti, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Creep test under compression: the apparatus described allows to study, in an horizontal beam hole of a research reactor such as EL2, the creep behaviour of nuclear fuel samples under neutron flux. The maximum stress applied on the specimens is a constant compression chooses between 0.200 and 0.400 kg/mm{sup 2} (285 psi and 570 psi). - Young's Modulus measurement: in another horizontal beam hole of such a reactor, an apparatus allows to study the irradiation effect on Young's Modulus of a structural material specimen. (author)Fren. [French] Essai de fluage en compression: l'appareillage decrit permet d'etudier, dans un canal horizontal d'une pile experimentale type EL2, le fluage en compression d'eprouvettes de materiaux fissiles sous le flux de neutrons, sous une contrainte maximum de 500 g/mm{sup 2}. - Mesure du module d'Young: dans un canal identique au precedent, un appareillage permet de suivre l'influence du rayonnement sur le module d'elasticite d'une eprouvette d'un materiau de structure. (auteur)

  8. Structure and properties of rare earth-rich glassed for nuclear waste immobilisation; Etude des caracteristiques structurales et des proprietes de verres riches en terres rares destines au confinement des produits de fission et elements a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    Bardez, I

    2004-11-15

    A new nuclear glass composition, able to immobilize highly radioactive liquid wastes from high burn-up UO{sub 2} fuel, was established and its structure studied. The composition of the selected rare earth-rich glass is (molar %): 61.79 SiO{sub 2} - 8.94 B{sub 2}O{sub 3} - 3.05 Al{sub 2}O{sub 3} - 14.41 Na{sub 2}O - 6.32 CaO - 1.89 ZrO{sub 2} - 3.60 RE{sub 2}O{sub 3} (with RE = La, Ce, Pr and Nd). The aim of this study was to determine the local environment of the rare earth in this glass and also to glean information about the effect of glass composition on the rare earth neighbouring (influence of Si, B, Al, Na and Ca contents). To this end, several series of glasses, prepared from the baseline glass, were studied by different characterisation methods such as EXAFS spectroscopy at the neodymium LIII-edge, optical absorption spectroscopy, Raman spectroscopy and {sup 29}Si, {sup 27}Al and {sup 11}B MAS-NMR. By coupling all the results obtained, several hypotheses about the nature of the rare earth neighbouring in the glass were proposed. (author)

  9. Mixed wastes treatment in Atucha I; Tratamiento de residuos mixtos de la CNA I (central nuclear Atucha I)

    Energy Technology Data Exchange (ETDEWEB)

    Varani, J L; Comandu, J F [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    1998-07-01

    Full text: During decontamination works of the fueling machine of Atucha I nuclear power plant (AINPP), a liquid waste with special characteristics was generated, which needed the development of a treatment method. The waste consisted of an emulsion designed for the cleaning of mechanical components and was formed by an organic solvent dispersed in water with aid of an emulsifier additive. After several cleaning operations, the emulsion contained an important quantity of lubricants and radioactive dirt. The treatment had the objective of recycling a toxic waste such as the organic solvent and reducing the volume of the residual mass. Laboratory tests were made tending to the emulsion separation in their components. Ionic force and ionic mobility were modified for join the emulsion micelles and produce their coalescence. Different salts and working temperatures were tried and it was stated that the combination of 1% of Na{sub 2}SO{sub 4} added and 40 degree C temperature were the optimum taking into account the available equipment in AINPP and cost considerations. The process was carried out in batch mode and 3 residual streams were obtained, an aqueous one which was sent to Residual Water System of AINPP, an organic liquid consisting of decontaminated hydrocarbons, useful for other cleaning tasks and finally a solid one, sited in the in-between interface of the other two liquids, consisting of insoluble soaps used as lubricant thickness, containing the principal proportion of radioactivity. As a result of this process we have achieved a volume reduction higher than 90%, the recycling of the organic solvent and concentration of radioactivity in a solid greasy mass with low water solubility. (author) [Spanish] Texto completo: Como resultado de tareas de descontaminacion de la maquina de carga de la central nuclear Atucha I (CNAI) se genero un residuo liquido de caracteristicas especiales, que requirio el desarrollo de un metodo de tratamiento. El residuo consistia en

  10. Contribution to the study of nuclear fuel materials with a metallic uranium base; Contribution a l'etude des materiaux combustibles nucleaires a base d'uranium metallique

    Energy Technology Data Exchange (ETDEWEB)

    Englander, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-11-15

    In a power reactor destined to supply industrially recoverable thermal energy, the most economical source of heat still consists of natural metallic uranium. However, the nuclear fuel material, most often employed in the form of rods of 20 to 40 mm diameter, is subjected to a series of stresses which lead to irreversible distortions usually incompatible with the substructure of the reactor. As a result the fuel material must possess at the outset a certain number of qualities which must be determined. Investigations have therefore been carried out, first on the technological characters peculiar to each of the three allotropic phases of pure uranium metal, and on their interactions on the stabilisation of the material which consists of either cast uranium or uranium pile-treated in the {gamma} phase. (author) [French] Dans un reacteur de puissance destine a fournir de l'energie thermique industriellement recuperable, la source de chaleur la plus economique reste constituee par de l'uranium metallique naturel. Or, le materiau combustible nucleaire, employe le plus souvent sous forme de barreaux de 20 a 40 mm de diametre, se trouve soumis a un ensemble de contraintes qui provoque des deformations irreversibles, le plus souvent incompatibles avec l'infrastructure du reacteur. Par consequent, le materiau combustible doit presenter a l'origine un certain nombre de qualites qu'il est necessaire de determiner. Aussi a-t-on d'abord etudie les caracteres technologiques propres a chacune des trois phases allotropiques de l'uranium-metal pur et leurs interactions sur la stabilisation du materiau constitue soit par de l'uranium coule, soit par de l'uranium traite en pile en phase {gamma}. (auteur)

  11. Development of a power-period calculation unit for nuclear reactor Control; Etude et realisation d'un ensemble de calcul puissance periode pour le controle d'un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Martin, J [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1966-10-01

    The apparatus studied is a digital calculating assembly which makes it possible to prepare and to present numerically the period and power of a nuclear reactor during operation, from start-up to nominal power. The pulses from a fission chamber are analyzed continuously, using real time. A small number of elements is required because of the systematic use of a calculation technique comprising the determination of a base 2 logarithm by a linear approximation. The accuracy obtained for the period is of the order of 14%; the response time of the order of the calculated period value. An approximate value of the power (30%) is given at each calculation cycle together with the power thresholds required for the control. (author) [French] L'appareil etudie est un ensemble de calcul digital permettant d'elaborer et d'afficher numeriquement la periode et la puissance, d'un reacteur nucleaire lors de son fonctionnement depuis le demarrage jusqu'a la puissance nominale. Il traite en temps reel, de facon continue, les impulsions en provenance d'une chambre de fission. Grace a l'utilisation systematique d'une technique de calcul, la determination d'un logarithme a base 2 par approximation lineaire, un nombre reduit d'elements est utilise. La precision obtenue sur la periode est de l'ordre de 14 pour cent, le temps de reponse de l'ordre de la valeur de la periode calculee. Un ordre de grandeur de la puissance (30 pour cent) est donne a chaque cycle de calcul ainsi que des seuils de puissance necessaires au controle. (auteur)

  12. Study of a cohort of Latvian workers having participated to the decontamination of the nuclear site of Chernobyl; Etude d`une cohorte de travailleurs lettons ayant participe a la decontamination du site nucleaire de Tchernobyl

    Energy Technology Data Exchange (ETDEWEB)

    Viel, J.F. [Faculte de Medecine de Besancon, 25 (France)

    1999-11-01

    In the consequences attributable to the accident at the Chernobyl nuclear power plant, it is debated whether post-disaster psycho-pathology is related to the perception of the level of contamination or the level of contamination itself. To address this issue, the authors have assessed the association of various exposure mental and psychosomatic distress, on a sample of 1,1412 Latvian liquidators drawn from the State Latvian Chernobyl clean-up workers registry. The outcome considered was a mixed mental/psychosomatic disorder occurring during the time period 1986-1995. Comparisons between subgroups of the cohort, classified according to exposure type or level, were based on the proportional hazards model. Length of work ({>=} 28 days) in a 10 km radius from the reactor (relative risk (RR) = 1.39, 95 percent confidence interval (CI) 1.14-1.70), work (> 1 time) on the damaged reactor roof (RR 1.46, 95 percent CI 1.02-2.09), forest work (RR 1.41,95 percent CI 1.19-1.68), and fresh fruits consumption ({>=} 1 time/day) (RR 1.72,95 percent CI 1.12-2.65) are risk factors for mixed mental/ psychosomatic disorder. Construction of the sarcophagus (RR 1.82, 95 percent CI 0.89-3.72), is also associated with this outcome, although non significantly. These findings confirm that some exposure variables represent risk factors for mental disorders and suggest some radiation-induced consequences although surely overweight by stress-related effects. (author)

  13. Structural and crystallisation study of a rare earth alumino borosilicate glass designed for nuclear waste confinement; Etude de la structure et du comportement en cristallisation d'un verre nucleaire d'aluminoborosilicate de terre rare

    Energy Technology Data Exchange (ETDEWEB)

    Quintas, A

    2007-09-15

    This work is devoted to the study of a rare earth alumino borosilicate glass, which molar composition is 61,81 SiO{sub 2} - 3,05 Al{sub 2}O{sub 3} - 8,94 B{sub 2}O{sub 3} - 14,41 Na{sub 2}O - 6,33 CaO - 1,90 ZrO{sub 2} - 3,56 Nd{sub 2}O{sub 3}, and envisaged for the immobilization of nuclear wastes originating from the reprocessing of high discharge burn up spent fuel. From a structural viewpoint, we investigated the role of the modifier cations on the arrangement of the glass network through different modifications of the glass composition: variation of the Na/Ca ratio and modification of the nature of the alkali and alkaline earth cations. The NMR and Raman spectroscopic techniques were useful to determine the distribution of modifier cations among the glass network and also to cast light on the competition phenomena occurring between alkali and alkaline earth cations for charge compensation of [AlO{sub 4}]{sup -} and [BO{sub 4}]{sup -} species. The neodymium local environment could be probed by optical absorption and EXAFS spectroscopies which enabled to better understand the insertion mode of Nd{sup 3+} ions among the silicate domains of the glass network. Concerning the crystallization behavior we were interested in how the glass composition may influence the crystallization processes and especially the formation of the apatite phase of composition Ca{sub 2}Nd{sub 8}(SiO{sub 4}){sub 6}O{sub 2}. In particular, this work underlined the important role of both alkaline earth and rare earth cations on the crystallization of the apatite phase. (author)

  14. Study of the multifragmentation in central collisions of the system: {sup 129}Xe + {sup nat}Sn between 32 and 50 MeV/A: measurement of collective expansion energy and of freeze-out volume; Etude de la multifragmentation dans les collisions centrales pour le systeme {sup 129}Xe + {sup nat}Sn entre 32 et 50 MeV/A: mesure de l`energie collective d`expansion et du volume de freeze-out

    Energy Technology Data Exchange (ETDEWEB)

    Salou, S

    1997-12-05

    The multifragmentation of the nuclear system formed in the central collisions of the Xe+Sn reaction between 32 and 50 MeV/A has been studied with the INDRA detector. A tensorial analyse is used to select central collisions. An important part of the charge (about 85 %) is isotropically emitted. The charge partitions have the characteristics of a simultaneous multiple fragment emission. The shape of the fragment kinetic energy distributions together with the reduced velocity correlation functions indicate that the fragmentation is a simultaneous process that occurs at low density. A comparison between the experimental data and predictions of the statistical multifragmentation model of Copenhagen (SMM) shows that charge partitions agree with the hypothesis of a thermodynamical equilibrium, whereas, kinetic observables are more constraining to the model and difficult to reproduce. However, fragments correlation functions are used in order to extract the freeze-out volume and the collective radial energy. At 50 MeV/A, the freeze-out volume is estimated to be 2.7 times the normal volume. It decreases with incident energy to be nearly twice the normal volume at 32 MeV/S. The collective energy evolves from 0 to 1.3 MeV/A with the bombarding energy. This expansion is not purely thermal and originates probably from a dynamical compression developed in the early stage of the collision. (author) 88 refs.

  15. PENULISAN ETUDE-ETUDE MUSIK TALEMPONG UNGGAN (Sebuah Usaha Pembelajaran Musik Tradisi Berbasis Literatur

    Directory of Open Access Journals (Sweden)

    Asri MK

    2014-12-01

    Full Text Available “Talempong unggan”, a traditional music from Minangkabau community particularly in Unggan, Sumpur Kudus, Sijunjung Regency, West Sumatera Indonesia is classified into genre of “talempong duduak” (rea. Due to its special musical concept and the playing technics, this traditional music is selected as a practising course in the Karawitan Department of Indonesian Institute of Art (ISI Padang Panjang since 1993 till now. In a system of class learning with many students, Talempong Unggan definitely needs supporting methods and learning technics suitable for the course where the students can reach their maximum skills. All the melody of “talempong unggan” that has been made as a material of practice is transcribed to the system of numeric notation and rhythm motive of “gendang” and “aguang” which is written into signs and special notation. All of qualitative data is formulated into finding methods, technics and etude of learning ensamble of Talempong Unggan the traditional music that learned in Karawitan Department of ISI Padang Panjang. Key words: Talempong Unggan, Methods, Technics, Etude

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

    Energy Technology Data Exchange (ETDEWEB)

    Francia, L.

    2016-07-01

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

  17. The nuclear power stations of the French atomic energy programme (1960); Les centrales nucleaires de puissance du programme francais (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Leduc, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Roux, J P [Electricite de France (EDF), 75 - Paris (France)

    1960-07-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [French] Apres avoir rappele l'integration de l'energie nucleaire parmi les moyens de production de l'energie en France, les auteurs se penchent surtout sur l'evolution des techniques appliquees dans l'equipement des centrales nucleaires francaises et decrivent les moyens mis en oeuvre pour reduire les prix de revient du kWh d'EDF2 et d'EDF3 par rapport a EDF1: la puissance electrique par tonne d'uranium varie de 493 kW/t pour EDF1 a 970 kW/t pour EDF3. C'est dans ce but que les puissances thermiques et la puissance unitaire des groupes turbo-alternateurs passent respectivement de 290 MWt pour EDF1 a 1200 ou 1600 MWt pour EDF3 et de 82 a 250 MW. Les resultats sont obtenus par une amelioration des caracteristiques neutroniques, des progres realises sur la technologie des elements combustibles, une simplification du systeme de

  18. 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)

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

    International Nuclear Information System (INIS)

    Warenmo, G.

    1979-01-01

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

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

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  1. Geochemical Study of Natural CO{sub 2} Emissions in the French Massif Central: How to Predict Origin, Processes and Evolution of CO{sub 2} Leakage; Etude geochimique des emissions naturelles de CO{sub 2} du Massif Central: origine et processus de migration du gaz

    Energy Technology Data Exchange (ETDEWEB)

    Battani, A.; Deville, E.; Faure, J.L.; Jeandel, E.; Noirez, S.; Tocque, E.; Benoit, Y.; Schmitz, J.; Parlouar, D. [Institut francais du petrole, IFP, 92 - Rueil-Malmaison (France); Sarda, P. [Paris-11 Univ., 91 - Orsay (France); Gal, F.; Le Pierres, K.; Brach, M.; Braibant, G.; Beny, C. [Bureau de Recherches Geologiques et Minieres (BRGM), 45 - Orleans (France); Pokryszka, Z.; Charmoille, A.; Bentivegna, G. [Institut National de l' Environnement Industriel et des Risques (INERIS), Parc Technologique ALATA, 60 - Verneuil-en-Halatte (France); Pironon, J.; De Donato, P.; Garnier, C.; Cailteau, C.; Barres, O.; Radilla, G.; Bauer, A. [Institut National Polytechnique de Lorraine (INPL), 54 - Vandoeuvre-les-Nancy (France)

    2010-07-15

    This study presents an overview of some results obtained within the French ANR (National Agency of Research) supported Geocarbone-Monitoring research program. The measurements were performed in Sainte-Marguerite, located in the French Massif Central. This site represents a natural laboratory for CO{sub 2}/fluid/rock interactions studies, as well as CO{sub 2} migration mechanisms towards the surface. The CO{sub 2} leaking character of the studied area also allows to test and validate measurements methods and verifications for the future CO{sub 2} geological storage sites. During these surveys, we analyzed soil CO{sub 2} fluxes and concentrations. We sampled and analyzed soil gases, and gas from carbo-gaseous bubbling springs. A one-month continuous monitoring was also tested, to record the concentration of CO{sub 2} both in atmosphere and in the soil at a single point. We also developed a new methodology to collect soil gas samples for noble gas abundances and isotopic analyses, as well as carbon isotopic ratios. Our geochemical results, combined with structural geology, show that the leaking CO{sub 2} has a very deep origin, partially mantle derived. The gas rises rapidly along normal and strike-slip active faults. CO{sub 2} soil concentrations (also showing a mantle derived component) and CO{sub 2} fluxes are spatially variable, and reach high values. The recorded atmospheric CO{sub 2} is not very high, despite the important CO{sub 2} degassing throughout the whole area. (authors)

  2. Point-of-care ultrasonography adoption in Canada: using diffusion theory and the Evaluation Tool for Ultrasound skills Development and Education (ETUDE).

    Science.gov (United States)

    Woo, Michael Y; Frank, Jason R; Lee, A Curtis

    2014-09-01

    Point-of-care ultrasonography (PoCUS) first appeared in the 1980s in North America, but the extent of the diffusion of its adoption is unknown. We characterized early PoCUS adoption by emergency physicians in Canada and its barriers to use using Rogers' diffusion of innovations theory. We developed a questionnaire based on a pilot study and literature review to assess past, current, and potential use of PoCUS and potential barriers to adoption. A Dillman technique for electronic surveys was used for dissemination. Using Rogers' diffusion of innovations theory, we developed and validated the Evaluation Tool for Ultrasound skills Development and Education (ETUDE). ETUDE scores allowed categorization of respondents into innovators, early adopters, majority, and nonadopters. Descriptive statistics, correlations, and χ² statistics were used to analyze the data. The 296 respondents (36.4% of 814 surveyed) had a median age of 40 and were 72.5% male. Adoption scores using ETUDE revealed nonadopters (18.8%), majority (28.7%), early adopters (34.5%), and innovators (18.0%). Respondents endorsed "always" using PoCUS currently and in the future for focused assessment with sonography in trauma (FAST) (current 41.8%/future 88.4%), first trimester pregnancy (current 23.3%/future 73.7%), suspected abdominal aortic aneurysm (current 32.7%/future 92.6%), basic cardiac indications (current 30.7%/future 87.5%), and central venous catheterization (current 17.0%/future 80.3%). Several barriers to PoCUS were identified for part-time emergency physicians and those working in inner-city/urban/suburban settings. This is the first study to determine the state of adoption and barriers to the introduction of PoCUS in Canadian emergency medicine practice. The novel validated ETUDE instrument should be used to evaluate the uptake of PoCUS over time.

  3. 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)

  4. 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.

  5. Modernization of the system integrated ERIS computer (SIEC) of the nuclear power plant Cofrentes; Modernizacion del sistema integrado ERIS computador (SIEC) de la Central Nuclear de cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, R.; Ramos, M.; Mendez, J.; Zuriaga, J. V.

    2011-07-01

    The complete replacement of the SIEC of Nuclear Power Cofrentes is framed within the process of modernization of systems instrumentation and control in which the Spanish nuclear power plants are immersed, process caused by an increase in security, as well as the obsolescence and lack of spare parts.

  6. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    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)

  7. Relationships between central and prefectural government for the nuclear energy development in the era of decentralization. Lesson from Germany

    International Nuclear Information System (INIS)

    Murata, Takashi

    1999-01-01

    In spite of the fact that nuclear power covers one third of the Japanese electric demand, siting of the nuclear installations faces very difficult problems to cope with. Among the reasons there is a lack of the consensus of the people at large on the legal and administrative procedures for the construction of the facilities in the context of decentralization of political system. Referring the federal legal system under the German Basic Law and its relationship with nuclear energy development, this paper analyzes and proposes several legal and administrative improvements in Japanese political integration system for the nuclear development in the era of Decentralization. (author)

  8. The Problems of Controlling Defects in the Materials Used for the First Czechoslovak Nuclear-Power Station; Problemes de Controle des Defauts dans les Materiaux Utilises a la Premiere Centrale Nucleaire de Tchecoslovaquie; Problemy defektoskopicheskogo kontrolya stroitel'nykh materialov reaktora pervoj chekhoslovatskoj atomnoj ehlektrostantsii; Problemas de Control de Defectos en los Materiales Utilizados en la Primera Central Nuclear de Checoslovaquia

    Energy Technology Data Exchange (ETDEWEB)

    Radislav, Filipp [Zavody Im.V.I. Lenina, Pl' zen, Czechoslovakia (Czech Republic)

    1965-09-15

    Pilsen, on a elabore a cet effet un instrument special grace auquel on peut faire des controles a haute temperature avec une grande precision. Le controle non destructif des pieces soudees peut se faire egalement par radioscopie. La verification de petites epaisseurs et celle, a haute temperature, de la base d'une soudure longitudinale sont realisees a l'aide des rayons X provenant d'un appareil a emanation circulaire, et de cassettes speciales. Pour la radioscopie des pieces soudees de grande epaisseur, on a recours a un betratron de fabrication tchecoslovaque. L'auteur decrit les methodes d'essai, indique les resultats obtenus et fait une etude comparative entre le betatron tchecoslovaque de 15 MeV et celui de Siemens. (author) [Spanish] En la memoria se describe brevemente el cuerpo del reactor de la primera central nuclear de Checoslovaquia. Las rigurosas normas seguidas en su construccion (acero inoxidable de baja aleacion, de 650 mm de espesor) exigieron elaborar un metodo de 'testigos'para proceder al control no destructivo del material basico y de las soldaduras. Para el control de calidad del material basico y de las soldaduras se recurrio en gran medida al metodo de impulsos ultrasonicos, utilizando una sonda. En la memoria se describe la tecnica empleada y se evaluan los datos obtenidos; tambien se expone el metodo de control de calidad de las piezas soldadas electricamente con formacion de escorias y de las soldadas en atmosfera de anhidrido carbonico, asf como las soldadas a mano mediante arco electrico. La integridad de las placas forjadas o laminadas se controla automaticamente en una instalacion de defectoscopia de fabricacion checoslovaca, qoe consta de dos partes: un mecanismo movil y un defectoscopio de ultrasonidos U1D-A2. La instalacion se distingue por poseer varios elementos nuevos. La influencia ejercida por la distancia sobre la amplitud de la sen al originada por el defecto se compensa de manera que la altura de la senal permanece constante

  9. Management of distortion channels in the Cofrentes NPP; Gestion de la deformacion de canales en la central nuclear de Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Albendea, J. C.; Garcia, P. J.; Iglesias, J.; Mascarell, R.

    2015-07-01

    Fuel channels distortion in BWR (Boiling Water Reactor) reactors may have implication for safety. This phenomenon is complex and, at the present time it is not known in detail. This article provides the Iberdrola Generacion Nuclear SAU ongoing activities to know, predict and mitigate the consequences that this phenomenon may cause in Cofrentes Nuclear Power Plant. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

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

  11. Modernization of the pre-treatment plants in Almaraz and Trillo Nuclear Power Plants; Actualizacion de las plantas de pretratamiento en las centrales nucleares de Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Pascual Carballo, N.

    2010-07-01

    Description of the modernization project carried out in Almaraz and Trillo Nuclear Power Plants where EEAA. participates supporting and monitoring the RFQ, the design and the supplies as well as the documentary update and the design of new plants interconnection.

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

    International Nuclear Information System (INIS)

    Chiripus, Vlad-Ionut

    2004-01-01

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

  13. Implementing Formative Assessment in Engineering Education: The Use of the Online Assessment System Etude

    Science.gov (United States)

    Dopper, Sofia M.; Sjoer, Ellen

    2004-01-01

    This article describes the possibilities offered by the online assessment system Etude to achieve the benefits of formative assessment. In order to find out the way this works in practice, we carried out an experiment with the use of Etude for formative assessment in the course on collaborative report writing. Results show that online formative…

  14. Exploitation of the nuclear plant Asco and the benthic community of the river Ebro; Explotacion de la central nuclear Asco y la comunidad bentonica del rio Ebro

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin

    2015-07-01

    The Ebro river passing through the town of Asco in the province of Tarragona, provides the necessary water for the operation of the nuclear plant. water of circulation flows and service components are returned completely to the river, or if operation of cooling towers, decreased in a small part. Evaporative losses account for approximately 1% of the total flow used for two nuclear groups. (Author)

  15. 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)

    Lorenz, A.

    1982-12-01

    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)

  16. Power Nuclear Reactors: technology and innovation for development in future; Centrales Nucleares de Potencia: tecnologias actuales e innovaciones para el futuro

    Energy Technology Data Exchange (ETDEWEB)

    Suarez Antola, R [Universidad Catolica del Uruguay, Montevideo(Uruguay); Ministerio de Industria Energia y Minerria, Montevideo(Uruguay)

    2009-07-01

    The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view.

  17. Estimation of the costs of electricity generation in nuclear and other types of power stations; Estimacion de costes de generacion de electricidad en centrales nucleares y otros tipos de centrales

    Energy Technology Data Exchange (ETDEWEB)

    Col Buti, P.; Tapia Fernandez, C.

    2002-07-01

    (Study of the Nuclear Power Sector in the Context of the Energy Study in Catalonia to the 2020 Horizon) prepared by the same authors, which analyses the characteristics of the nuclear sector in Catalonia. This an other studies has provided the basis for the preparation of the Pla de l'Energia a Catalunya a l'Horitzo de l'Any 2010 (Catalonia Energy Plan to the 2010 Horizon). (Author)

  18. 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)

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  20. 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)

  1. The modernization of the process computer of the Trillo Nuclear Power Plant; Modernizacion del ordenador de proceso de la Central Nuclear de Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Aparicio, J.; Atanasio, J.

    2011-07-01

    The paper describes the modernization of the Process computer of the Trillo Nuclear Power Plant. The process computer functions, have been incorporated in the non Safety I and C platform selected in Trillo NPP: the Siemens SPPA-T2000 OM690 (formerly known as Teleperm XP). The upgrade of the Human Machine Interface of the control room has been included in the project. The modernization project has followed the same development process used in the upgrade of the process computer of PWR German nuclear power plants. (Author)

  2. 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)

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

    International Nuclear Information System (INIS)

    National Frederic Joliot-Curie Research Institute for Radiobiology and Radiohygiene

    2007-01-01

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

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

    International Nuclear Information System (INIS)

    Pham Duy Hien; Ngo Quang Huy; Vu Hai Long; Tran Khanh Mai

    1994-01-01

    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

  5. Contribution to the study of french pitchblendes; Contribution a l'etude des pechblendes francaises

    Energy Technology Data Exchange (ETDEWEB)

    Geffroy, J [Commissariat a l' Energie Atomique, Lab. de Mineralogie, Centre de Chatillon (France). Centre d' Etudes Nucleaires; Sarcia, J A [Commissariat a l' Energie Atomique, Div. de la Crouzille, Haute Vienne (France). Centre d' Etudes Nucleaires

    1955-07-01

    The authors first review the characteristics of uraninite-pitchblende, as deduced of present literature. They set apart from typical pitchblende a black oxide aspect, which probably corresponds to neo-formations, and a 'para-pitchblende' aspect, which they relate to deep sur-oxidation of normal pitchblende. They insist on the easy replacement of pitchblende by silica. and give indications as to changes in vein stones (fluorite, quartz, etc...). A detailed study of paragenesis and successions in french uranium districts follows (including discussion of uranium of uranium-bearing coals). The authors attempt to classify french pitchblende veins. They are chiefly epithermal and poor in satellite ores. Three types of deposits are identified: massive - pitchblende type, silica type, fluorite type. These deposits, as those of Portugal, are included in granite, Central-European peri-batholitic types where uranium associates which Ni, Co, Bi and Ag, are in France both rare and poor. Finally, the authors attempt to bring out in the european Hercynian area a particular distribution of paragenetic types. (authors) [French] Les auteurs recapitulent d'abord les caracteres et les occurences de l'uraninite - pechblende, tels qu'ils peuvent etre degages de l'actuelle bibliographie. Ils exposent ensuite les faits qui du point de vue mineralogique seulement ressortent de l'etude mineralogique et chalcographique des pechblendes francaises et de leurs satellites. Ils distinguent de la pechblende-type un facies oxyde noir; correspondant probablement a une neoformation, et un facies parapechblende, qui est rapporte a une sur oxydation hypogene de la pechblende proprement dite. Ils insistent sur le facile remaniement de la pechblende par la slice; et donnent quelques precisions sur les modifications des gangues (fluorine, quartz, etc...). Suit l'etude detaillee des parageneses et des successions dans les districts uraniferes francais: Divisions du Limousin, de Grury, de Lachaux et de

  6. 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)

  7. Cenozoic biogeography and evolution in direct-developing frogs of Central America (Leptodactylidae: Eleutherodactylus) as inferred from a phylogenetic analysis of nuclear and mitochondrial genes.

    Science.gov (United States)

    Crawford, Andrew J; Smith, Eric N

    2005-06-01

    We report the first phylogenetic analysis of DNA sequence data for the Central American component of the genus Eleutherodactylus (Anura: Leptodactylidae: Eleutherodactylinae), one of the most ubiquitous, diverse, and abundant components of the Neotropical amphibian fauna. We obtained DNA sequence data from 55 specimens representing 45 species. Sampling was focused on Central America, but also included Bolivia, Brazil, Jamaica, and the USA. We sequenced 1460 contiguous base pairs (bp) of the mitochondrial genome containing ND2 and five neighboring tRNA genes, plus 1300 bp of the c-myc nuclear gene. The resulting phylogenetic inferences were broadly concordant between data sets and among analytical methods. The subgenus Craugastor is monophyletic and its initial radiation was potentially rapid and adaptive. Within Craugastor, the earliest splits separate three northern Central American species groups, milesi, augusti, and alfredi, from a clade comprising the rest of Craugastor. Within the latter clade, the rhodopis group as formerly recognized comprises three deeply divergent clades that do not form a monophyletic group; we therefore restrict the content of the rhodopis group to one of two northern clades, and use new names for the other northern (mexicanus group) and one southern clade (bransfordii group). The new rhodopis and bransfordii groups together form the sister taxon to a clade comprising the biporcatus, fitzingeri, mexicanus, and rugulosus groups. We used a Bayesian MCMC approach together with geological and biogeographic assumptions to estimate divergence times from the combined DNA sequence data. Our results corroborated three independent dispersal events for the origins of Central American Eleutherodactylus: (1) an ancestor of Craugastor entered northern Central America from South American in the early Paleocene, (2) an ancestor of the subgenus Syrrhophus entered northern Central America from the Caribbean at the end of the Eocene, and (3) a wave of

  8. 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)

    1993-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-12-31

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

  11. 98 Etude Comparative du Systeme Phonematique et Tonal des ...

    African Journals Online (AJOL)

    98. Etude Comparative du Systeme Phonematique et Tonal des. Deux Parlers: Le Yoruba du Nigeria et L'itsa Parle en. Republique du Benin. Ajani Akinwumi Lateef et Ayuba G. Ajibabi http://dx.doi./org/10.4314/ujah.v18i3.5. Résume. En ce début de l'époque ou la mondialisation et la coexistence des peuples dans le ...

  12. Benchmarking on the management of radioactive waste in the Spanish Nuclear Power; Benchmarking sobre la gestion de residuos radiactivos en las Centrales Nucleares Espanola

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, M. A.; Gonzalez, R.; Gomez, N.

    2012-07-01

    The main objective of this project is to perform a comparative evaluation of the practices carried out in the field of waste management in the Spanish nuclear power plants. Once compared such practices have been established recommendations that may be of interest for application in other plants.

  13. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-07-01

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

  15. 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)

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

    International Nuclear Information System (INIS)

    Gautheron, S.; Laborier, J.C.; Robert-Gnansia, E.; Chevrier, C.

    2005-01-01

    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)

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  18. Accidental behaviour of nuclear fuel in a warehousing site under air: investigation of the nuclear ceramic oxidation and of fission gas release; Comportement accidentel du combustible nucleaire dans un site d'entreposage sous air: Etude de l'oxydation de la ceramique nucleaire et du relachement des gaz de fission

    Energy Technology Data Exchange (ETDEWEB)

    Desgranges, L.

    2006-12-15

    After a brief presentation of the context of his works, i.e. the nuclear fuel, its behaviour in a nuclear reactor, and studies performed in high activity laboratory, the author more precisely presents its research topic: the behaviour of defective nuclear fuel in air. Then, he describes the researches performed in three main directions: firstly, the characterization and understanding of fission gas localisation (experimental localisation, understanding of the bubble forming mechanisms), secondly, the determination of mechanisms related to oxidation (atomic mechanisms related to UO{sub 2} oxidation, oxidation of fragments of irradiated fuel, the CROCODILE installation). He finally presents his scientific project which notably deals with fission gas release (from UO{sub 2} to U{sub 3}O{sub 7}, and from U{sub 3}O{sub 7} to U{sub 3}O{sub 8}), and with further high activity laboratory experiments

  19. Study on the efficiency of a central neutron source for the 300-MW(e)-THTR-Nuclear Power Station Schmehausen

    International Nuclear Information System (INIS)

    Gutsch, U.; Scherer, W.; Gerwin, H.

    1976-03-01

    The loading and starting phase of the THTR-300 is controlled by an external neutron source. The possible positions of this source result from the requirement to fulfil certain criteria concerning the intensity and the interpretation of the detector-signal. In this study it is investigated how far a source centrally inserted into the reactor can be equal to this task and whether it is possible to go over to a non-central position at a later point of time. It is shown that the central source can fulfil all discussed demands. A source position lying in the vicinity of the side reflector demands a special choice of the detector position, which can be exactly determined only by further three-dimensional calculations. Beyond that, this study shows that during the loading phase in the subcritical range the spatial neutron flux distribution is expected to be completely different from that of the critical reactor. (orig.) [de

  20. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  2. The CNA-1 (Nuclear Power Plant Atucha-1) QK-01 repairing project; Proyecto de reparacion del QK-01 de CNA-1 (Central Nuclear Atucha-1)

    Energy Technology Data Exchange (ETDEWEB)

    Pizzaferri, J C [Nucleoelectrica Argentina S.A. (NASA), Buenos Aires (Argentina); Cabot, P [Comision Nacional de Energia Atomica, San Martin (Argentina). Centro Atomico Constituyentes

    1998-12-31

    The repair/maintenance of the CNA-1 QK-01 Moderator Cooler will be a leading case of the repair of a class 1 nuclear component in a high radiation environment; utilizing for the work, sophisticated remotely operated equipment. This paper describes the component, the repair-maintenance objective, and the equipment-procedures developed for the intervention. (author) 9 refs., 5 figs. [Espanol] La reparacion/mantenimiento del enfriador del moderador QK-01 de CNA-1 sera un caso sobresaliente de reparacion de un componente nuclear clase 1 en un ambiente de alta radiacion, utilizando equipamiento sofisticado de accion remota. En este trabajo se describen caracteristicas de diseno del componente, objetivos del mantenimiento, y las facilidades y procedimientos desarrollados en el marco del proyecto para realizar la tarea en cuestion. (autor)

  3. The modernization of the nuclear power plants of Asco and Vandellos II; Modernizacion de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Anton, L.

    2011-07-01

    Since the beginning of their commercial operation, the nuclear power plants of Asco and Vandellos have made design modifications aimed at improving the safety, reliability and operation of the plants. From the moment the management of the three plants was brought together within the Association Nuclear Asco-Vandellos II, and within the assets management process, joint strategic modernisation and improvement plans have been developed on the basis of the status of equipment, the evaluation of their ageing, obsolesce, degradations, manufacturers recommendations and/or the application of new regulations. The article lists the mos important actions already carried out or in the project phase for the 3 plants in the primary and secondary system, electrical and instrumentation systems and auxiliary systems, highlighting the problems and the solutions adopted in the most relevant modifications. (Author)

  4. 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)

  5. Application of the weld in maintenance mechanics at the Nuclear Power Station Atucha I; Aplicaciones de soldadura en mantenimiento de la Central Nuclear Atucha I

    Energy Technology Data Exchange (ETDEWEB)

    Cosentino, R E

    1988-12-31

    The application of the `weld procedures`, in the field of activity of nuclear power is an special chapter of weld. The so called `Nuclear Installations` are actually under control from their contruction up to their life extension operation to special control programs and quality assurance. This situation obliges the implementation of procedures to assure the fulfilment of the programs for the need to make the reparations or mechanics construction. This paper describes the considerations that has been taken into account to repare some components of the plant. The works carried out constitute applications to the TIG weld procedure. The `lip weld` is a mechanic component required in pressurized systems subject to air pressure. (Author).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  7. Risks and challenges associated with the design and construction of a nuclear power plant; Control de riesgos y retos asociados al diseno y construccion de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Liebana Martinez, B.; Armas Garcia, A.; Martinez Gozalo, I.

    2011-07-01

    The construction of a nuclear power plant project, considering the period prior to the operation of the plant, requires a very strict risk control to ensure compliance with a series of challenges. The present paper identifying the most important challenges facing the construct ability and license requirements of the process, identifying the interfaces and proposing a methodology of construction to meet the challenge of a construction process in 5 years.

  8. Proposal for implementation of alternative source term in the nuclear power plant of Laguna Verde; Propuesta de implementacion del termino fuente alternativo en la central nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Bazan L, A.; Lopez L, M.; Vargas A, A.; Cardenas J, J. B. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 7.5 Carretera Veracruz-Medellin, Dos Bocas, Veracruz (Mexico)], e-mail: ariadna.bazan@cfe.gob.mx

    2009-10-15

    In 2010 the nuclear power plant of Laguna Verde will implement the extended power upbeat in both units of the plant. Agree with methodology of NEDC-33004P-A, (constant pressure power up rate), and the source term of core, for accidents evaluations, were increased in proportion to the ratio of power level. This means that for the case of a design basis accident of loss of coolant an increase of power of 15% originated an increase of 15% in dose to main control room. Using the method of NEDC-33004P-A to extended power upbeat conditions was determined that the dose value to main control room is very near to regulatory limit established by SRP 6.4. By the above and in order to recover the margin, the nuclear power plant of Laguna Verde will calculate an alternative source term following the criteria established in RG 1.183 (alternative radiological source term for evaluating DBA at nuclear power reactor). This approach also have a more realistic dose value using the criterion of 10-CFR-50.67, in addition is predicted to get the benefit of additional operational flexibilities. This paper present the proposal of implementing the alternative source term in Laguna Verde. (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)

    1982-09-01

    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. Possible uses and applications of drones in a nuclear power plant; Posibles usos y aplicaciones de los drones en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Celis del A, L.; Palacios, J.; Rivero, T.; Valero, D., E-mail: lina.celis@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The versatility of drones is one of the strengths that have led to the rapid development of this technology, as they adapt relatively easily to new applications, presenting considerable advantages such as greater energy efficiency, longer life and a significant lower operation cost than manned systems. The current applications of the drones, in addition to the military, are very wide and varied. The nuclear industry represents an important area of opportunity for drones, mainly in response to radiological emergencies, since in this case there is a latent risk of the general population being exposed to high radiation doses. Drones can be used in environments with high chemical and radiological toxicity without endangering human lives. Some of the possible applications of the drones in a nuclear power plant are: perimeter surveillance in physical security, where equipped with a high definition camera can be used as support to physical security systems in general; visual inspection at sites, structures, equipment and pipelines, etc., as part of preventive maintenance in order to avoid the loss of material due to corrosion, oxidation, cracking, subsidence; the visual inspection through thermo-graphic images to be able to detect hot spots in some critical element; measurement and radiological mapping on surfaces to maintain monitoring of radiological safety at nuclear power plant facilities; the monitoring of environmental parameters and the Environmental Impact Assessment to obtain important information to determine the environmental impact of a given area; and accident support by providing information that allows staff to size the magnitude of the damage. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  12. 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.

  13. 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.)

  14. 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.)

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

    International Nuclear Information System (INIS)

    Portius, U.

    2007-01-01

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

  16. Economic impact associated with the decommissioning process of Vandellos I Nuclear Power Plant; Informe final. Impacto economico del desmantelamiento de la central nuclear Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Silva, M.

    2005-07-01

    This economic study examines the economic impact associated with the decommissioning process of the Vandellos I Nuclear Power Plant, measured in terms of the global income that generated the ending of the Nuclear Power Plant activity, on the territory. To this end, we will take into account the total investment that has been necessary to complete the process of decommissioning. The economic impact is calculated using the Input- Output methodology. Briefly, the Input-Output model defines a group of accounting relationships that reflect the links taking place within the production system. The Input-Output model is based on the assumption that given an increase (decrease) in the final demand of one sector, this sector should produce more (less) to satisfy this new demand. At the same time, this will lead to demand more (less) intermediate consumption goods from the remainder sectors of the economy. Then, these sectors should produce more (less) and use more (less) intermediate inputs, and so on. Therefore, an increase (decrease) in the final demand of one sector multiplies the effect throughout the economy, following the interdependency relationships that exist among the productive activities. We will start by collecting an exhaustive economic information. This information covers the whole decommissioning process and the whole economic and productive activity of the province of Tarragona. Next, this information is used with the objective of building an Input-Output table of the province that will serve as a base to establish the global economic impact of Vandellos I. The incomes and employment generation has been evaluated in the province of Tarragona that, following the main assumptions, correspond to the global effects of the decommissioning. In addition, we have evaluated the income and employment generation within the region where the nuclear power plant is located. The total income impacts show a high multiplier effect due to the investment carried out during the

  17. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition); Analisis determinista de seguridad para centrales nucleares. Guia de Seguridad Especifica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  18. 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)

  19. The added value of the replica simulators in the exploitation of nuclear power plants; El valor anadido de los simuladores replica en la explotacion de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Giron, P. a.; Ortega, F.; Rivero, N.

    2011-07-01

    Nuclear power plants full scope replica simulators were in the past solely designed following operational personnel training criteria. Nevertheless, these simulators not only feature a high replica control room but also provide an accurate process response. Control room replica simulators are presently based on complex technological platforms permitting highest physical and functional fidelity, allowing to be used as versatile and value added tools in diverse plants operation and maintenance activities. In recent years. Tecnatom has extended the use of such simulators to different engineering applications. this article intends to identify the simulators use in training and other applications beyond training. (Author)

  20. 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)

  1. The role of nuclear power plants in the wholesale electricity market; El papel de las centrales nucleares en el mercado mayorista de electricidad

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, J c; Alonso, J; Gonzalez, A; Gonzalez, R

    2009-07-01

    The Spanish electricity market has been running foe eleven years and its rules and procedures have proven compatible with a safe and stable operation of the nuclear power plants, helped by a wide portfolio of technologies in the Spanish system. In the near future, two issues emerge as a potential threat: the increase in renewable (mainly wind) production and its volatility and the development of new network infrastructure around the plants owned by third parties. Stricter rules on network development and operation and greater respect to the plants operational needs have to be pushed forward by the industry to succeed in life extension programs. (Author)

  2. Following to the occupational dose in a nuclear power plant. Second part; Seguimiento de la dosis ocupacional en una central nuclear. Segunda parte

    Energy Technology Data Exchange (ETDEWEB)

    Medrano L, M A [Gerencia de Seguridad Radiologica, Instituto Nacional de Investigaciones Nucleares, Salazar (Mexico)

    1991-07-01

    The pursuit of the occupational doses in any installation where radioactive material is managed it allows to those responsible for the radiological safety, to know those practices or places in which should focus its efforts so that the doses received by their workers are controlled and minimized. In this work another form of pursuit of the occupational doses is presented making emphasis in the practices, places and devices or teams that produce the doses to the exposed personnel to diverse radiation sources inside a typical nuclear power station.

  3. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  4. Implementation of the monitoring Plan of the State and behavior of the systems in the Central Nuclear Almaraz

    International Nuclear Information System (INIS)

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

    2013-01-01

    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. 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)

    2013-01-01

    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).

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

    International Nuclear Information System (INIS)

    Korun, M.

    2013-01-01

    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

  7. 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)

  8. Need for a probabilistic fire analysis at nuclear power plants; Necesidad de un analisis probabilista de incendios en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Calabuig Beneyto, J L [Empresarios Agrupados, A.I.E., Madrid (Spain); Ibanez Aparicio, J [Asociacion Nuclear ASCO, Barcelona (Spain)

    1993-12-15

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

  9. More child leukemia near nuclear power plants; Plus de leucemies chez l'enfant pres des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2012-03-15

    A French study shows that there are more cases of child leukemia near nuclear power plants but the statistics is low: only 14 cases detected. The same study shows that the excess is not due to the releases of gaseous effluents from the plant, there is no relationship between the excess and a particular type of plant or even a particular plant. Some experts suggest that it might be the movement and intermingling of populations in the plant area that ease the propagation of infectious agents involved in child acute leukemia. A similar result was obtained in Germany a few years ago. (A.C.)

  10. Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central; Mejoras relacionadas con la seguridad requeridas por la Autoridad Regulatoria Argentina a la Central Nuclear Atucha I

    Energy Technology Data Exchange (ETDEWEB)

    Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, 1429- Ciudad de Buenos Aires (Argentina)]. e-mail: jcalvo@sede.arn.gov.ar

    2006-07-01

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Hacker, P; Kogan, A; Garzon, D

    1991-12-31

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

  12. Application of Nuclear Analytical Techniques in Elemental Characterization of Wadi El-Nakhil Alabaster, Central Eastern Desert, Egypt

    OpenAIRE

    Zain M. Alamoudi; A. El-Taher

    2016-01-01

    Instrumental neutron activation analysis (INAA) is a powerful technique for trace element determination in rocks. Nine alabaster samples were collected from Wadi El-Nakhil located at the intersection of lat. 26°10′50′′N and long. 34°03′40′′E, central Eastern Desert, Egypt, for investigation by INAA and Energy Depressive X-Ray Fluorescence (EDXRF). The samples were irradiated by thermal neutrons at the TRIGA Mainz research reactor at a neutron flux of 7 × 1011 n/cm2·s. Twenty-two elements were...

  13. Aseismatic design and safety of nuclear power generation facilities. Research in Central Research Institute of Electric Power Industry

    International Nuclear Information System (INIS)

    1995-01-01

    In order to contribute to the aseismatic design of nuclear power generation facilities, this Research Institute has carried out the observation on the site of buildings in Matsushiro earthquake, the experiment on a large vibration table, the vibration experiment on actual buildings and so on, thus made clear the method of evaluating the dynamic model of buildings and foundation grounds. Also it cooperated in the determination of input earthquake motion which is important for aseismatic design by carrying out the evaluation of the activity of faults the observation of strong earthquakes, and the elucidation and evaluation of the characteristics of earthquake motion. It has made the standard for evaluating the fault activity and the stability in earthquakes of the foundation and surrounding grounds of power stations. The development of new underground location technology, the location on Quaternary grounds and the location on the sea, and the research on developing the aseismatic construction of FBRs are in progress. The survey and evaluation of fault activities, the evaluation of earthquake input, the limit state design of important outdoor structures, the new location technology for nuclear power stations, and the development of the buckling and base isolation design of FBRs are reported. (K.I.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Murata, Takashi [Graduate School of Energy Sci., Kyoto Univ., Kyoto (Japan)

    1999-12-01

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

  15. Comparative Studies of Chemical Effects following Nuclear Reactions and Transformations on Metal Organic Phenyl Compounds; Etudes Comparatives des Effets Chimiques Induits par les Reactions et les Transformations Nucleaires sur des Composes Phenylmetalliques; 0421 0420 0410 0414 ; Estudios Comparativos de los Efectos Quimicos de las Reacciones y Transformaciones Nucleares en Compuestos Fenil-Organometalicos

    Energy Technology Data Exchange (ETDEWEB)

    Merz, E.; Riedel, H. J. [Kernforschungsanlage, Juelich, Federal Republic of Germany (Germany)

    1965-04-15

    A study of the chemical effects created by the energetic recoil atoms of nuclear reactions in solids and liquids was made on the basis of a broad comparison of the products formed by (n, {gamma}) and (n, 2n) processes in the metalphenyl compounds of germanium, tin, lead, arsenic and antimony. In addition, the radioactive recoil products formed after the K-capture process on Ge{sup 68} - tetraphenyl are compared with the results from the (n, {gamma}) -process on Ga-triphenyl and the (n,p) process on Ge-tetra phenyl. Finally, the studies include the {beta}{sup -} transition on Ge{sup 77}-tetraphenyl to As{sup 77}. Applying different separation methods, e.g. adsorption chromatography on alumina, ion exchange and electrophoresis, the various radioactive recoil products were separated and the individual yields determined. It was found that in nuclear reactions the compounds of the mentioned metals having identical ligands formed practically the same classes of recoil products. The yield distribution however reveals characteristic alterations between the (n, {gamma}) and (n, 2n) reaction. Only a small influence on the yields is perceptible when irradiations are performed in liquids and solutions. The large differences found for the new compounds formed by nuclear transformations are striking, not only in the kind of typical products but also in their percentage yields. Thus, several recoil products of Ge and Ga with metalorganic character were found by nuclear reactions on Ge-tetraphenyl that could not be detected at all by the K-capture process on Ge{sup 68}-tetraphenyl. The {beta}{sup -} decay on Ge{sup 77}-tetraphenyl produces practically the same chemical compounds as were observed by nuclear reactions. However, a remarkable increase in the portion of the labelled parent molecules (retention) is typical for the {beta}{sup -} transition. The results are discussed on the basis of theoretical considerations of the amount of kinetic energy transferred to the reacting

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

    International Nuclear Information System (INIS)

    2007-01-01

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

  17. 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.)

  18. CNE (central nuclear en Embalse): probabilistic safety study. Loss-of-coolant accidents. Analysis through events sequence

    International Nuclear Information System (INIS)

    Layral, S.I.

    1987-01-01

    The aim of this study was to perform for the Embalse nuclear power plant, a probabilistic evaluation of loss-of-coolant accidents (LOCA) to identify the risks associated with them and to determine their acceptability in accordance with norms. This study includes all ruptures in the primary system that produce the automatic activation of 'emergency core cooling system'. Three starting events were selected for the probabilistic evaluation: 100% rupture of an input collector; 5% rupture of an input collector; 1.2% rupture of an input collector. At this stage the evaluation is focussed on the identification and quantization of the main failure sequences that follow a LOCA and lead to an uncontrolled reactor state or 'core meltdown'. The most important contribution to the core meltdown due to LOCA is the failure of supplies that are required for the emergency core cooling system. (Author)

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

    International Nuclear Information System (INIS)

    Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R.

    2006-01-01

    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)

  20. The Central Research Institute of Electric Power Industry and nuclear energy. Real images and views for compatibility of specialty and sociality

    International Nuclear Information System (INIS)

    Sato, Motohide

    2004-01-01

    The Central Research Institute of Electric Power Industry (CRIEPI) has been a motive power supporting electric energy and rich society in Japan as a center of electric power field in Japan under always challenging technologies advancing at a step since beginning of business as a special research institute on electrical power technology in Japan. And, on today receiving whole of liberalization on electric business, CRIEPI plans to carry out new development closer to society and nationals under a flag of 'contribution to society' by making its specialty and sociality compatible. Therefore, when social discussion on nuclear energy constructing basis of electric energy in Japan is noisy, here were summarized efforts, actual results, and topics for individual researching subjects shown as follows under showing basic attitude of CRIEPI to the nuclear energy: maintenance and administration techniques to rationally secure soundness of the light water reactor apparatuses; intermediate storage technique on spent fuels (concrete cask storage); survey, design and safety evaluation techniques supporting landfill disposal business of high level radioactive wastes; dry recycle technique and metal fuel fast reactors applicable to spent fuel processing at light water reactors; and small size fast reactors (4S reactors) usable for diverse applications. (G.K.)

  1. Advantages of using 3D design tools in the nuclear power plants projects; Ventajas del uso de herramientas de diseno 3D en los proyectos de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Roldan, P.; Melendro, J.; Gomez, A.; Hermana, I.

    2011-07-01

    It there is anything that distinguished Iberdrola Ingeneria y Construccion, as part of the Iberdrola Group, it is its firm commitment to innovation and continuous improvement. This is the philosophy that led the company to its interest in three-dimensional design tools back when they were in an early stage of development : very little international implementation, lack of integration with other applications, absence of previous experiences to understand the best possible configuration for each case, etc. Nevertheless, the company was able to see the tremendous advantage of having a construction program in the early months of a project- a detailed program that could predict, and therefore avoid, the problems that, if not anticipated, would arise in the construction phase when they result in higher costs, longer time frames and a multitude of complications. This is precisely what 3D design tools offer prediction and this has been proven in the latest combined cycle projects executed with these tools. A project executed without errors not only decreases cost and time overruns, but also necessarily increases the quality of the end result. Efficiency and quality: these are both basic goals of Iberdrola Ingenieria y Construccion. The knowledge of and skill in the use of these tools have grown at the same time that their development has reached increasingly higher levels. As a result, Iberdrola Ingenieria y Conctruccion now has intensive experience in the use of 3D design tools and is preprared for the future challenges posed by these tools, the capabilities of which have attained such heights that it is possible to take on one of the most technically challenging projects that exists a nuclear power plant. And we are ready. (Author)

  2. Study of thermocouples for control of high temperatures; Etude de thermocouples pour le reperage des hautes temperatures

    Energy Technology Data Exchange (ETDEWEB)

    Villamayor, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Faculte des Sciences de l' Universite de Lyon - 69 (France)

    1967-07-01

    Previous works have shown that the tungsten-rhenium alloys thermocouples were a good instrument for control of high temperatures. From its, the author has studied the W/W 26 per cent and W 5 per cent Re/W 26 per cent Re french manufactured thermocouples and intended for control of temperatures in nuclear reactors until 2300 deg. C. In 'out-pile' study he determines the general characteristics of these thermocouples: average calibration curves, thermal shocks influence, response times, and alloys allowing the cold source compensation. The evolution of these thermocouples under thermal neutron flux has been determined by 'in-pile' study. The observations have led the author to propose a new type of thermocouples settled of molybdenum-columbium alloys. (author) [French] Des travaux anterieurs ont montre que les thermocouples des alliages tungstene-rhenium etaient susceptibles de reperer avec precision des hautes temperatures. A partir de la, l'auteur a etudie las thermocouples W/W 26 pour cent Re et W 5 pour cent Re/W 26 pour cent Re de fabrication francaise et destines au controle des temperatures dans les reacteurs nucleaires, jusqu'a 2300 deg. C Dans l'etude 'hors-pile' il a determine les caracteristiques generales de ces thermocouples: courbes d'etalonnage moyen, influence des chocs thermiques, temps de reponse, et alliages assurant la compensation de soudure froide. L'etude 'en-pile' a permis de rendre compte de l'evolution de ces thermocouples sous flux neutroniques. Les phenomenes observes ont conduit l'auteur a proposer un nouveau type de thermocouples constitues d'alliages molybdene-niobium. (auteur)

  3. 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

  4. 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.

  5. Application of Nuclear Analytical Techniques in Elemental Characterization of Wadi El-Nakhil Alabaster, Central Eastern Desert, Egypt

    Directory of Open Access Journals (Sweden)

    Zain M. Alamoudi

    2016-01-01

    Full Text Available Instrumental neutron activation analysis (INAA is a powerful technique for trace element determination in rocks. Nine alabaster samples were collected from Wadi El-Nakhil located at the intersection of lat. 26°10′50′′N and long. 34°03′40′′E, central Eastern Desert, Egypt, for investigation by INAA and Energy Depressive X-Ray Fluorescence (EDXRF. The samples were irradiated by thermal neutrons at the TRIGA Mainz research reactor at a neutron flux of 7 × 1011 n/cm2·s. Twenty-two elements were determined, namely, As, Ba, Ca, Co, Cr, Sc, Fe, Hf, K, Mg, Mn, Na, Rb, U, Zn, Zr, Lu, Ce, Sm, La, Yb, and Eu. The chemical analysis of alabaster indicated having high contents of CaO and MgO and LOI and low contents of SiO2, Al2O3, Na2O, K2O, MnO, and Fe2O3.

  6. Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995; Informe de la Cuarta Recarga de Combustible. Central Laguna Verde. Unidad 1. Abril-Mayo 1995

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

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

    International Nuclear Information System (INIS)

    Agyemang, O.

    2008-06-01

    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

  9. Study of very heavy systems by means of INDRA: First evidence for a volume effect in the nuclear multifragmentation process; Etude de systemes tres lourds observes avec INDRA: Premiere mise en evidence d`un effet de volume dans le processus de multifragmentation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Frankland, John David [Inst. de Physique Nucleaire, Paris-11 Univ., 91 - Orsay (France)

    1998-12-10

    We present a study of Gd+U collisions at 36 AMeV measured with the INDRA multidetector, permitting almost complete detection (over 80%) of all the reaction products. We show that events exist which correspond to the multifragmentation of a single system comprising the majority of the nucleons for a cross-section of 2.6 mbarn, by isolating reactions for which the emitted fragments have lost all memory of the entrance channel. Such reactions correspond to neither the most central collisions nor the most isotropic events (in the fragments` momentum space), and therefore cannot be correctly distinguished from the dominant binary deeply-inelastic collisions using these criteria. An initial comparison of the selected data with a statistical code indicates that fragments are formed in a dilute, compact system, undergoing a self-similar expansion corresponding to a collective energy of between 1 and 1.5 MeV. Comparison with the same type of events observed in Xe+Sn collisions at 32 AMeV reveals the existence of a scaling law for the multifragmentation of systems of different mass at the same excitation energy per nucleon: fragment Z distributions are identical while their multiplicity increases proportionally to the mass of the multi-fragmenting system. This observation is interpreted as an experimental signal that this multifragmentation originates in a bulk instability of low-density nuclear matter (spinodal region). A complete semi-classical microscopic calculation for the two reactions, including the formation and multifragmentation by spinodal decomposition of very heavy, low-density systems, reproduces very well not only the experimental fragment multiplicities and Z distributions but also their mean kinetic energies, as well as the size distributions of the largest fragments. (author) 156 refs., 76 figs., 19 tabs.

  10. Preliminary studies on the closed cycle magneto aerodynamic converter; Etudes preliminaires sur les convertisseurs magnetohydrodynamiques fonctionnant hors d'equilibre thermodynamique

    Energy Technology Data Exchange (ETDEWEB)

    Ricateau, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    electron heating in argon-potassium can be achieved by magnetic fields from 1 to 2 Ts. Plans are being made to build an important facility which will work on the principle of hot shots. The gas generator will deliver cesium-seeded helium shots at a temperature of 2100 deg. K. The shot will last 1/ 10 s and the instantaneous thermal power will reach 1 MW. (author) [French] A cote des convertisseurs magnetoaerodynamiques a cycle ouvert qui transforment l'energie thermique contenue dans les gaz de combustion on etudie tres attentivement le convertisseur a cycle ferme qui peut tirer son energie de toute source de chaleur a haute temperature et tout particulierement des sources nucleaires. Avant une etude pratique de l'ensemble de la centrale les performances du convertisseur lui-meme doivent etre bien delimitees. Ces performances sont largement fonction de la conductivite du gaz utilise. Mais cette conductivite ne doit pas etre payee par une temperature techniquement inadmissible pour l'echangeur de chaleur. Dans le fluide de conversion on est amene a associer un gaz porteur, helium ou argon, et une semence facilement ionisable cesium ou potassium. L'ionisation purement thermique n'est efficace qu'a partir de 2500 deg. K, par contre le champ electrique developpe par induction dans le convertisseur peut, sous certaines conditions, accroitre la temperature electronique et developper une ionisation bien superieure a la valeur d'equilibre. Il devient alors possible d'ioniser le gaz a temperature moderee. Des travaux en cours ont pour but de preciser les conditions permettant de creer cette ionisation hors d'equilibre dans les gaz rares ensemenses. Des mesures ont ete faites a l'aide d'un plasmatron triphase do 500 kVA alimente a l'argon ensemence de potassium. On a fait debiter cet appareil dans une cellule permettant de mesurer les composantes tensorielles de la conductivite en presence de champ magnetique. Les valeurs trouvees dans les conditions d'equilibre thermodynamique

  11. 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)

    2014-01-01

    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

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

    Czech Academy of Sciences Publication Activity Database

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

    2016-01-01

    Roč. 93, č. 3 (2016), s. 034913 ISSN 0556-2813 R&D Projects: GA MŠk(CZ) LG13031 Institutional support: RVO:68378271 ; RVO:61389005 Keywords : ALICE collaboration * heavy ion collisions * centrality dependece Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders; BF - Elementary Particles and High Energy Physics (FZU-D) Impact factor: 3.820, year: 2016

  13. Operating Experience with Indian Point Nuclear Electric Generating Station; Experience d'exploitation de la centrale nucleaire d'Indian point; Opyt ehkspluatatsii Indian-pojntskoj yadernoj ehlektrostantsii; Experiencia adquirida con la explotacion de la central nucleoelectrica de Indian point

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, W. C.; Freyberg, R. H. [Consolidated Edison Company of New York, Inc., New York, NY (United States)

    1963-10-15

    predicted performance for the reactor. Further testing of response to load transients is to continue into the Spring of 1963. The Indian Point Station has proved to the satisfaction of our Company the feasibility of a combination nuclear and oil-fired plant to produce competitive power. The United States Atomic Energy Commission has been requested to issue a construction permit for the Company to build another nuclear plant, similar in design, but of 1000 MW capacity, to be located at Ravenswood which is within the corporate limits of the City of New York. Our Company is prepared to finance the venture with its own funds without subsidy of any kind as was the case with our Indian Point Station. (author) [French] La centrale No. 1 d'Indian Point se compose d'un reacteur a eau sous pression de 585 MWt, quatre circuits de refroidissement primaires avec des echangeurs de chaleur horizontaux, deux surchauffeurs au mazout de 500 000 kg/h et un turbogenerateur de 275 000 kW. Le combustible du reacteur est un melange d'oxyde d'uranium completement enrichi en {sup 235}U et d'oxyde de {sup 232}Th. L'installation se trouve au bord de l'Hudson a une quarantaine de kilometres au nord de New York. En raison de la proximite de cette ville, on a prevu des dispositifs de securite intrinseques exceptionnels contre le risque d'un emballement du reacteur et contre les rayonnements qui pourraient en resulter. La construction a ete terminee en mai 1962. Le combustible a ete charge en juin et le reacteur est entre en divergence pour la premiere fois le 2 aout 1962. On a ensuite procede, dans le courant du mois d'aout, a des essais a faible puissance (jusqu'a 5 MWt), a la temperature ambiante et a .des temperatures elevees. Le turbogenerateur aeteintegre pour la premiere fois au reseau de la ''Consolidated Edison'', le 16 septembre 1962. Les essais aux puissances allant jusqu'a 50% de la puissance theorique se sont prolonges jusqu'en novembre et ont ete marques par de frequents arrets automatiques

  14. A central region in the minor capsid protein of papillomaviruses facilitates viral genome tethering and membrane penetration for mitotic nuclear entry.

    Directory of Open Access Journals (Sweden)

    Inci Aydin

    2017-05-01

    Full Text Available Incoming papillomaviruses (PVs depend on mitotic nuclear envelope breakdown to gain initial access to the nucleus for viral transcription and replication. In our previous work, we hypothesized that the minor capsid protein L2 of PVs tethers the incoming vDNA to mitotic chromosomes to direct them into the nascent nuclei. To re-evaluate how dynamic L2 recruitment to cellular chromosomes occurs specifically during prometaphase, we developed a quantitative, microscopy-based assay for measuring the degree of chromosome recruitment of L2-EGFP. Analyzing various HPV16 L2 truncation-mutants revealed a central chromosome-binding region (CBR of 147 amino acids that confers binding to mitotic chromosomes. Specific mutations of conserved motifs (IVAL286AAAA, RR302/5AA, and RTR313EEE within the CBR interfered with chromosomal binding. Moreover, assembly-competent HPV16 containing the chromosome-binding deficient L2(RTR313EEE or L2(IVAL286AAAA were inhibited for infection despite their ability to be transported to intracellular compartments. Since vDNA and L2 were not associated with mitotic chromosomes either, the infectivity was likely impaired by a defect in tethering of the vDNA to mitotic chromosomes. However, L2 mutations that abrogated chromatin association also compromised translocation of L2 across membranes of intracellular organelles. Thus, chromatin recruitment of L2 may in itself be a requirement for successful penetration of the limiting membrane thereby linking both processes mechanistically. Furthermore, we demonstrate that the association of L2 with mitotic chromosomes is conserved among the alpha, beta, gamma, and iota genera of Papillomaviridae. However, different binding patterns point to a certain variance amongst the different genera. Overall, our data suggest a common strategy among various PVs, in which a central region of L2 mediates tethering of vDNA to mitotic chromosomes during cell division thereby coordinating membrane

  15. Contribution to the study of french pitchblendes; Contribution a l'etude des pechblendes francaises

    Energy Technology Data Exchange (ETDEWEB)

    Geffroy, J. [Commissariat a l' Energie Atomique, Lab. de Mineralogie, Centre de Chatillon (France). Centre d' Etudes Nucleaires; Sarcia, J.A. [Commissariat a l' Energie Atomique, Div. de la Crouzille, Haute Vienne (France). Centre d' Etudes Nucleaires

    1955-07-01

    The authors first review the characteristics of uraninite-pitchblende, as deduced of present literature. They set apart from typical pitchblende a black oxide aspect, which probably corresponds to neo-formations, and a 'para-pitchblende' aspect, which they relate to deep sur-oxidation of normal pitchblende. They insist on the easy replacement of pitchblende by silica. and give indications as to changes in vein stones (fluorite, quartz, etc...). A detailed study of paragenesis and successions in french uranium districts follows (including discussion of uranium of uranium-bearing coals). The authors attempt to classify french pitchblende veins. They are chiefly epithermal and poor in satellite ores. Three types of deposits are identified: massive - pitchblende type, silica type, fluorite type. These deposits, as those of Portugal, are included in granite, Central-European peri-batholitic types where uranium associates which Ni, Co, Bi and Ag, are in France both rare and poor. Finally, the authors attempt to bring out in the european Hercynian area a particular distribution of paragenetic types. (authors) [French] Les auteurs recapitulent d'abord les caracteres et les occurences de l'uraninite - pechblende, tels qu'ils peuvent etre degages de l'actuelle bibliographie. Ils exposent ensuite les faits qui du point de vue mineralogique seulement ressortent de l'etude mineralogique et chalcographique des pechblendes francaises et de leurs satellites. Ils distinguent de la pechblende-type un facies oxyde noir; correspondant probablement a une neoformation, et un facies parapechblende, qui est rapporte a une sur oxydation hypogene de la pechblende proprement dite. Ils insistent sur le facile remaniement de la pechblende par la slice; et donnent quelques precisions sur les modifications des gangues (fluorine, quartz, etc...). Suit l'etude detaillee des parageneses et des successions dans les districts uraniferes francais: Divisions du

  16. Simulation of the electric systems of the Laguna Verde nuclear power station; Simulacion de los sistemas electricos de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Lozano, Saul; Ruiz Ponce, Gerardo E [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1992-03-01

    In this article, the electric system models of the Laguna Verde Nuclear Power Station (CNLV) simulator, are presented. These models permit the functioning simulation, in the different operation modes of the main generator (Ruiz and Rodriguez 1991a), of the auxiliaries system and of the substation (Ruiz and Rodriguez 1991b), and of the emergency diesel generators system (Ruiz and Rodriguez 1991c). The general characteristics of such systems, considered as the basis to obtain the representative models, which were developed as modules in an independent way to be integrated in the simulator, are also described. [Espanol] En este articulo, se presenta los modelos de los sistemas electricos del simulador de la Central Laguna Verde (CLV). Estos modelos permiten simular el funcionamiento, en los diferentes modos de operacion del generador principal (Ruiz y Rodriguez, 1991a), del sistema de auxiliares y de la subestacion (Ruiz y Rodriguez, 1991b) y del sistema de generadores diesel de emergencia (Ruiz y Rodriguez, 1991c). Asimismo, se describen las caracteristicas generales de tales sistemas, consideradas como la base para obtener los modelos representativos, los cuales fueron desarrollados como modulos en forma independiente para integrarse al simulador.

  17. Brief communication: Ancient nuclear DNA and kinship analysis: the case of a medieval burial in San Esteban Church in Cuellar (Segovia, Central Spain).

    Science.gov (United States)

    Gamba, Cristina; Fernández, Eva; Tirado, Mirian; Pastor, Francisco; Arroyo-Pardo, Eduardo

    2011-03-01

    The aim of this work was to investigate a very common situation in the archaeological and anthropological context: the study of a burial site containing several individuals, probably related genetically, using ancient DNA techniques. We used available ancient DNA and forensic protocols to obtain reliable results on archaeological material. The results also enabled molecular sex determination to be compared with osteological data. Specifically, a modified ancient DNA extraction method combined with the amplification of nuclear markers with the AmpFlSTR®MiniFiler™ kit(Applied Biosystems) was used. Seven medieval individuals buried in four niches dated in the 15th Century at San Esteban Church in Cuellar (Segovia, Central Spain) were analyzed by the proposed method, and four of seven provided complete autosomal short tandem repeat (STRs) profiles. Kinship analyses comprising paternity and sibship relations were carried out with pedigree-specific software used in forensic casework. A 99.98% paternity probability was established between two individuals, although lower percentages (68%) were obtained in other cases, and some hypothetical kinship relations were excluded. The overall results could eventually provide evidence for reconstructing the historical record. Copyright © 2010 Wiley-Liss, Inc.

  18. Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

  19. 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)

    Birraux, C.

    2002-01-01

    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.)

  20. Etudes sur le Portugal au Temps de l'Humanisme

    Directory of Open Access Journals (Sweden)

    J. Cruz Costa

    1953-06-01

    Full Text Available BATAILLON (Marcel. — Etudes sur le Portugal au Temps de l'Humanisme.  Acta Universitatis Conimbrigencis, 1952, 309 pp. (Primeiro Parágrafo do Artigo O Prof. Marcel Bataillon, erudito dos mais inteligentes da França atual, autor de uma obra que é hoje impr:scindível para quem pretenda estudar o humanismo renascentista na Espanha ou em Portugal, diríamos melhor, talvez: para quem pretenda estudar o Humanismo e a Renascença, — acaba de publicar, na coleção Acta Universitatis Conimbrigencis, êste volume no qual reune alguns trabalhos da mais alta importância para o conhecimento de muitos aspectos da vida espiritual portuguêsa do século XVI.

  1. Study of transfers and their interactions with self-healing in the cracks to increase the service life of infrastructures (bridges, nuclear centrals); Etude des transferts et de leurs interactions avec la cicatrisation dans les fissures pour prolonger la duree de service des infrastructures (ponts, centrales nucleaires)

    Energy Technology Data Exchange (ETDEWEB)

    Ismail, M

    2006-04-15

    Concrete structures are frequently cracked by the action of different types of physicochemical mechanisms (external loads, restrained shrinkage, internal expansion). Cracks could impair the durability of concrete structures by creating preferential paths for the penetration of various types of potentially aggressive agents (liquids, gases, and ions). The aim of this thesis is to study transport properties in mechanically induced cracks. The first objective of the study is to better understand the potential effect of critical crack opening and self-healing. Cracks were generated in an inert material (brick) and in old mortar samples of 28 days and 2 years of age. A mechanical expansive core was used to generate cracks of constant width across the thickness of the sample. For the brick material, results show that a mechanical interaction between the fracture surfaces (critical crack opening) can affect the chloride-diffusion process along a crack path. A critical crack opening was also found for mortar samples. The age at which cracks were generated is also an important parameter. Self-healing was found to be more important in young mortars (28 days). The second objective of this thesis is the prediction of airflow in cracked cementitious material samples. A model proposed by Rizkalla et al. was evaluated through the experimental measurement of the flow coefficient n and the friction coefficient k. A simplified model was proposed to predict airflow through a crack for laminar type flow. The third research objective is to study the effect of self-healing on airflow through cracked mortar samples stored in a 100% relative humidity environment. Results show that self-healing mainly occurs during the first two months of storage. SEM analysis of fracture surfaces shows the formation of self-healing products such as calcite, C-S-H, and ettringite. (author)

  2. Regulation imposed to nuclear facility operators for the elaboration of 'waste studies' and 'waste statuses'; Reglementation imposee aux exploitants d'installations nucleaires pour l'elaboration ''des etudes dechets'' et ''des bilans dechets''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-04

    This decision from the French authority of nuclear safety (ASN) aims at validating the new versions of the guidebook for the elaboration of 'waste studies' for nuclear facilities and of the specifications for the elaboration of 'waste statuses' for nuclear facilities. This paper includes two documents. The first one is a guidebook devoted to nuclear facility operators which fixes the rules of production of waste studies according to the articles 20 to 26 of the inter-ministry by-law from December 31, 1999 (waste zoning conditions and ASN's control modalities). The second document concerns the specifications for the establishment of annual waste statuses according to article 27 of the inter-ministry by-law from December 31, 1999 (rational management of nuclear wastes). (J.S.)

  3. 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.

  4. Study of the retention of radionuclides by ion-exchange resins contained in the circuits of a Pressurized Water Reactor; Etude de la retention des radionucleides dans les resines echangeuses d'ions des circuits d'une centrale nucleaire a eau sous pression

    Energy Technology Data Exchange (ETDEWEB)

    Gressier, F.

    2008-11-15

    Physico-chemical quality of fluids in nuclear power plant circuits must be maintained in order to limit contamination and dose rate especially when the shutdown takes place. Nevertheless, an optimum between diminishing liquid waste and limiting solid waste production has to be reached, but at affordable costs. Ion-exchange resins of purification circuits are used to fulfill this goal. In this work, different resin types have been characterized (exchange capacity, water and electrolyte sorption) and their selectivity towards Co{sup 2+}, Ni{sup 2+}, Cs{sup +} and Li{sup +} cations have been studied. We have shown that the two cation-exchange resins selectivity varies according to the nature and concentrations of their counter-ions. Moreover, flow rate (and thus hydro-kinetics) impact on species retention in a column has been characterized: the more the flow rate, the more the ionic leakage (output concentration divided by input concentration) is fast and the more the output concentration front is spread. A literature revue has enabled to put in light advantages and drawbacks of the models of interest to simulate operations of ion-exchange resins. Thus, the pure end-members mixing model associated to a non-ideality description of the resin phase based on the regular solutions model has been retained for modelling ion-exchange equilibrium. Ion-exchange kinetics has been described by mass transfer coefficients. Using the experimental results to determine model parameters, these last ones have been implemented in a speciation code CHESS, coupled with a hydrodynamic code in HYTEC. On the one hand, equilibrium experiments of ion retention have been simulated and, on the other hand, column retention tests have been modelled. Finally, selectivity variations and hydro-kinetics impacts have been simulated on some test cases so as to demonstrate the importance of taking these into account when simulating ion-exchange resins operations. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Kamenik, J.; Dulaiova, H. [Hawaii Univ., Manoa, Honolulu, HI (United States). Dept. of Geology and Geophysics; Buesseler, K.O.; Pike, S.M. [Woods Hole Oceanographic Institution, Woods Hole, MA (United States). Dept. of Marine Chemistry and Geochemistry; St' astna, K. [Czech Technical Univ., Prague (Czech Republic). Dept. of Nuclear Chemistry

    2013-07-01

    Surface seawater {sup 134}Cs and {sup 137}Cs 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 {sup 134}Cs values that were impacted by Fukushima releases. Between March and May 2011, {sup 134}Cs was not detected around the Hawaiian Islands and Guam. Here, most {sup 137}Cs activities (1.2-1.5 Bq m{sup -3}) were in the range of expected preexisting levels. Some samples north of the Hawaiian Islands (1.6-1.8 Bq m{sup -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{sup -3} (Station Aloha, 18 values). In contrast, samples collected between Japan and Hawaii contained {sup 134}Cs activities in the range of 1-4 Bq m{sup -3}, and {sup 137}Cs 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.

  7. Population distribution around French nuclear sites

    International Nuclear Information System (INIS)

    Bastien, M.C.

    1985-10-01

    With the help of two files respectively from the Institut geographique national (IGN) containing the geographic reference of all cities in France, and from the Institut national de la statistique et des etudes economiques (INSEE) containing the population figures of the 1982 census, the distribution of the population around a geographic point can be determined according to a given grid. Tables of population distribution around the 30 french nuclear sites were obtained by this method; however, at a short distance from a site, a detailed local examination/survey/investigation is necessary. Data shall have to be collected to estimate the non-french population around frontier sites [fr

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

    International Nuclear Information System (INIS)

    1982-01-01

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

  9. 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

  10. Second IAEA advisory group meeting on transactinium isotope nuclear data, CEN Cadarache, France, 2-5 May 1979

    International Nuclear Information System (INIS)

    Lorenz, A.

    1979-09-01

    The Second Advisory Group Meeting on Transactinium Isotope Nuclear Data was convened by the IAEA Nuclear Data Section at the CEA Centre d'Etudes Nucleaires at Cadarache, France, from 2-5 May 1979. The meeting was attended by 37 representatives from 10 Member States and 2 international organizations. The main objectives of this meeting were to assess the transactinium nuclear data (TND) requirements for nuclear fission reactors and fuel cycles, with emphasis on new trends in nuclear technology, and to review the status of the required TND in the light of new measurements, calculations and evaluations. (author)

  11. Contribution to the study on the flow rate adjustment for gas cooled power reactors (1964); Contributiom a l'etude de reglage du debit pour les reacteurs industriels refroidis par gaz (1964)

    Energy Technology Data Exchange (ETDEWEB)

    Milliot, B. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1961-06-15

    1. This original study firstly defines the problem of the adjustment of the coolant flow rate in a reactor channel as a function of the corresponding heat transfer equations and of the local and temporal neutron flux. The necessity of such an adjustment is pointed out and the modifying parameters are studied. An adjustment study using the envelope of the possible flux curves is developed. A short study on the technology and the economical advantage of this adjustment is presented. Some measurements, made on G-1 and G-2, show the precision one can obtain from adjustment apparatus itself as well as from the complete reactor adjustment system. 2. Evolution of nuclear properties of fuel in an heterogeneous thermal reactor. In the first port of this paper, the phenomena of fuel evolution have been mainly pointed out. Now a bibliographical study more qualitatively than quantitatively has been done. This survey specifies the present theories and relates to a real effective cross section and also yields to the bases of such a nuclear calculation. (author) [French] 1. Cette etude originale definit d'abord le probleme du reglage du debit de refrigerant dans un canal de reacteur en fonction de la formulation du calcul des performances thermodynamiques de ce canal et des variations du flux neutronique dans l'espace et le temps. La necessite du reglage est ensuite mise en evidence et les parametres le modifiant sont etudies. Une methode de reglage, basee sur l'emploi d 'une courbe enveloppe des courbes de flux possibles, est donnee. Une breve etude de la technologie et des incidences economiques du reglage est presentee. Des mesures effectuees sur les reacteurs G-1 et G-2 montrent la precision que l'on peut attendre des dispositifs de reglage comme du reglage d'ensemble du reacteur lui-meme. 2. Evolution des proprietes nucleaires du combustible dans un reacteur heterogene a neutrons thermiques. Les phenomenes d'evolution du combustible

  12. Contribution to the study on the flow rate adjustment for gas cooled power reactors (1964); Contributiom a l'etude de reglage du debit pour les reacteurs industriels refroidis par gaz (1964)

    Energy Technology Data Exchange (ETDEWEB)

    Milliot, B [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1961-06-15

    1. This original study firstly defines the problem of the adjustment of the coolant flow rate in a reactor channel as a function of the corresponding heat transfer equations and of the local and temporal neutron flux. The necessity of such an adjustment is pointed out and the modifying parameters are studied. An adjustment study using the envelope of the possible flux curves is developed. A short study on the technology and the economical advantage of this adjustment is presented. Some measurements, made on G-1 and G-2, show the precision one can obtain from adjustment apparatus itself as well as from the complete reactor adjustment system. 2. Evolution of nuclear properties of fuel in an heterogeneous thermal reactor. In the first port of this paper, the phenomena of fuel evolution have been mainly pointed out. Now a bibliographical study more qualitatively than quantitatively has been done. This survey specifies the present theories and relates to a real effective cross section and also yields to the bases of such a nuclear calculation. (author) [French] 1. Cette etude originale definit d'abord le probleme du reglage du debit de refrigerant dans un canal de reacteur en fonction de la formulation du calcul des performances thermodynamiques de ce canal et des variations du flux neutronique dans l'espace et le temps. La necessite du reglage est ensuite mise en evidence et les parametres le modifiant sont etudies. Une methode de reglage, basee sur l'emploi d 'une courbe enveloppe des courbes de flux possibles, est donnee. Une breve etude de la technologie et des incidences economiques du reglage est presentee. Des mesures effectuees sur les reacteurs G-1 et G-2 montrent la precision que l'on peut attendre des dispositifs de reglage comme du reglage d'ensemble du reacteur lui-meme. 2. Evolution des proprietes nucleaires du combustible dans un reacteur heterogene a neutrons thermiques. Les phenomenes d'evolution du combustible tiennent une place importante dans l'etude

  13. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands; Guide d'examen pour l'etude de l'impact radiologique d'une installation nucleaire de base (INB) fournie a l'appui des demandes d'autorisation de rejets

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M; Despres, A; Supervil, S; Conte, D; Hubert, P; Oudiz, A; Champion, D

    2002-10-01

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  14. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands; Guide d'examen pour l'etude de l'impact radiologique d'une installation nucleaire de base (INB) fournie a l'appui des demandes d'autorisation de rejets

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M.; Despres, A.; Supervil, S.; Conte, D.; Hubert, P.; Oudiz, A.; Champion, D

    2002-10-01

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  15. Monetary valorization of the sanitary and environmental impacts of a nuclear accident: synthesis of ''ExternE'' studies, interests and limits of complementary developments; Valorisation monetaire des impacts sanitaires et environnementaux d'un accident nucleaire: synthese des etudes externe, interets et limites de developpements complementaires

    Energy Technology Data Exchange (ETDEWEB)

    Schieber, C.; Schneider, Th

    2002-09-01

    This document constitutes a synthesis of the various available methods for the monetary evaluation of the nuclear accidents impacts in order to reveal the already evaluated impacts, those which need complementary developments and those for which the monetary approach currently seems to come up against limits. It is based primarily on the approach realized by the ''ExternE'' project of the European Commission, consisting in the evaluation of the external costs of the nuclear energy industry. (A.L.B.)

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  17. Etude de la qualité physico-chimique et biologique des eaux du ...

    African Journals Online (AJOL)

    Etude de la qualité physico-chimique et biologique des eaux du fleuve Niger à Niamey. ... le récepteur principal des rejets d'eaux usées de la ville de Niamey, capital du ... La description de ces taxons montre une variation de la structure des ...

  18. English Department Reforms at the Hautes Etudes Commerciales: Entering the Nineties.

    Science.gov (United States)

    Shanahan, Daniel

    1993-01-01

    Discusses the reforms made in the fall of 1990 in the English department at the Ecole Hautes Etudes Commerciales (Paris, France), which were based on the basis of a combination of literature-culture and second- and foreign-language acquisition pedagogical biases. (four references) (VWL)

  19. Contribution a l'etude des plantes alimentaires mineures dans la ...

    African Journals Online (AJOL)

    Contribution a l'etude des plantes alimentaires mineures dans la prefecture de Dankpen (Togo). AB Kebenzikato, S Akpavi, K Batawila, K Wala, M Dourma, K Kossi-Titrikou, KS Amouzou, I Butare, H Dantsey-Barry, K Akpagana ...

  20. 152 Etude de cas sur l'impact des amendements organiques vis-à ...

    African Journals Online (AJOL)

    john mukalay

    Etude de cas sur l'impact des amendements organiques vis-à-vis de la salinité en culture de bananier. Michel Mazinga KWEY1, Séverin Kalala BANZE2 et John Banza MUKALAY2*. 1Laboratoire des cultures in vitro, Département de phytotechnie, Faculté des sciences agronomiques,. Université de Lubumbashi, BP 1825, ...

  1. 186 Etude théorique du transport électronique par la simulation ...

    African Journals Online (AJOL)

    youness

    Choukria SAYAH et al. 186. Etude théorique du ... For that we carried out the microscopic simulations, based on the Monte. Carlo method. ... intervalles, piezoelectric as well as the interactions of alloy and on ionized impurities. ..... SAYA et al. 198. [5] - R. W. Hockney, J. W. Eastwood, "Computer simulation using particles",.

  2. Etude comparative de la flore aux abords des cours d'eau dans les ...

    African Journals Online (AJOL)

    Etude comparative de la flore aux abords des cours d'eau dans les zones hypo et hyper endémiques d'ulcère de Buruli en Côte d'Ivoire. C. Cisse Boni, E. Ehouman, D. Soro, M.W. Kone, A. Bakayoko, F. Dembele, K. Bauthire, M Dosso ...

  3. Some equipment for graphite research in swimming pool reactors; Quelques dispositifs d'etude du graphite dans les piles piscines

    Energy Technology Data Exchange (ETDEWEB)

    Seguin, M; Arragon, Ph; Dupont, G; Gentil, J; Tanis, G [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    The irradiation devices described are used for research concerning reactors of the natural uranium type, moderated by graphite and cooled by carbon dioxide. The devices are generally designed for use in swimming pool reactors. The following points have been particularly studied: - maximum use of the irradiation volume, - use of the simplest technological solutions, - standardization of certain constituent parts. This standardization calls for precision machining and careful assembling; these requirements are also true when a relatively low irradiation temperature is required and the nuclear heating is pronounced. Finally, the design of these devices is suitable for the irradiation of other fissile or non-fissile materials. (authors) [French] Les dispositifs d'irradiation decrits servent aux etudes relatives a la filiere des reacteurs a uranium naturel, moderes au graphite et refroidis par le gaz carbonique. Ils sont generalement concus pour etre utilises dans des piles piscines. L'accent a ete mis sur: - l'utilisation au maximum du volume d'irradiation, - le recours aux solutions technologiques les plus simples, - la standardisation de certaines parties constitutives. Cette standardisation impose un usinage precis et un montage soigne, lesquels sont egalement necessaires lorsqu'on doit obtenir une temperature d'irradiation relativement basse alors que l'echauffement nucleaire est important. Enfin, la conception de ces dispositifs est valable pour irradier d'autres materiaux non fissiles ou fissiles. (auteurs)

  4. Study of deuterons induced nuclear reactions on light elements (N, Al and Si): Application to containment materials of radioactive wastes; Etude des reactions nucleaires induites par des deuterons sur des elements legers (N, Al, Si): application aux materiaux de confinement des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pellegrino, St

    2004-03-01

    Nuclear reaction analysis is well adapted to the quantification of light element. Profiles of concentration in order to follow elements migration into materials can be undertaken. This technique is used to study the behavior of the future matrices for nuclear waste containment. This technique is isotopic, characterized by a good signal-to-background ratio and a very low detection limit. The probability of a nuclear reaction is linked to a parameter called 'cross section' we have to know in order to carry out quantitative analysis. We have determined excitation curves for nitrogen, aluminium and silicon. These experiments were done with deuterons from 0.5 to 2 MeV. Two methods for the cross section characterization are presented and are in agreement with each other. The second one reduces uncertainty. Data are incorporated in the simulation software SIMNRA. We have compared the results obtained on different samples when we use data in literature or data of the study. We have noticed a great fit improvement with the data of this study. The new cross sections of this work will be integrated in the general data base SIGMABASE. Applications on materials such as Si{sub 3}N{sub 4}, nano-metric powders, WCN and nuclear glass YLaMgSiAlON studied for radioactive waste containment are also presented. (author)

  5. F{sup 19} relaxation in non-magnetic hexafluorides; Contribution a l'etude de la relaxation des fluors dans les hexafluorures non magnetiques

    Energy Technology Data Exchange (ETDEWEB)

    Rigny, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-12-01

    The interesting properties of the fluorine magnetic resonance in the hexafluorides of molybdenum, tungsten and uranium, are very much due to large anisotropies of the chemical shift tensors. In the solid phases these anisotropies, the values of which are deduced from line shape studies, allow one to show that the molecules undergo hindered rotations about the metal atom. The temperature and frequency dependence of the fluorine longitudinal relaxation times shows that the relaxation is due to the molecular motion. The dynamical parameters of this motion are then deduced from the complete study of the fluorine relaxation in the rotating frame. In the liquid phases, the existence of anisotropies allows an estimation of the different contributions to the relaxation. In particular, the frequency and temperature dependence of the relaxation shows it to be dominated by the spin-rotation interaction. We have shown that the strength of this interaction can be deduced from the chemical shifts, and the angle through which the molecule rotates quasi-freely can be determined. In the hexafluorides, this angle is roughly one radian at 70 C, and with the help of this value, the friction coefficients which describe the intermolecular interactions are discussed. (author) [French] Les proprietes de la resonance magnetique des fluors dans les hexafluorures de molybdene, tungstene et uranium sont influencees par l'existence de deplacements chimiques tres anisotropes. Dans les phases solides, la valeur de cette anisotropie peut etre determinee par l'analyse des formes de raies et son existence permet de montrer que les molecules sont en rotation empechee autour de leur atome central. L'etude du temps de relaxation longitudinal en fonction de la temperature et de la frequence montre que la relaxation est due aux mouvements moleculaires, aux plus hautes temperatures. Les proprietes dynamiques du mouvement sont obtenues par l'etude complete de la relaxation spin-reseau dans le referentiel

  6. Alecto 2 - interaction studies; Alecto 2 - etudes d'interaction

    Energy Technology Data Exchange (ETDEWEB)

    Brunet, J P; Clouet d' Orval, Ch; Mougniot, J C; Penet, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    Weak interactions were experimentally studies with the tank of the critical assembly Alecto II and one, two or three bottles containing solutions of various concentrations. In particular, was studied the validity of certain classical assumptions, shielding effects, screening and semi-reflexion effects, importance of thermal coupling. The method of the 'k{sub eff}, solid angle' is shown to apply to such a system. The determination by divergence and pulsed neutron technique of the reactivity related to a millimeter of solution level affords the obtention of critical heights in terms of reactivity. (authors) [French] Une etude experimentale d'interactions faibles a ete faite entre la cuve de l'experience critique ALECTO II et une, deux ou trois bouteilles contenant des concentrations variees. On etudie, en particulier, la validite de certaines hypotheses classiques, effets d'ombre, d'ecrans, de semi-reflexion, importance du couplage thermique. On montre d'autre part que la methode du 'K{sub eff}, angle solide' peut s'appliquer a un tel systeme. La determination par divergence et neutrons pulses de la reactivite liee au millimetre de solution permet de traduire les hauteurs critiques obtenues, en terme de reactivite. (auteurs)

  7. Baby fission chambers; Etude de chambres a fission miniatures

    Energy Technology Data Exchange (ETDEWEB)

    Guery, U; Tachon, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    The present report is intended, on the one band, as a study of the main types of fission chambers produced to date, and on the other, to deal more generally with this type of detector. Originally, it was with a view to the charting of neutron scatter in 'Proserpine' that the authors undertook the study of these chambers. During the course of the task, it was considered worth tbe trouble of developing its scope to include a more general application: neutron scatter measurement of various energy neutrons within a reduced volume with slight local disturbance. (author) [French] Le present rapport se propose, d'une part, d'exposer les principales realisations de chambres a fission, d'autre part de faire une mise au point a caractere plus general sur ces detecteurs. Au depart, c'est surtout en vue des mesures de densite neutronique dans 'Proserpine' que les auteurs ont etudie ces chambres; au cours de la mise au point, il a paru interessant de developper leur etude pour des applications plus generales: mesures de densites de neutrons de differentes energies dans un element de volume tres reduit et avec faible perturbation locale. (auteur)

  8. SEPA (Service d'etudes, de Procedes et Analyses)

    International Nuclear Information System (INIS)

    2017-01-01

    The SEPA (Service d'etudes, de Procedes et Analyses), is an engineering department specializing in the analysis and processing of uranium ore. It comes from a long tradition of mining in France that began sixty-five years ago with the French Atomic Energy Commission (CEA) and that has been carried on by COGEMA and then Areva. SEPA brings a combination of experience and excellence to its activities thanks to its multidisciplinary staff (mineralogists, chemists, mechanical engineers, instrumentation specialists...), who come from diverse cultural backgrounds. Today, the SEPA draws on its wealth of know-how and expertise to devise and develop new methods for processing and valorizing ores everywhere in the world. Its mission is to: - Develop and conduct laboratory tests on methods for processing uranium and other valuable elements such as molybdenum, vanadium, rare earths, niobium, tantalum and thorium; - Analyze ores obtained during prospecting at locations all over the world; -Serve as an advisor in the commissioning of Areva industrial units and ore processing plants; -Perform environmental analyses during the full period of mining operations; -Conduct audits and provide advice on processes and analysis methods; -Carry out research and development in all aspects of minerals treatment (including the filing of patents). The SEPA combines experience, skills and a global approach to technologies used in ore processing. Its role is to continually improve the processes for extracting, processing and valorizing ores while protecting the environment

  9. Baby fission chambers; Etude de chambres a fission miniatures

    Energy Technology Data Exchange (ETDEWEB)

    Guery, U.; Tachon, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    The present report is intended, on the one band, as a study of the main types of fission chambers produced to date, and on the other, to deal more generally with this type of detector. Originally, it was with a view to the charting of neutron scatter in 'Proserpine' that the authors undertook the study of these chambers. During the course of the task, it was considered worth tbe trouble of developing its scope to include a more general application: neutron scatter measurement of various energy neutrons within a reduced volume with slight local disturbance. (author) [French] Le present rapport se propose, d'une part, d'exposer les principales realisations de chambres a fission, d'autre part de faire une mise au point a caractere plus general sur ces detecteurs. Au depart, c'est surtout en vue des mesures de densite neutronique dans 'Proserpine' que les auteurs ont etudie ces chambres; au cours de la mise au point, il a paru interessant de developper leur etude pour des applications plus generales: mesures de densites de neutrons de differentes energies dans un element de volume tres reduit et avec faible perturbation locale. (auteur)

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

    International Nuclear Information System (INIS)

    Gasselblat, A.D.

    2010-01-01

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

  11. The radiological accident of Goiania and the acceptance by the public of new nuclear power plants; El accidente radiologico de Goiania y la aceptacion publica de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Meldonian, N L; Mattos, L A.T. [Grupo de Energia e Ambiente, Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)

    1998-12-01

    Misunderstandings on the peaceful uses and the safety of nuclear energy have been a leading cause of apprehension in Brazilian public opinion. A lack of knowledge of the characteristics and destination of radioactive wastes and negative media coverage of the use of nuclear energy have aggravated this situation. Believing that applications of nuclear energy are harmful to the population`s welfare and the environment, Brazilian public opinion is opposed to the utilization of nuclear energy, and in particular to the construction of new nuclear power plants. For this reason, the Brazilian nuclear sector should promote a more intensive programme of public discussion, directed not solely at the technical and scientific communities, but also at the Brazilian public at large. Such a campaign would contribute towards a better understanding by Brazilian society of the different uses of nuclear energy and would present arguments in support of the benefits of this form of energy. Moreover, a campaign of this kind would show that negative associations about the use of electricity derived from nuclear power, which are based on the Goiania radiological accident, are not justified. (author) 10 refs, 5 tabs

  12. Etude aerodynamique d'un jet turbulent impactant une paroi concave

    Science.gov (United States)

    LeBlanc, Benoit

    Etant donne la demande croissante de temperatures elevees dans des chambres de combustion de systemes de propulsions en aerospatiale (turbomoteurs, moteur a reaction, etc.), l'interet dans le refroidissement par jets impactant s'est vu croitre. Le refroidissement des aubes de turbine permet une augmentation de temperature de combustion, ce qui se traduit en une augmentation de l'efficacite de combustion et donc une meilleure economie de carburant. Le transfert de chaleur dans les au bages est influence par les aspects aerodynamiques du refroidissement a jet, particulierement dans le cas d'ecoulements turbulents. Un manque de comprehension de l'aerodynamique a l'interieur de ces espaces confinees peut mener a des changements de transfert thermique qui sont inattendus, ce qui augmente le risque de fluage. Il est donc d'interet pour l'industrie aerospatiale et l'academie de poursuivre la recherche dans l'aerodynamique des jets turbulents impactant les parois courbes. Les jets impactant les surfaces courbes ont deja fait l'objet de nombreuses etudes. Par contre des conditions oscillatoires observees en laboratoire se sont averees difficiles a reproduire en numerique, puisque les structures d'ecoulements impactants des parois concaves sont fortement dependantes de la turbulence et des effets instationnaires. Une etude experimentale fut realisee a l'institut PPRIME a l'Universite de Poitiers afin d'observer le phenomene d'oscillation dans le jet. Une serie d'essais ont verifie les conditions d'ecoulement laminaires et turbulentes, toutefois le cout des essais experimentaux a seulement permis d'avoir un apercu du phenomene global. Une deuxieme serie d'essais fut realisee numeriquement a l'Universite de Moncton avec l'outil OpenFOAM pour des conditions d'ecoulement laminaire et bidimensionnel. Cette etude a donc comme but de poursuivre l'enquete de l'aerodynamique oscillatoire des jets impactant des parois courbes, mais pour un regime d'ecoulement transitoire, turbulent

  13. Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition); Diseno del sistema de refrigeracion del reactor y los sistemas asociados en las centrales nucleares. Guia de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

  14. The study of some thiazinic and indaminic dye syntheses induced by ionising radiation; Etude de quelques syntheses de colorants thianziniques et indaminiques amorcees par les rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

    Balestic, S [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-03-15

    With a view to finding some radiochemical reactions applicable on an industrial scale for evaluating the radioactive waste from nuclear reactors, a systematic study was made of the radiochemical synthesis of thiazinic dyes such as methylene blue and Lauths' violet, on which the first tests were carried out in 1954. The first part of the study concerned the identification and the dosage, during radiolysis, of dyes by means of their absorption spectra after separation from the reaction medium by adsorption chromatography or ion-exchange; other radiolysis products such as ammonium chloride and hydrogen peroxide were also identified. During a later stage by systematically varying the physico-chemical parameters it was possible to determine the most favourable conditions for radio-synthesis; the maximum radiochemical yields obtained had the following values: G (Lauths' violet) 1,65; G (Methylene blue) = 1,75. Furthermore, the study of the influence of variously substituted aminated products on the radiochemical yield showed the possibility of synthesising Bindsehedlers green and Wursters blue by radiochemical methods. Finally the discovery of a fundamental intermediate product, Wursters red, together with the kinetic study of the chemical synthesis of methylene blue made it possible to determine the main stages of the reaction mechanism and to decide which of these stages could be attributed to ionising radiations in the case of the radiochemical synthesis. (author) [French] Dans le but de trouver des reactions radiochimiques susceptibles d'une application industrielle pour valoriser les dechets radioactifs provenant des reacteurs nucleaires, il a ete entrepris une etude systematique de la synthese radiochimique des colorants thiazimiques tels que le Bleu de Methylene et le Violet de Lauth dont les premiers essais ont ete effectues par Loiseleur en 1954. La premiere partie de l'etude a porte sur l'identification et le dosage des colorants formes au cours de la radiolyse

  15. 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)

  16. Beta decay and magnetic moments as tools to probe nuclear structure. Study of neutron-rich nuclei around N=40; Decroissance beta et moments magnetiques comme outils pour sonder la structure nucleaire. Etude des noyaux riches en neutrons autour de N=40

    Energy Technology Data Exchange (ETDEWEB)

    Matea, I

    2003-12-01

    The evolution of nuclear structure in nuclei far from the {beta} stability line is one of the 'hot topics' in modern experimental and theoretical nuclear physics. The present thesis is devoted to the study of structure of neutron-rich nuclei around N=40. The evolution of the neutron g9/2 orbital with increasing number of neutrons is one of the key points defining the structure of these nuclei at low excitation energy. We used for this investigation as experimental tools the magnetic dipole moments measurements and the {beta} decay spectroscopy. For the measurement of the gyromagnetic factor of the 9/2{sup +} isomeric state in Fe{sup 61} we have applied the TDPAD method. This method (like most of measurements of nuclear moments) requires an oriented ensemble of nuclei. The orientation of Fe{sup 61m} was achieved via the fragmentation of Ni{sup 64} at 55 MeV/u and the selection of the fragment momentum with the LISE spectrometer at GANIL. The experimental device was specially conceived to preserve the alignment up to the implantation point. The measured value of the g factor was compared with large-scale shell model and Hartree-Fock-Bogoliubov model predictions. The nuclei studied via {beta} decay were produced by the fragmentation of Kr{sup 86} at 58 MeV/u. For the selection of reaction products we used for the first time the LISE2000 spectrometer and for the detection of {gamma} rays four EXOGAM clover detectors. We measured 5 new lifetimes and 4 lifetimes with a higher precision. From the prompt {beta}{gamma} coincidences we identified new states in the daughter nuclei, as it is the case of the first 2{sup +} excited states in Fe{sup 68} and Ni{sup 72}. The results were compared with the predictions of the large-scale shell model. Other transitions were observed for the first time in {beta}{gamma} decay of Ti{sup 60}, Fe{sup 70} and Co{sup 71,73}. (author)

  17. The Use of the Moessbauer Effect in Investigating the Chemical Effects of Nuclear Transmutations in Oxygenous Compounds of Manganese and Tin; Utilisation de l'Effet Moessbauer pour l'Etude des Effets Chimiques des Transformations Nucleaires dans les Composes de Manganese et d'Etain; 0418 0421 0421 041b 0415 0414 ; Empleo del Efecto Moessbauer para Investigar las Transformaciones Nucleares de Compuestos Oxigenados de Estano y de Manganeso

    Energy Technology Data Exchange (ETDEWEB)

    Nesmejanov, An. N.; Babeshkin, A. M.; Kosev, N. P.; Bekker, A. A.; Lebedev, V. A. [Moskovskij Gosudarstvennyj Universitet Im. M.V. Lomonosova, Moskva, SSSR (Russian Federation)

    1965-04-15

    auteurs ont etudie les formes de stabilisation des atomes de recul de 56 Mn des solutions et des echantillons solides irradies de permanganate, ainsi que celles des atomes de recul de {sup 119m}Sn dans l'oxyde et le bioxyde d'etain. Les echantillons de permanganate ont ete irradies dans un bloc de paraffine a l'aide d'une source au polonium-beryllium donnant un flux de neutrons de 10{sup 7} a 10{sup 8} n/cm{sup 2} * s. Les atomes chauds de {sup 56}Mn qui se forment peuvent avoir les valences +7, +4 et inferieures. Les echantillons (SnO et SnO{sub 2}), exposes dans un reacteur a un flux de 2,2 * 10{sup 13} n/cm{sup 2} * s pendant 1800 h, ont ete directement utilises pour la preparation de sources destinees a l'etude de l'absorption par resonance des phonons dans une installation fonctionnant a vitesse constante. Des composes d'etain correspondants ont ete employes comme absorbeurs. On n'a constate la presence d'atomes {sup 119m}Sn de recul qu'a l'etat tetravalent. Sur la base des donnees obtenues, les auteurs examinent le mecanisme de stabilisation des atomes de recul. (author) [Spanish] Los metodos utilizados corrientemente para estudiar el estado quimico de los atomos de retroceso, esto es, aquellos asociados a los cambios de fase (analisis quimico, cromatografia, electroforesis), lo mismo que el recocido, solo permiten conocer indirectamente el mecanismo de estabilizacion de los atomos calientes. Cuando el analisis se efectua por el metodo de absorcion por resonancia de los cuantos gamma sin retroceso, no se introduce en la muestra ninguna modificacion capaz de influir en las formas de estabilizacion, incluso si la estabilidad no es muy grande. Los autores investigaron las formas de estabilizacion de los atomos de retroceso del {sup 56}Mn en soluciones y muestras solidas de permanganato irradiadas, y las de los atomos de retroceso del {sup 119m}Sn en oxido estannico y estannoso. Las muestras del permanganato se irradiaron en un bloque de parafina con un flujo de 10{sup

  18. Integration of in-service inspection works in the objectives of nuclear power plants; Integracion de los trabajos de inspeccion en servicio en los objectivos de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, M.; Lopez, M.A.

    1996-09-01

    The present articles summarizes the objectives of Spanish NPPs and the in-service inspection aspect in these objectives. The Safety maintenance, lifetime of nuclear power plants, reduction of doses and wastes and the participation of main are evaluated.

  19. 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.

  20. 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)

    Andre, J.-J.; Drouet, J.; Leblanc, P.

    1979-01-01

    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 [fr

  1. Nuclear fragmentation for Xe+Au and Xe+Ag systems at an energy of 44 A.MeV, formation and decay of hot nuclei; Etude de la fragmentation nucleaire pour les systemes XE+AU et XE+AG a 44 A.MeV, production et decroissance de noyaux chauds

    Energy Technology Data Exchange (ETDEWEB)

    Meslin, C.

    1995-01-01

    A study of the formation and the decay of hot nuclear fragments produced in the reactions Xe+Au and Xe+Ag at an energy of 44 A.MeV is presented in this thesis. The 4{pi} experimental setup consisted of four multidetectors -two for the detection of the fragments (Z>7; DELF and XYZT) and two for the detection of the charged particles (Z<6; MUR and TONNEAU) and allowed an analysis using ``complete events`` (80 % of the total charge and the total parallel linear momentum of the entrance channel) to be carried out. The reaction mechanism is binary with as observed at low energy an almost complete relaxation of the incident energy. The collision results in two hot fragments at the beginning of the exit channel which decay by evaporation and/or fragmentation. In addition of these two body events, we have identified a new dynamic mechanism where we detect a small fragment, called the neck, coming form the overlap of the nuclei during the interaction, in coincidence with a projectile-like fragment and a target-like fragment. For the most dissipative collisions, the deep inelastic collision have allowed an estimation of the lifetime of the hot nuclear fragments to be made. This is possible using proximity effects and fragment-fragment space-time correlations of the decay of one or two primary partners from the deep inelastic collisions. This method is seen to reach its limits in the case of the reactions studied here. (authors). 61 refs.

  2. Electrical systems at the nuclear power plant of Laguna Verde after the event in Fukushima; Sistemas electricos en la central nucleoelectrica Laguna Verde despues del evento de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Lopez J, J. F., E-mail: jflopez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose M. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2016-09-15

    During the event at the nuclear power plant of Fukushima Daichii (Japan), the electrical systems were affected both Onsite and Offsite, which were lost for a long time with irreversible consequences. Therefore, the Mexican Regulatory Body known as the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has taken various actions to review the current capacity of the electrical systems at the nuclear power plant of Laguna Verde (NPP-LV) before an event beyond the design bases. The CNSNS made special inspections to the NPP-LV to verify the current capacity of the electrical systems of Ac and Dc; as a result of the inspections, requirements were generated that must be met to demonstrate that has the capacity to deal with events beyond the design bases. In addition, CNSNS has participated in the Ibero-American Forum to deal with resistance testing. Is important to note that prior to the event at the nuclear power plant of Fukushima, the NPP-LV had implemented 1) the project Extended Power Increase in both Units of the NPP-LV, and 2) the Generic Charter 2006-02, both issues are considered contributions in the robustness of electrical systems. But it is also important to mention that the US Nuclear Regulatory Commission will soon issue mitigation strategies for a Station Blackout event, which could involve new actions at nuclear power plants. Based on the aforementioned, the CNSNS concludes that all the actions being taken contribute to the strengthening of the NPP-LV electrical systems, in order to increase their reliability, safety and operation when these are required to deal with events beyond the design bases as the event occurred in Fukushima Daichii and avoid as far as possible, damage in the reactor cores of the NPP-LV. (Author)

  3. Revival of nuclear power engineering in the Central-Eastern Europe in response to rising power demand and the problem of CO2 emission

    Energy Technology Data Exchange (ETDEWEB)

    Rozkosz, Grazyna; Kaszowski, Bartosz

    2010-09-15

    Safety and reliability of electric power supply is guarantee for stable development. Necessity of decommissioning of largely depreciated power plants and rising power demands (average ca. 3% per year) may cause energy deficit in CE Europe. Decision on construction new power plants is determined mainly by power energy generation costs. Nuclear power generation cost forecast is significantly lower than cost of energy from fossil fuels. Such factors offer a new view on source of ''clean and safe'' nuclear energy.

  4. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    1989-01-01

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

  5. Super-resolution imaging visualizes the eightfold symmetry of gp210 proteins around the nuclear pore complex and resolves the central channel with nanometer resolution

    NARCIS (Netherlands)

    Löschberger, A.; Van de Linde, S.; Debauvalle, M.C.; Rieger, B.; Heilemann, M.; Krohne, G.; Sauer, M.

    2012-01-01

    One of the most complex molecular machines of cells is the nuclear pore complex (NPC), which controls all trafficking of molecules in and out of the nucleus. Because of their importance for cellular processes such as gene expression and cytoskeleton organization, the structure of NPCs has been

  6. A review of the status of nuclear safety in the Central and East European Countries with special reference to the evaluation of the situation in Romania

    International Nuclear Information System (INIS)

    Webster, Simon

    2001-01-01

    This paper briefly presents the status of nuclear safety in the candidate countries in the light of the progress towards accession to the European Union, and draws particular attention to the recent evaluation made by the Atomic Questions Group of the Council of Ministers by reference to the general recommendations and the specific recommendations addressed to Romania appearing in the evaluation report. (author)

  7. Preparation and study of the properties of lead telluride and cadmium telluride diodes for use in nuclear spectrometry; Preparation et etude des proprietes de diodes au tellurure de plomb et au tellurure de cadmium en vue d'une utilisation en spectrometrie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Lancon, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-07-01

    This work studies the possibility of using high atomic number compound semiconductors, like lead telluride and cadmium telluride as to realize nuclear radiation detectors, specially in gamma ray spectrometry because of their high absorption coefficient. The problems related to the preparation of binary compounds are exposed. Experiments on PbTe show the influence of the conditions of preparation on the electrical properties of the semiconductor which are greatly dependent on the stoichiometry of the compound. PbTe surface-barrier diodes were realized and have been used to study the surface properties of this semiconductor. These diodes cannot detect nuclear radiations because of the too weak resistivity of our material. Different types of devices made of Cd Te have been studied. One of these diodes has been used as an alpha particle detector. We explain the relative poor performances of that detector by the presence of lattice defects in Cd Te where charge carriers may recombine themselves. By analysing the properties of gold diffused Cd Te diodes we identified this defect, the cadmium vacancy, the presence of which is due to the deviation from stoichiometry during the preparation of the material. (author) [French] Ce travail etudie la possibilite d'utiliser des semiconducteurs composes d'elements a numero atomique eleve, tels que le tellurure de plomb et le tellurure de cadmium pour la realisation de detecteurs de rayonnements nucleaires, grace notamment a la section efficace de capture elevee qu'ils presentent vis-a-vis des rayons gamma. On souligne les problemes relatifs a la preparation des composes binaires. Les experiences realisees sur PbTe mettent en evidence l'influence des conditions de preparation sur les proprietes electriques du semiconducteur qui dependent fortement de la stoechiometrie du compose. Nous avons realise des diodes au PbTe a barriere de surface qui ont permis de preciser les proprietes de surface de ce semiconducteur. La trop faible

  8. Structure study and properties of rare earth-rich glassed for the conditioning of nuclear waste; Etude des caracteristiques structurales et des proprietes de verres riches en terres rares destines au confinement des produits de fission et elements a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    Bardez, I

    2004-11-15

    A new nuclear glass composition, able to immobilize highly radioactive liquid wastes from high burn-up UO{sub 2} fuel, was established and its structure studied. The composition of the selected rare earth-rich glass is (molar %): 61.79 SiO{sub 2} - 8.94 B{sub 2}O{sub 3} - 3.05 Al{sub 2}O{sub 3} - 14.41 Na{sub 2}O - 6.32 CaO - 1.89 ZrO{sub 2} - 3.60 RE{sub 2}O{sub 3} (with RE = La, Ce, Pr and Nd) The aim of this study was to determine the local environment of the rare earth in this glass and also to glean information about the effect of glass composition on the rare earth neighbouring (influence of Si, B, Al, Na and Ca contents). To this end, several series of glasses, prepared from the baseline glass, were studied by different characterisation methods such as EXAFS spectroscopy at the neodymium L{sub III}-edge, optical absorption spectroscopy, Raman spectroscopy and {sup 29}Si, {sup 27}Al and {sup 11}B MAS-NMR. By coupling all the results obtained, several hypotheses about the nature of the rare earth neighbouring in the glass were proposed. (author)

  9. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

    Volino, F [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  10. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

    Volino, F. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  11. Development of an automatic scanning system for nuclear emulsion analysis in the OPERA experiment and study of neutrino interactions location; Developpement d'un systeme ultra rapide pour le scan des emulsions nucleaires d'OPERA et etude sur la localistion des vertex de l'interaction des neutrinos a l'aide de ce systeme

    Energy Technology Data Exchange (ETDEWEB)

    Arrabito, L

    2007-10-15

    Following Super Kamiokande and K2K experiments, Opera (Oscillation Project with Emulsion tracking Apparatus), aims to confirm neutrino oscillation in the atmospheric sector. Taking advantage of a technique already employed in Chorus and in Donut, the Emulsion Cloud Chamber (ECC), Opera will be able to observe the {nu}{sub {mu}} {yields} {nu}{sub {tau}} oscillation, through the {nu}{sub {tau}} appearance in a pure {nu}{sub {mu}} beam. The Opera experiment, with its {approx} 100000 m{sup 2} of nuclear emulsions, needs a very fast automatic scanning system. Optical and mechanics components have been customized in order to achieve a speed of about 20 cm{sup 2}/hour per emulsion layer (44 {mu}m thick), while keeping a sub-micro-metric resolution. The first part of this thesis was dedicated to the optimization of 4 scanning systems at the French scanning station, based in Lyon. An experimental study on a dry objective scanning system has also been realized. The obtained results show that the performances of dry scanning are similar with respect to the traditional oil scanning, so that it can be successfully used for Opera. The second part of this work was devoted to the study of the neutrino interaction location and reconstruction strategy actually used in Opera. A dedicated test beam was performed at CERN in order to simulate Opera conditions. The obtained results definitely confirm that the proposed strategy is well adapted for tau search. (author)

  12. Resonant ionization by laser beams: application to ions sources and to study the nuclear structure of radioactive tellurium isotopes; Ionisation resonante par faisceaux laser: application aux sources d'ions et a l'etude de la structure des noyaux radioactifs de tellure

    Energy Technology Data Exchange (ETDEWEB)

    Sifi, R

    2007-07-15

    The radioactive ion beams that are produced through current isotope separators are well separated according to the A mass but not according to the Z parameter. The resonant ionization through laser beams applied to ion sources allows the production of radioactive ion beam in a very selective and efficient way by eliminating the isobaric contamination. The first chapter is dedicated to the resonant ionization by laser beams, we describe the principle, the experimental setting, the lasers used, the ionization schemes and the domain of application. The second chapter deals with the application of resonant ionization to laser ion sources for the production of radioactive ion beams. We present experimental tests performed for getting copper ion beams. Resonant ionization through laser is also used in the spectroscopy experiments performed at the Isolde (isotope separation on-line device) installation in CERN where more than 20 elements are ionized very efficiently. The technique is based on a frequency scanning around the excitation transition of the atoms in order to probe the hyperfine structure. Laser spectroscopy allows the determination of the hyperfine structure as well as the isotopic shift of atoms. In the third chapter the method is applied to the spectroscopy of tellurium atoms. First, we define the 2 parameters on which the extraction is based: charge radius and nuclear moments, then we present several theoretical models that we have used to assess our experimental results. (A.C.)

  13. A study of filtering problems of background noise in nuclear spectrometry, improvement of signal-to-noise ratio, and of pulse characteristics produced by the optimum predictor device; Etude de problemes de filtrage de bruit de fond en spectrometrie nucleaire, amelioration du rapport signal sur bruit et des caracteristiques de l'impulsion mise en forme par le dispositif du predicteur optimum

    Energy Technology Data Exchange (ETDEWEB)

    Benda, J [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1967-05-01

    The purpose of nuclear spectrometry is the precise measurement of particles energy. The resolving power of a spectrometer design is an important factor. Two main phenomena are involved in the limitation of this resolving power: The statistical fluctuations of the detector itself, and the background noise. For a given noise, the theory of filters enables the calculation of networks specially designed for the improvement of signal to noise ratio. The proposed system should lead to an improvement of 10.5 per cent of this ratio. Experiments have confirmed this theoretical estimation. The predictor device also makes possible the obtaining of shortened pulses. (author) [French] Les mesures en spectrometrie nucleaire ont pour but la determination precise de l'energie des particules. Le pouvoir de resolution d'une chaine de spectrometrie est une caracteristique importante. Deux phenomenes principaux concourent a limiter ce pouvoir de resolution: les fluctuations statistiques du detecteur et le bruit de fond. Pour un bruit de fond donne, la theorie des filtres permet de calculer des reseaux susceptibles de modifier le rapport signal sur bruit. Le systeme propose permet d'ameliorer de 10.5 pour cent ce rapport lorsqu'on se place dans les conditions optimales. Les resultats experimentaux confirment les previsions. Le dispositif predicteur permet aussi un raccourcissement de l'impulsion dans le temps. (auteur)

  14. Study and development of a method allowing the identification of actinides inside nuclear waste packages, by active neutron or photon interrogation and delayed gamma-ray spectrometry; Etude et developpement d'une technique de dosage des actinides dans les colis de dechets radioactifs par interrogation photonique ou neutronique active et spectrometrie des gamma retardes

    Energy Technology Data Exchange (ETDEWEB)

    Carrel, F

    2007-10-15

    An accurate estimation of the alpha-activity of a nuclear waste package is necessary to select the best mode of storage. The main purpose of this work is to develop a non-destructive active method, based on the fission process and allowing the identification of actinides ({sup 235}U, {sup 238}U, {sup 239}Pu). These three elements are the main alpha emitters contained inside a package. Our technique is based on the detection of delayed gammas emitted by fission products. These latter are created by irradiation with the help of a neutron or photon beam. Performances of this method have been investigated after an Active Photon or Neutron Interrogation (INA or IPA). Three main objectives were fixed in the framework of this thesis. First, we measured many yields of photofission products to compensate the lack of data in the literature. Then, we studied experimental performances of this method to identify a given actinide ({sup 239}Pu in fission, {sup 235}U in photofission) present in an irradiated mixture. Finally, we assessed the application of this technique on different mock-up packages for both types of interrogation (118 l mock-up package containing EVA in fission, 220 l mock-up package with a wall of concrete in photofission). (author)

  15. Software for computers in the safety systems of nuclear power stations. Identical with IEC 45A(Central Office)88. Draft. Software fuer Rechner im Sicherheitssystem von Kernkraftwerken. Identisch mit IEC 45A(CO)88. Entwurf

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The basic principles for the design of nuclear instrumentation as specifically applied to the safety systems of nuclear power plants have been interpreted in existing standards as the IAEA ''Safety Guide 50-SG-D3'' with a view to hardwired systems. This publication has been developed to interprete these principles for the utilization of digital systems - multiprocessor distributed systems as well as larger scale central processor systems - in the safety systems of nuclear power plants. It is important to note that this document establishes no additional functional requirements for safety systems. Areas which have been dealt with because of the unique nature of digital computer systems especially the software are: a) Established hardware criterea as far as they affect the software with care taken to account for the high degree of interdependency between hardware and software. b) A general approach to software development to assure the production of the highly reliable software required. c) A general approach to software verification and computer system validation. d) Procedures for software maintenance, modification and configuration control. The systems are in accordance with the German KTA regulation KTA 3501.2. (orig./HP).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-10-15

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

  17. Singing as a Therapeutic Agent, inThe Etude, 1891-1949.

    Science.gov (United States)

    Hunter

    1999-01-01

    The Etude music magazine, founded by Theodore Presser, was one of a number of popular music magazines published in the years prior to the establishment of the music therapy profession in 1950. During its publication run from 1883 to 1957, over 100 music therapy related articles appeared, including 13 on the health benefits of singing published between 1891 and 1949. Written by authors with diverse backgrounds, such as the famous Battle Creek, Michigan physician John Harvey Kellogg and Boston music critic Louis C. Elson, the articles contained consistent and adamant support regarding the health benefits of singing. The advantages described were both physical and psychological, and were recommended prophylactically for well persons and therapeutically for ill persons. Although the articles varied in perspective, from philosophical to theoretical to pedagogical, there is a consistent holistic medicine theme that appeared almost ahead of its time and no doubt linked to the push for vocal music education in that era. The importance of The Etude in promulgating ideas that helped shape the early practice of music therapy should not be underestimated. For much of its publication run The Etude was the largest music periodical in print, reaching its peak circulation of 250,000 copies per month in 1924.

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

    CERN Document Server

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

    2016-03-25

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

  19. France's nuclear power programme; Le programme nucleaire francais

    Energy Technology Data Exchange (ETDEWEB)

    Cabanius, J [Electricite de France (EDF), 75 - Paris (France); Horowitz, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    -increasing importance, by using the country's resources of natural uranium, and later plutonium, to the best ends. (authors) [French] Les perspectives d'evolution de la consommation d'energie electrique francaise confirment l'aggravation du deficit des ressources energetiques metropolitaines. Les centrales nucleaires doivent permettre de diminuer ce deficit si un certain nombre d'incertitudes actuelles sont levees. Le premier programme presente par MM AILLERET et TARANGER a la Conference de Geneve en 1955 visait la mise en service pour 1965 de 850 MWe; il a ete consacre au developpement de la filiere uranium naturel - graphite - gaz et s'acheve avec la realisation d'EDF 3, premiere unite capable de 500 MWe engagee dans le monde. Avant de passer du stade des prototypes a celui des duplications, ELECTRICITE DE FRANCE a decide, en accord avec le COMMISSARIAT A L'ENERGIE ATOMIQUE, la realisation d'EDF 4 qui, en reprenant la partie reacteur d'EDF 3 ainsi que l'appareil de chargement et de dechargement, l'ensemble de controle et divers materiels, apporte une innovation importante en incorporant les echangeurs et les soufflantes a l'interieur du caisson en beton precontraint contenant le coeur. En meme temps, les etudes se poursuivent dans cette meme filiere et laissent entrevoir les possibilites d'utiliser un nouvel element combustible annulaire dont l'emploi ameliorerait notablement les performances d'EDF 5. Dans la filiere eau lourde, la realisation d'EL 4 a Brennilis par le COMMISSARIAT A L'ENERGIE ATOMIQUE et ELECTRICITE DE FRANCE se poursuit. Les etudes d'un reacteur de 500 MWe de cette filiere ont deja commence. Dans la filiere a eau pressurisee, la centrale de CHOOZ est realisee en association par ELECTRICITE DE FRANCE et les Producteurs Belges. Enfin, le COMMISSARIAT A L'ENERGIE ATOMIQUE poursuit a Cadarache la realisation du surgenerateur 'Rapsodie' et les etudes d'un reacteur de puissance plus important. Ainsi, les connaissances techniques et economiques acquises dans ces diverses

  20. Study of molybdenum (VI) complexation and precipitation by zirconium (IV) in strongly acid medium. Application to nuclear spent fuel dissolution; Etude de la complexation et de la precipitation du molybdene (VI) par le zirconium (IV) en milieu tres acide. Application a la dissolution du combustible nucleaire irradie

    Energy Technology Data Exchange (ETDEWEB)

    Esbelin, E

    1999-07-01

    These last years the formation of solid deposits has been observed in the dissolution workshops of the La Hague plant. A sample of the solid was withdrawn for expertise: molybdenum and zirconium are the two major components of the solid, identified as zirconium molybdate. This thesis consisted in the approach of the mechanisms in solution liable to induce precipitate formation. After a bibliographical overview on the chemistry of Mo(VI) in highly acidic solution, this system was studied by absorption spectrophotometry in perchloric medium. The implication of two major forms of Mo(VI) in a dimerization equilibrium was confirmed by this way and by {sup 95}Mo NMR. The principal parameters governing this equilibrium were identified. It is thus shown that the molybdenum dimerization reaction is exothermic. Disturbance of the Mo(VI) system in highly acidic solution by Zr(IV) was also studied. In a restricted experimental field, for which 'conventional' exploitation methodologies had to be adapted to the system, a main complex of stoichiometry 1:1 between Mo(VI) and Zr(IV) was found. The precipitation study of Mo(VI) by Zr(IV) under conditions close to those of the dissolution medium of nuclear spent fuel was undertaken. The main parameters which control precipitation kinetics were identified. The results obtained reveal that precipitation is controlled by a single macroscopic process and therefore can be described by a single equation. The solid obtained is composed of only one phase presenting a Mo:Zr non-stoichiometry when compared to the theoretical formula ZrMo{sub 2}O{sub 7}(OH){sub 2},2H{sub 2}O. At last, on the basis of the research results, a descriptive mechanism of the system is proposed in which intervenes a 1:1 intermediate complex, much more soluble than a probable 2:1 precipitation precursor. (author)

  1. Study of the impact of radionuclides discharges from nuclear industry in the northern Cotentin area on the oyster Crassostrea gigas: expression of cellular stress molecular markers; Etude de l'impact des radionucleides rejetes par les installations nucleaires du Nord Cotentin sur l'huitre creuse Crassostrea gigas: analyse de l'expression de marqueurs moleculaires de stress

    Energy Technology Data Exchange (ETDEWEB)

    Farcy, E

    2006-11-15

    This thesis explores the potential radiological impact of radionuclide discharges from the nuclear industry on the Pacific oyster, Crassostrea gigas. One of the major goals of this research was to identify markers that could be used to monitor the effects of low-level chronic irradiation. We decided to focalize on the expression of stress-induced genes involved in the regulation of cellular stress, focusing on transcription. First, homology cloning was used to identify four new cDNAs encoding stress markers. Then data collected at various sites enabled to evidence that mRNA levels for each of the genes of interest naturally vary to a significant degree, based on individual differences and seasonal factors. Comparing oysters from exposed sites with those from a reference site located on the Atlantic coast did not suggest any relationship between mRNA levels changes and the oysters exposure to liquid radioactive waste from the A.R.E.V.A. reprocessing plant. In the environment, we found that those radionuclide releases resulted in a very small increase in radioactivity in oysters, especially compared with their natural radioactivity. In the laboratory, by exposing the oysters to higher radionuclide concentrations than those found in the environment, we were able to identify two genes as potential candidates for studying the effects of chronic exposure to low doses of ionizing radiations in the oyster: genes encoding MT and MXR. We confirmed that transcriptional induction of these two genes occurs in response to high doses of acute irradiation. Finally, the comparison between environmental results and the laboratory results underlined the complementarity of these two approaches. In particular, it revealed that seasonal variations in mRNA levels probably have a significant effect on the stress response. (author)

  2. Gamow-Teller decay and nuclear deformation: implementing of a new total absorption spectrometer, study of isotopes N {approx_equal} Z krypton and strontium; Decroissance Gamow-Teller et deformation nucleaire: mise en oeuvre d'un nouveau spectrometre a absorption totale, etude d'isotopes N {approx_equal} Z de krypton et strontium

    Energy Technology Data Exchange (ETDEWEB)

    Poirier, E

    2002-12-01

    Nuclei with A {approx} 70 along the N=Z line are known to be the scene of phenomena closely related to the nuclear deformation and are of particular interest since theoretical mean field calculations predict that a large part of the Gamow-Teller resonance might be located below the ground state of the mother nucleus and then be accessible through {beta}-decay studies. These results have shown the effect of the shape of the ground state on the intensity of the Gamow-Teller strength. Thus, the experimental determination, through {delta}-decay, of the Gamow-Teller strength distribution and the comparison to the theoretical predictions allow to pin down the quadrupolar deformation parameter of the ground state of the parent nucleus. In order to study the neutron deficient isotopes of krypton (A=72,73,74,75) and strontium (A=76,77,78) and to establish the {beta}-strength on the full energy range, a new total absorption spectrometer (TAgS) has been built in the frame of an international collaboration and installed at the (SOLDE/CERN mass separator. For the data analysis, the response function R of the spectrometer has been calculated by means of Monte-Carlo simulations, based on the GEANT4 code, and of a statistical description of the level scheme in the daughter nucleus. The {beta}-feeding distribution has been obtained from experimental spectra through a method based on Bayes theorem and then converted into Gamow-Teller strength. The results coming from the {sup 74}Kr decay analysis allow to describe the ground state of such a nucleus as the coexistence of an oblate shape and of a prolate shape. In the case of {sup 76}Sr, the experimental Gamow-Teller strength distribution strongly indicates a prolate deformation. (author)

  3. Application of digital solutions to help the safe and efficient operation of nuclear power plants; Aplicacion de soluciones digitales para la ayuda a la operacion segura y eficiente de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ortega P, F.; Fernandez F, S., E-mail: fortega@tecnatom.es [Tecnatom S. A., Av. Montes de Oca 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

    2017-09-15

    In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

  4. A study of the conformation and stability of nitroxide free radicals; Etude de la conformation et de la stabilite de radicaux libres nitroxydes

    Energy Technology Data Exchange (ETDEWEB)

    Briere, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-03-01

    The first part of this study is an application of nuclear magnetic resonance to the determination of the sign and magnitude of the long range nuclear-electron spin-spin couplings in the free radical nitroxide derived from piperidine. It has been shown that the coupling constants of the protons {gamma} to the nitrogen atom have a pronounced spatial dependence as do the protons in the {beta} position, a point which has not been brought out by previous investigations. Conformational analysis of these compounds has been carried out by measurement of the effect of temperature on the NMR spectra at 310 MHz. The synthesis of di-t-Bu nitroxide labelled with C{sup 13} in the {alpha}-position made possible the unambiguous determination of the corresponding {sup 13}C nuclear-electron spin-spin coupling constant, a parameter which had not previously been measured. The coupling constants measured in the 2,2,6,6-tetramethyl piperidine series could then be attributed to the {sup 13}C atoms in the {beta}-position and their variation related to the conformations of the heterocycles. This constitutes the second part of the work reported here. The final section is devoted to a study of the decomposition of an unstable nitroxide having a hydrogen atom in the p-position. This decomposition is bimolecular and the primary isotope effect shows that the rupture. of the C-H bond is involved. From this one can conclude that a nitroxide is stable when the different groups attached to the nitrogen atom cannot give rise to a decomposition either intra molecularly, if the molecular geometry is suitable, or inter molecularly by dimerisation through attack on a different center of a neighbouring molecule thus leading to a fragmentation or a disproportionation. (author) [French] La premiere partie est une application de la resonance magnetique nucleaire a la determination du signe et de la grandeur des couplages a longue distance dans des radicaux libres nitroxydes piperidiniques. Il est montre que

  5. 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.)

  6. The mission of the central commission of the Czechoslovak Academy of Agriculture for use of energy resources and nuclear methods in agriculture

    International Nuclear Information System (INIS)

    Horacek, P.

    1979-01-01

    The possibility is discussed of using waste heat of nuclear power plants for the intensification of agricultural production. In France, protected agricultural areas are heated with warm water circulating in a polyethylene perforated blanket. Experiments with subirrigation using warm water or with heating using water circulating in subsurface piping yield good results. Heating water for fish husbandry appears prospective and a research project in this field is suggested. (H.S.)

  7. Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde; Implementacion del proyecto de confiabilidad de equipo en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rios O, J. E.; Martinez L, A. G. [CFE, Central Laguna Verde, Subgerencia General de Operacion, Veracruz (Mexico)]. e-mail: jrios@cfe.gob.mx

    2008-07-01

    A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

  8. Studies on solid-state physics carried out with the Saclay reactor (1962); Etudes de physique du solide realisees a la pile de Saclay (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Herpin, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    This paper deals only with solid-state physics experiments carried out on outgoing beams: rather than giving a general review of the work performed, if refers to only a few of the most important studies or those nearest completion. These are being made with the experimental beams of the two Saclay reactors EL-2, with a central flux of 10{sup 13} n/cm{sup 2}, and - since 1958 - EL-3, whose central flux is equal ta 10{sup 14} n/cm{sup 2}. The experiments are being carried out by two separate groups of physicists, employing different techniques, namely neutron diffraction using a crystal spectrometer, and inelastic scattering using a time-of-flight spectrometer. (author) [French] Cet expose ne relate que des experiences de physique du solide faites sur des faisceaux sortis; plutot que de donner une revue de l'ensemble des travaux effectues, on ne cite que quelques etudes que l'on peut considerer comme plus essentielles ou mieux achevees. On utilise les faisceaux experimentaux des deux piles de Saclay, EL-2 dont le flux au centre est de 10{sup 13}n/cm{sup 2} et, depuis 1958, EL-3 pour laquelle il est egal a 10{sup 14} n/cm{sup 2}. Les experiences sont realisees par deux groupes de physiciens distincts, employant des techniques differentes, la diffraction des neutrons qui utilise un spectrometre a cristal, et la diffusion inelastique avec un spectrometre a temps de vol. (auteur)

  9. Contribution to the study of time-resolution in pulse electronics for nuclear physics: phase control circuits; Contribution a l'etude de la resolution en temps de l'electronique impulsionnelle pour physique nucleaire: les circuits de mise en phase

    Energy Technology Data Exchange (ETDEWEB)

    Cortet, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    Phase control circuits make it possible to improve quite markedly the time resolution in pulse electronics. They replace a random pulse, of which the time of arrival with respect to a reference zero is being measured, by another pulse whose phase is well determined with respect to that, of a clock taken as reference. The time spectrum of the output, delayed, can always be situated inside channels of width {delta}T defined by the clock. The time statistics of the events analyzed is always correct even if the transition time for the circuits defining the channels represents a large fraction of {delta}T: the coding of the time becomes perfect, The phase control circuits, used in precision chronometry, are widely applied in Nuclear Physics since the lime spectra obtained are representative, indirectly, of certain values which are required to be measured with great accuracy. A description is given of: the constitution and operation of phase control circuits; a chain with automatic analysis and automatic reading, built for testing these circuits. Finally the measurement results are given. (author) [French] Les circuits de mise en phase permettent d'ameliorer notablement la resolution en temps de l'electronique impulsionnelle. Ils substituent a une impulsion aleatoire, dont on cherche a mesurer l'instant d'arrivee par rapport a un instant pris pour origine, une autre impulsion dont la phase est bien determinee par rapport a celle d'une horloge prise comme reference. Le spectre temporel de sortie, retarde, peut toujours etre situe a l'interieur des canaux de largeur {delta}T, definis par l'horloge. La statistique temporelle des evenements analyses est toujours correcte, meme si la duree de transition des circuits definissant les canaux represente une grande fraction de {delta}T: le codage de temps devient parfait. Les circuits de mise en phase, utilises en chronometrie fine, sont tres employes en Physique Nucleaire car les spectres temporels oblenus sont representatifs

  10. Use of 14 MeV neutrons in activation analysis. Experiments carried out at the Grenoble nuclear research Centre (1963); Utilisation de neutrons de 14 MeV en analyse par activation. Experience realisee au Centre d'etudes nucleaires de Grenoble (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Auboin, G; Guazzoni, P; Laverlochere, J [Commisariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1963-07-01

    The use of 14 MeV neutron irradiation makes it possible to extend the field of application of activation analysis to elements which cannot be activated in nuclear reactors (oxygen, boron, for example) or else to consider the possibility of 'portable' measurement units for routine analyses. With this aim, tests have been carried out for studying the sensitivity and interferences in the case of the dosing of oxygen in eleven different matrices using 150 and 300 kV SAMES accelerators producing 14 MeV neutrons by the reaction {sup 3}H (d, n) {sup 4}He. The sensitivity of the dosage methods for six writer elements has also been studied. The results obtained show that, for a neutron flux of 10{sup 10} n/4{pi}, the sensitivities vary from 100 {mu}g and 1 mg for oxygen in nine matrices (Be, Ta, Nb, Ti, Zr, Fe, Al, Sb, Si) and that it is possible to dose the six elements F, B, Y, Si, N, Al with sensitivities of between 1 an 1000 micrograms. (authors) [French] L'irradiation au moyen de neutrons de 14 MeV permet d'etendre le domaine d'application de l'analyse par activation a des elements non activables en reacteur nucleaire (oxygene, bore, par exemple) ou encore d'envisager des unites de dosage ''portables'' pour des analyses de routine. Dans ce but, des essais ont ete effectues pour etudier les sensibilites et les interferences dans le cas du dosage de l'oxygene dans onze matrices differentes, au moyen d'accelerateurs SAMES 150 et 300 kV. produisant les neutrons de 14 MeV par la reaction {sup 3}H (d, n) {sup 4}He. Des sensibilites de dosage ont egalement ete etudiees pour six autres elements. Les resultats obtenus montrent que, pour un flux de neutrons de 10{sup 10} n /4{pi}, les sensibilites varient entre 100 {mu}g et 1 mg, pour l'oxygene dans neuf matrices (Be, Ta, Nb, Ti, Zr, Fe, Al, Sb, Si) et qu'il est possible de doser les six elements F, B, Y, Si, N, Al avec des sensibilites se situant entre 1 et 1000 microgrammes. (auteurs)

  11. Study and modelling of the in-pile densification of the UO{sub 2} and MO{sub x} nuclear oxides; Etude et modelisation de la densification en pile des oxydes nucleaires UO{sub 2} et MO{sub x}

    Energy Technology Data Exchange (ETDEWEB)

    Boulore, A

    2001-03-01

    Amongst the many phenomena which take place in the course of the irradiation of UO{sub 2} or (U, Pu)O{sub 2} nuclear fuels, one of them involves the elimination of a fraction of the as-fabricated porosity. In-pile densification or sintering can reach 2.5%, i.e. approximately half the initial volume of pores is likely to disappear. Our literature survey indicates that the amplitude and kinetics of the phenomenon are both heavily dependent on the initial fuel microstructure. Micro-structural characterisation techniques of oxide fuels have therefore been developed in conjunction with quantitative image analysis methods. The ensuing methodology enables a quantitative comparison of micro-structural features in different fuels and has been applied to ascertaining the influence of the local fission rate and temperature on in-pile densification. It is thus revealed that in-pile operation eliminates a significant fraction of pores smaller than 3 microns in diameter. The experimental data generated has been used to set up a semi-empirical and a mechanistic model. The former is based on experimental results and is not essentially predictive. The inability of this model to predict the in-pile densification of oxide fuels is illustrated by the fact that the maximum fraction of pores that disappears is proportional to an empirical function of fission rate, and temperature. The proportionality factor appears to be difficult to correlate quantitatively to any given micro-structural feature. The model has however been applied to the interpretation of an in-pile densification experiment carried out in the Halden reactor (Norway). The latter model is mechanistic, i.e. it is based on the solution to a set of equations that describe the coupled temperature and radiation induced phenomena which occur in-pile. These can broadly be broken down into three categories: the fission fragment-pore interaction, the creation of point defects as the fission fragments slow down, and the diffusion

  12. 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.

  13. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  15. Near-infrared variability study of the central 2.3 × 2.3 arcmin2 of the Galactic Centre - II. Identification of RR Lyrae stars in the Milky Way nuclear star cluster

    Science.gov (United States)

    Dong, Hui; Schödel, Rainer; Williams, Benjamin F.; Nogueras-Lara, Francisco; Gallego-Cano, Eulalia; Gallego-Calvente, Teresa; Wang, Q. Daniel; Rich, R. Michael; Morris, Mark R.; Do, Tuan; Ghez, Andrea

    2017-11-01

    Because of strong and spatially highly variable interstellar extinction and extreme source crowding, the faint (K ≥ 15) stellar population in the Milky Way's nuclear star cluster is still poorly studied. RR Lyrae stars provide us with a tool to estimate the mass of the oldest, relative dim stellar population. Recently, we analysed HST/WFC3/IR observations of the central 2.3 × 2.3 arcmin2 of the Milky Way and found 21 variable stars with periods between 0.2 and 1 d. Here, we present a further comprehensive analysis of these stars. The period-luminosity relationship of RR Lyrae is used to derive their extinctions and distances. Using multiple approaches, we classify our sample as 4 RRc stars, 4 RRab stars, 3 RRab candidates and 10 binaries. Especially, the four RRab stars show sawtooth light curves and fall exactly on to the Oosterhoff I division in the Bailey diagram. Compared to the RRab stars reported by Minniti et al., our new RRab stars have higher extinction (AK > 1.8) and should be closer to the Galactic Centre. The extinction and distance of one RRab stars match those for the Milky Way's nuclear star cluster given in previous works. We perform simulations and find that after correcting for incompleteness, there could be not more than 40 RRab stars within the Milky Way's nuclear star cluster and in our field of view. Through comparing with the known globular clusters of the Milky Way, we estimate that if there exists an old, metal-poor (-1.5 < [Fe/H] < -1) stellar population in the Milky Way nuclear star cluster on a scale of 5 × 5 pc, then it contributes at most 4.7 × 105 M⊙, I.e. ˜18 per cent of the stellar mass.

  16. Balance between automation and human actions in nuclear power plant operation. Results of international cooperation; Equilibre entre automatisation et action humaine dans la conduite des centrale nucleaires, resultats de la cooperation internationale

    Energy Technology Data Exchange (ETDEWEB)

    Sun, B [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d' Analyse de Surete; Bastl, W [Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany); Olmstead, R [Atomic Energy of Canada Ltd, Mississauga (Canada); Oudiz, A [Electric Power Research Inst., Palo Alto, CA (United States); Jenkinson, J [Nuclear Electric PLC, Gloucester (United Kingdom); Kossilov, A [International Atomic Energy Agency, Vienna (Austria)

    1990-07-01

    Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation. (author) [French] L'automatisation a longtemps ete une caracteristique bien etablie des centrales nucleaires. Dans certaines applications, l'utilisation de l'automatisation a ete le facteur decisif qui a permis a la technologie des centrales de progresser jusqu'a son etat actuel. Les exigences de l'opinion publique en matiere de securite renforcee ont conduit a l'utilisation d'une plus grande redondance et a une plus grande diversification et ceci, en retour, a encore accru le niveau d'automatisation. Toutefois, il est possible que le facteur preponderant de cet accroissement de l'automatisation soit constitue par les progres effectues dans la technologie de l'information. Plus recemment, l'attention s

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-02-15

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

  18. Study of the {sup 60}Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel; Etude de la speciation du {sup 60}Co dans les effluents de l'usine de retraitement de combustibles irradies de la Hague; devenir apres rejet dans les eaux de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    Gaudaire, J.M

    1999-07-01

    {sup 60}Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 {mu}m) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l{sup -1}. The {sup 60}Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 {mu}m), and then in the form of two soluble species: ionic divalent (Co{sup 2+}) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total {sup 60}Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg{sup 2+} and Ca{sup 2+}) go through a precipitation. This comes with the coprecipitation of the ion Co{sup 2+} and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non

  19. Study of the {sup 60}Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel; Etude de la speciation du {sup 60}Co dans les effluents de l'usine de retraitement de combustibles irradies de la Hague; devenir apres rejet dans les eaux de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    Gaudaire, J M

    1999-07-01

    {sup 60}Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 {mu}m) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l{sup -1}. The {sup 60}Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 {mu}m), and then in the form of two soluble species: ionic divalent (Co{sup 2+}) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total {sup 60}Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg{sup 2+} and Ca{sup 2+}) go through a precipitation. This comes with the coprecipitation of the ion Co{sup 2+} and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non

  20. Introduction of fuel GE14 in the nuclear power plant of Laguna Verde for the extended increase of power; Introduccion del combustible GE14 en la central nuclear Laguna Verde para el aumento de potencia extendido

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A. F.; Cardenas J, J. B.; Contreras C, P. [CFE, Central Nuclear Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5 (Mexico)]. e-mail: natividad.hernandez@cfe.gob.mx

    2008-07-01

    The project of extended increase of power responds to a necessity of electrical energy in the country, increasing the thermal exit of the reactors of the nuclear power plant of Laguna Verde of 2027 MWt to 2317 MWt. In order to support this transition, changes will make in the configuration of the reactor core and in the operation strategies of the cycle, also they will take initiatives to optimize the economy in fuel cycle. At present in both reactors of the nuclear plant of Laguna Verde fuel GE12 is used. The fuel GE14 presents displays with respect to the GE12, some improvements in the mechanical design and consequently in its performance generally. Between these improvements we can mention: 1. Spacers of high performance. 2. Shielding with barrier. 3. Filter for sweepings {sup d}ebris{sup a}nd 4. Fuel rods of minor partial length. The management of nuclear power plants has decided to introduce the use of fuel GE14 in Laguna Verde in the reload 14 for Unit 1 and of the reload 10 for Unit 2. The process of new introduction fuel GE14 consists of two stages, first consists on subjecting the one new design of fuel to the regulator organism in the USA: Nuclear Regulatory Commission, in Mexico the design must be analyzed and authorized by the National Commission of Nuclear Safety and Safeguards, for its approval of generic form, by means of the demonstration of the fulfillment with the amendment 22 of GESTAR II, the second stage includes the specific analyses of plant to justify the use of the new fuel design in a reload core. The nuclear plant of Laguna Verde would use some of the results of the security analyses that have been realized for the project of extended increase of power with fuel GE14, to document the specific analyses of plant with the new fuel design. The result of the analyses indicates that the reload lots are increased of 116-120 assemblies in present conditions (2027 MWt) to 140-148 assemblies in conditions of extended increase of power (2317 MWt

  1. Training sessions for radiation protection. A singular occasion to analyze the risk perception by nuclear workers

    International Nuclear Information System (INIS)

    Escudie, M.

    1986-04-01

    The training sessions for radiation protection - given on the one hand to employees of the decontamination and storage action section, of the nuclear center of Saclay, and on the other hand to technicians of low and medium activity laboratories - represent a goog ground to test hypotheses mentioned at the origin of the analysis of the perception of risk by the nuclear workers undertaken by the Laboratoire d'Etude du Facteur Humain (L.E.F.H., Human Factor Analysis Laboratory) of the Commissariat a l'Energie Atomique (CEA, Atomic Energy Commission of France)

  2. Recommended practice for the design of a computer driven Alarm Display Facility for central control rooms of nuclear power generating stations

    International Nuclear Information System (INIS)

    Ben-Yaacov, G.

    1984-01-01

    This paper's objective is to explain the process by which design can prevent human errors in nuclear plant operation. Human factor engineering principles, data, and methods used in the design of computer driven alarm display facilities are discussed. A ''generic'', advanced Alarm Display Facility is described. It considers operator capabilities and limitations in decision-making processes, response dynamics, and human memory limitations. Highlighted are considerations of human factor criteria in the designing and layout of alarm displays. Alarm data sources are described, and their use within the Alarm Display Facility are illustrated

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

    International Nuclear Information System (INIS)

    Orsag, V.

    1989-01-01

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

  4. Nuclear energy

    International Nuclear Information System (INIS)

    Rippon, S.

    1984-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

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

  7. 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.)

  8. 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)

  9. 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)

  10. Quality Assurance in the Vandellos 1 Nuclear Power Plant Dismantling and Decommissioning Project; La garantia de calidad en el proyecto de desmantelamiento y clausura de la Central Nuclear de Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Soto Lanuza, A

    2000-07-01

    General description of the Quality Assurance System established and implemented for the efficient development of the current activities specified in the Dismantling and Decommissioning Plan for Vandellos I Nuclear Power Plant. Aspects related to the Quality organization, scope and applicability on the established Quality Assurance Manual, availability of requirements and recommendations on quality as well as actions to be taken for the correct verification on the quality and practical application of the Manual should be described. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

  13. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    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.

  14. 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)

    1994-12-01

    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

  15. New recommendations of the ICRP and the ALARA program of the Nuclear power plant of Laguna Verde; Nuevas recomendaciones del ICRP y el programa ALARA de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Padilla C, I [Comision Federal de Electricidad, Central Laguna Verde (Mexico)

    1991-07-01

    In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program.

  16. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

    Atucha I nuclear power plant moderator system operates with highly radioactive heavy water, a pressure of 115 Bar and temperatures of about 200 C degrees. In March 2000, an increasing leakage of heavy water to the conventional thermal circuit was detected, conducting the plant to a shut down. The development of a number of actions and measures were taken, in order to plug this leakage. The leakage was found in a heat exchanger, which is located in a place of difficult access, with a high radiological yield and which, according to design, it was not considered to be mechanically repaired. It is a U bend tubes heat exchanger, weighting about 20 tons, and with a heavy water flow of 800 tons/h on the primary circuit, and 950 tons/h of ordinary water on the secondary side. Foreseeing this event, it had been designed and constructed special equipment and procedures, by means of a contract, with the Company INVAP SA. Repair works were carried out within a period of eighty-six (86) days, from which, forty five days were used to repair the component itself. A considerable amount of time was used to prepare simulators and the training of personnel. Due to the high radiological yield and the strict care of radiological standards, it was necessary the participation of 300 persons, integrating a collective dose of 4,86 Sv-m. It was necessary the construction of platforms and auxiliary stairs so as to make the work place accessible, as well as lifting and movement devices for heavy components, since this area does not have such kind of facilities. Welding and cutting machines remote controlled as well as manipulators which operated in front of the exchanger tube sheet were used. The aim was the reduction of dose values as much as possible. Special shielding were developed and in some cases it was necessary the adoption of drastic measures such as the cutting of bolts or pipes. The failure was detected and the tube was plugged. Also were plugged those tubes with wall thickness

  18. Study of semi-conductor spectrometers for high counting rates. Application to the study of the reaction {sup 31}P (p, {alpha}{sub 0}): E{sub p} < 2 MeV; Etude de spectrometres a semi-conducteurs pour forts taux de comptage application a l'etude de la reaction {sup 31}P (p, {alpha}0): E{sub p} < 2 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Ligeon, E [Commissariat a l' Energie Atomique, 38 - Grenoble (France). Centre d' Etudes Nucleaires

    1967-10-01

    The study of nuclear reactions involving particles of low charge (E < 2 MeV) calls for spectrometers of high resolving power. In many experiments however, the counting rate is high because of Coulomb scattering at the target: this results in a distortion of the experimental spectra and a loss of resolving power in the detection equipment. The first part of the work is devoted to an evaluation of the resolving power obtained with silicon-detector spectrometers. A study of the elastic scattering of protons by {sup 31}P shows which are the factors limiting the resolving power. In the second part we examine the various types of spectrometer which can be used in the case of a high count-rate. We have built an apparatus which can be used for carrying out spectrometry on particles produced by nuclear reactions, for a total, count-rate of 10{sup 5} counts/sec. (author) [French] L'etude des reactions nucleaires avec particules chargees a basse energie (E < 2 MeV) exige des spectrometres de haute resolution. Cependant, dans de nombreuses experiences le taux de comptage est eleve, par suite de la diffusion coulombienne sur la cible; on observe alors une distorsion des spectres experimentaux et une perte de resolution de l'ensemble de detection. La premiere partie de ce travail est consacree a l'evaluation de la resolution obtenue avec des spectrometres utilisant des detecteurs au silicium. L'etude de la diffusion elastique des protons sur le {sup 31}P montre quels sont les facteurs qui limitent la resolution. Dans une deuxieme partie, nous etudions les differents types de spectrometres que l'on peut utiliser dans le cas d'un taux de comptage eleve. Nous avons construit un appareil qui permet de faire la spectrometrie de particules, provenant de reactions nucleaires, pour un taux de comptage total de 10{sup 5} c/s. (auteur)

  19. Study of semi-conductor spectrometers for high counting rates. Application to the study of the reaction {sup 31}P (p, {alpha}{sub 0}): E{sub p} < 2 MeV; Etude de spectrometres a semi-conducteurs pour forts taux de comptage application a l'etude de la reaction {sup 31}P (p, {alpha}0): E{sub p} < 2 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Ligeon, E. [Commissariat a l' Energie Atomique, 38 - Grenoble (France). Centre d' Etudes Nucleaires

    1967-10-01

    The study of nuclear reactions involving particles of low charge (E < 2 MeV) calls for spectrometers of high resolving power. In many experiments however, the counting rate is high because of Coulomb scattering at the target: this results in a distortion of the experimental spectra and a loss of resolving power in the detection equipment. The first part of the work is devoted to an evaluation of the resolving power obtained with silicon-detector spectrometers. A study of the elastic scattering of protons by {sup 31}P shows which are the factors limiting the resolving power. In the second part we examine the various types of spectrometer which can be used in the case of a high count-rate. We have built an apparatus which can be used for carrying out spectrometry on particles produced by nuclear reactions, for a total, count-rate of 10{sup 5} counts/sec. (author) [French] L'etude des reactions nucleaires avec particules chargees a basse energie (E < 2 MeV) exige des spectrometres de haute resolution. Cependant, dans de nombreuses experiences le taux de comptage est eleve, par suite de la diffusion coulombienne sur la cible; on observe alors une distorsion des spectres experimentaux et une perte de resolution de l'ensemble de detection. La premiere partie de ce travail est consacree a l'evaluation de la resolution obtenue avec des spectrometres utilisant des detecteurs au silicium. L'etude de la diffusion elastique des protons sur le {sup 31}P montre quels sont les facteurs qui limitent la resolution. Dans une deuxieme partie, nous etudions les differents types de spectrometres que l'on peut utiliser dans le cas d'un taux de comptage eleve. Nous avons construit un appareil qui permet de faire la spectrometrie de particules, provenant de reactions nucleaires, pour un taux de comptage total de 10{sup 5} c/s. (auteur)

  20. On the protection and operation of nuclear power plants and great structures in Central Europe with respect to the tectonics of European Alps

    International Nuclear Information System (INIS)

    Nedoma, J.

    1991-01-01

    The aim of the study is to show that the financial resources needed for exploitation of the energetical resources as well as for the security of great energetical structures (i.e. nuclear power plants (NPP), deep mines, great waterdams, etc.), can be employed with high efficiency only when using appropriate basic and applied geological and geophysical investigations. One can only by this way save money expended during the last years to great structures built in critical regions. The breakdown of the Chernobyl NPP and the catastrophic earthquake in Armenia as well as the construction of a NPP there, situated on the Ararat deep fault, in a relatively small distance from the earthquake region, warn us and cons