WorldWideScience

Sample records for secondaires apres traitement

  1. Traitements didactiques preventifs d'un type de conceptions erronees en sciences physiques chez des eleves du secondaire

    Science.gov (United States)

    Blondin, Andre

    hypotheses avec la cohorte suivante d'eleves chez qui se repetaient les memes conditions d'apprentissage. Nous avons utilise le design de recherche "posttest only" de Campbell et Stanley. En mai, apres le moment prevu dans la planification du programme pour donner le probleme aux eleves, nous avons suggere deux facons differentes de reviser la solution de ce probleme. Les eleves du premier groupe experimental ont revise sans que soit activee la connaissance anterieure apprehendee de la rotation de la Terre. Les eleves du deuxieme groupe experimental ont ete confrontes, par des questions et une simulation, au fait que la rotation de la Terre n'est pas une connaissance pertinente pour resoudre le probleme. Les groupes temoins et les groupes experimentaux ont ete choisis au hasard dans le bassin des ecoles secondaires de la commission scolaire. (Abstract shortened by UMI.)

  2. Suivi après le traitement du cancer du sein

    Science.gov (United States)

    Sisler, Jeffrey; Chaput, Geneviève; Sussman, Jonathan; Ozokwelu, Emmanuel

    2016-01-01

    Résumé Objectif Offrir aux médecins de famille un résumé des recommandations fondées sur les données probantes pour guider les soins aux survivantes traitées pour le cancer du sein. Qualité des données Une recherche documentaire a été effectuée dans MEDLINE entre 2000 et 2016 à l’aide des mots-clés anglais suivants : breast cancer, survivorship, follow-up care, aftercare, guidelines et survivorship care plans, en se concentrant sur la revue des lignes directrices publiées récemment par les organismes nationaux de cancérologie. Les données étaient de niveaux I à III. Message principal Les soins aux survivantes comportent 4 facettes : surveillance et dépistage, prise en charge des effets à long terme, promotion de la santé et coordination des soins. La surveillance des récidives ne se traduit que par une mammographie annuelle, et le dépistage d’autres cancers doit suivre les lignes directrices basées sur la population. La prise en charge des effets à long terme du cancer et de son traitement aborde des problèmes courants tels la douleur, la fatigue, le lymphœdème, la détresse et les effets indésirables des médicaments, de même que les préoccupations à long terme comme la santé du cœur et des os. La promotion de la santé met en relief les bienfaits de l’activité chez les survivantes du cancer, avec l’accent mis sur l’activité physique. Les soins aux survivantes sont de meilleure qualité lorsque divers services et professionnels de la santé participent aux soins, et le médecin de famille joue un rôle important dans la coordination des soins. Conclusion Les médecins de famille sont de plus en plus souvent les principaux fournisseurs de soins de suivi après le traitement du cancer du sein. Le cancer du sein doit être considéré comme une affection médicale chronique, même chez les femmes en rémission, et les patientes profitent de la même approche que celle utilisée pour les autres affections chroniques en

  3. Les fractures pathologiques secondaires des tumeurs bénignes ...

    African Journals Online (AJOL)

    Les fractures pathologiques secondaires des tumeurs bénignes chez l'enfant: à propos de 20 cas. ... La prise en charge de ces fractures dépend surtout de la tumeur causale et des caractéristiques de la fracture. Le rôle de la radiologie est incontournable et let traitement doit se faire selon une méthodologie précise.

  4. Effets des electrons secondaires sur l'ADN

    Science.gov (United States)

    Boudaiffa, Badia

    Les interactions des electrons de basse energie (EBE) representent un element important en sciences des radiations, particulierement, les sequences se produisant immediatement apres l'interaction de la radiation ionisante avec le milieu biologique. Il est bien connu que lorsque ces radiations deposent leur energie dans la cellule, elles produisent un grand nombre d'electrons secondaires (4 x 104/MeV), qui sont crees le long de la trace avec des energies cinetiques initiales bien inferieures a 20 eV. Cependant, il n'y a jamais eu de mesures directes demontrant l'interaction de ces electrons de tres basse energie avec l'ADN, du principalement aux difficultes experimentales imposees par la complexite du milieu biologique. Dans notre laboratoire, les dernieres annees ont ete consacrees a l'etude des phenomenes fondamentaux induits par impact des EBE sur differentes molecules simples (e.g., N2, CO, O2, H2O, NO, C2H 4, C6H6, C2H12) et quelques molecules complexes dans leur phase solide. D'autres travaux effectues recemment sur des bases de l'ADN et des oligonucleotides ont montre que les EBE produisent des bris moleculaires sur les biomolecules. Ces travaux nous ont permis d'elaborer des techniques pour mettre en evidence et comprendre les interactions fondamentales des EBE avec des molecules d'interet biologique, afin d'atteindre notre objectif majeur d'etudier l'effet direct de ces particules sur la molecule d'ADN. Les techniques de sciences des surfaces developpees et utilisees dans les etudes precitees peuvent etre etendues et combinees avec des methodes classiques de biologie pour etudier les dommages de l'ADN induits par l'impact des EBE. Nos experiences ont montre l'efficacite des electrons de 3--20 eV a induire des coupures simple et double brins dans l'ADN. Pour des energies inferieures a 15 eV, ces coupures sont induites par la localisation temporaire d'un electron sur une unite moleculaire de l'ADN, ce qui engendre la formation d'un ion negatif transitoire

  5. Valorisation par voie hydrométallurgique de Matières Premières Secondaires Valorization of Secondary Raw Materials by hydrometallurgical way

    Directory of Open Access Journals (Sweden)

    Meux Eric

    2013-11-01

    Full Text Available Cet exposé s'intéressera à la récupération par voie hydrométallurgique de métaux contenus dans les Matières Premières Secondaires. Dans un premier temps seront abordées des généralités sur les Métaux Critiques, leur taux de recyclage et les gisements identifiés. Deux exemples de traitement seront ensuite développés : le traitement de catalyseurs d'hydrotraitement et le traitement de poudres métallifères issues de broyats d'accumulateurs par couplage électrolixiviation/électrodéposition. This talk will focus on the hydrometallurgical recovery of metals contained in secondary raw materials. At first, generalities about critical metals, their recycling rate and their identified supply will be addressed. Two examples of hydrometallurgical treatment will be then developed: the treatment of spent hydrotreating catalysts and the treatment of electrodes powders coming from grinding of spent batteries by coupling electroleaching/electrodeposition.

  6. Compression medullaire lente secondaire a un lymphome de Burkitt ...

    African Journals Online (AJOL)

    faciale à la fin du 1er mois et une récupération neurologique au bout d'un an. La localisation secondaire intra rachidienne d'un LB bien que rare doit être présente à l'esprit surtout en face d'une compression médullaire lente survenue dans un ...

  7. Resultat du traitement d'un craniopharyngiome kystique par de la ...

    African Journals Online (AJOL)

    Introduction Le craniopharyngiome est une tumeur bénigne qui provient de nids épithéliaux ou de zones de métaplasies squameuses liées à l'embryogenèse hypophysaire. Touchant surtout l'enfant, peut être potentiellement agressive et caractérisée par un taux élevé de récidive après traitement chirurgical. La bléomycine ...

  8. Antenna Pattern Range (APR)

    Data.gov (United States)

    Federal Laboratory Consortium — TheAntenna Pattern Range (APR)features a non-metallic arch with a trolley to move the transmit antenna from the horizon to zenith. At the center of the ground plane,...

  9. Processus de traitement de l'air t.1

    CERN Document Server

    Edipa

    2009-01-01

    Edition entièrement revue et actualisée du tome 1 de « L'intégrale de la Clim », consacré aux processus de traitement de l'air. Cet ouvrage qui comprend 224 pages (au lieu de 166 lors de la précédente édition), aborde d'une façon très pratique toutes les techniques mises en oeuvre pour traiter les caractéristiques physiques de l'air en fonction de la qualité de l'ambiance recherchée : habitat, locaux tertiaires, locaux industriels, salles propres, salles de spectacles, piscines, etc. Dans un premier temps sont présentées les propriétés physiques de l'air humide et l'ensemble de ses caractéristiques. Après avoir analysé les fonctions que l'on souhaite réaliser, le système aéraulique est choisi et les différents débits d'air sont calculés. Chaque traitement élémentaire (chauffage, refroidissement, humidification, déshumidification, filtration, atténuation acoustique, récupération de chaleur, etc.) est ensuite étudié. Les procédés de régulation sont aussi examinés. Un nouve...

  10. Complications du traitement traditionnel des fractures : aspects ...

    African Journals Online (AJOL)

    Tous les patients reçus avec des complications du traitement traditionnel des fractures ont été inclus dans ce travail. Le diagnostic des lésions était clinique et radiologique. Nous avions reçu 51 patients porteurs de complications suite à des traitements de médecine traditionnelle, soit 13,7% du total des patients hospitalisés ...

  11. Detection of fission fragments by secondary emission; Detection des fragments de fission par emission secondaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    This fission fragment detecting apparatus is based on the principle that fragments traversing a thin foil will cause emission of secondary electrons. These electrons are then accelerated (10 kV) and directly detected by means of a plastic scintillator and associated photomultiplier. Some of the advantages of such a detector are, its rapidity, its discriminating power between alpha particles and fission fragments, its small energy loss in detecting the fragments and the relatively great amount of fissionable material which it can contain. This paper is subdivided as follows: a) theoretical considerations b) constructional details of apparatus and some experimental details and c) a study of the secondary emission effect itself. (author) [French] Le detecteur de fragments de fission que nous avons realise est base sur le principe de l'emission secondaire produite par les fragments de fission traversant une feuille mince: les electrons secondaires emis sont acceleres a des tensions telles (de l'ordre de 10 kV), qu'ils soient directement detectables par un scintillateur plastique associe a un photomultiplicateur. L'interet d'un tel detecteur reside: dans sa rapidite, sa tres bonne discrimination alpha, fission, la possibilite de detecter les fragments de fission avec une perte d'energie pouvant rester relativement faible, et la possibilite d'introduire des quantites de matiere fissile plus importantes que dans les autres types de detecteurs. Ce travail comporte: -) un apercu bibliographique de la theorie du phenomene, -) realisation et mise au point du detecteur avec etude experimentale de quelques parametres intervenant dans l'emission secondaire, -) etude de l'emission secondaire (sur la face d'emergence des fragments de fission) en fonction de l'energie du fragment et en fonction de l'epaisseur de matiere traversee avant emission secondaire, et -) une etude comparative de l'emission secondaire sur la face d'incidence et sur la face d'emergence des fragments de

  12. Respirators: APR Issuer Self Study 33461

    Energy Technology Data Exchange (ETDEWEB)

    Chochoms, Michael [Los Alamos National Laboratory

    2016-07-13

    Respirators: APR Issuer Self-Study (course 33461) is designed to introduce and familiarize employees selected as air-purifying respirator (APR) issuers at Los Alamos National Laboratory (LANL) with the responsibilities, limitations, procedures, and resources for issuing APRs at LANL. The goal is to enable these issuers to consistently provide proper, functioning APRs to authorized users

  13. Programming list processes. SLIP: symmetric list processor - applications; Le traitement de listes en programmation. SLIP: langage de listes symetrique - applications

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-06-01

    Modern aspects of programming languages are essentially turned towards list processing. The ordinary methods of sequential treatment become inadequate and we must substitute list processes for them, where the cells of a group have no neighbourhood connection, but where the address of one cell is contained in the preceding one. These methods are required in 'time sharing' solving problems. They also allow us to treat new problems and to solve others in the shortest time. Many examples are presented after an abstract of the most usual list languages and a detailed study of one of them : SLIP. Among these examples one should note: locating of words in a dictionary or in a card index, treatment of non numerical symbols, formal derivation. The problems are treated in Fortran II on an IBM 7094 machine. The subroutines which make up the language are presented in an appendix. (author) [French] La programmation moderne ne se satisfait plus des methodes classiques de traitement sequentiel ni des tableaux a positions de memoire contigues. Elle tend a generaliser les methodes de listes ou les cellules d'un groupe n'ont pas de relation de voisinage, mais sont enchainees en listes, l'une donnant l'adresse machine de l'autre. Ces methodes sont indispensables en 'partage de temps' et dans les traitements en 'temps reel'. De plus, elles permettent de traiter des problemes nouveaux et d'optimiser le temps de traitement de nombreux autres. De nombreux exemples sont traites, apres un resume des langages les plus utilises et une etude plus precise d'un langage de listes: SLIP. Parmi les exemples traites signalons la recherche lexicographique, le traitement de symboles alphanumeriques, la derivation formelle. Probleme traite en Fortran II sur IBM 7094. Les sous-programmes constitutifs du langage sont fournis en annexe. (auteur)

  14. Diagnostic Strategy in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dongyoung; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-05-15

    These features may bring out changes in operator tasks, changing the characteristics of tasks, or creating new tasks. Diagnostic strategy for identifying anomaly may be different especially in APR1400 from that in the analog control room due to the change of human-system interface, i.e. alarm system and display system. Since the first plant of APR1400 is being built at this moment, it is not known what strategies the operators will adopt in diagnosis tasks in the new operating environment. In this light, this paper aims at investigating operator's diagnostic strategies which are appropriate for APR1400. In order to collect data, several different approaches which are complementary are used to identify diagnostic strategies in the digital control room: analysis on audio/video recording of operation, observation in the simulator, and interview with the operators. The result shows that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of strategies, mostly, by getting more support from the computerized system. This paper investigated how the digitalized control room may influence operator's diagnostic strategies. Several different approaches, i. e., audio/video record, observation of training, and the interview with operators, were used to gather information about the operator's behaviors. As a conclusion, this paper figured out that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of the strategies, mostly, by getting more support from the computerized system. The operators interviewed also commented that the diagnosis in the APR1400 is quicker, more correct, and easier, compared with the analog control room.

  15. Diagnostic Strategy in APR1400

    International Nuclear Information System (INIS)

    Kim, Dongyoung; Kim, Jonghyun

    2013-01-01

    These features may bring out changes in operator tasks, changing the characteristics of tasks, or creating new tasks. Diagnostic strategy for identifying anomaly may be different especially in APR1400 from that in the analog control room due to the change of human-system interface, i.e. alarm system and display system. Since the first plant of APR1400 is being built at this moment, it is not known what strategies the operators will adopt in diagnosis tasks in the new operating environment. In this light, this paper aims at investigating operator's diagnostic strategies which are appropriate for APR1400. In order to collect data, several different approaches which are complementary are used to identify diagnostic strategies in the digital control room: analysis on audio/video recording of operation, observation in the simulator, and interview with the operators. The result shows that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of strategies, mostly, by getting more support from the computerized system. This paper investigated how the digitalized control room may influence operator's diagnostic strategies. Several different approaches, i. e., audio/video record, observation of training, and the interview with operators, were used to gather information about the operator's behaviors. As a conclusion, this paper figured out that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of the strategies, mostly, by getting more support from the computerized system. The operators interviewed also commented that the diagnosis in the APR1400 is quicker, more correct, and easier, compared with the analog control room

  16. LE TRAITEMENT DE LA STENOSE URETERALE D'ORIGINE ...

    African Journals Online (AJOL)

    Conclusion L'endoprothèse JJ associant un traitement antituberculeux est proposée comme une alternative à la chirurgie classique. Un traitement corticoïde s'il est accordé précocement peut aider sans doute à une réduction de la sténose. Treatment of Ureteral Stricture due to Tuberculosis by a ";Double J"; Catheter

  17. Radioactive Waste Facilities at the Australian Atomic Energy Commission Research Establishment; Installations pour le Traitement des Dechets Radioactifs au Centre de Recherche de la Commission Australienne a l'Energie Atomique; 0423 0421 0422 0414 ; Dispositivos para Evacuacion de Desechos Radiactivos en el Centro de Investigaciones de la Australian Atomic Energy Commission

    Energy Technology Data Exchange (ETDEWEB)

    Berglin, C. L.W.; Keher, L. H.; Miles, G. L.; Wilson, A. R.W. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, Sydney, NSW (Australia)

    1960-07-01

    'impuretes fertiles (appliquant un procede calcium-fer-phosphate) et de bassins de retenue. Le memoire examine les diverses methodes de concentration des impuretes et de traitement secondaire qui sont actuellement a l'etude. Les auteurs etudient la formule d'evacuation et la dilution probable dans le Woronora, et decrivent un essai de dilution qui a ete effectue dans les eaux touchees par la maree. On se propose d'enfouir, le cas echeant apres empaquetage, tous les dechets solidesi de faible activite. Les auteurs etudient le choix et l'emplacement de la zone d'elimination. Ils font un expose sur la construction d'une installation destinee au stockage et a l'elimination de dechets solides a activite elevee. On envisage l'e vaporation et le stockage des dechets liquides a activite moyenne et elevee. Le memoire donne des renseignements detailles sur les depenses d'equipement et d'exploitation afferentes a l'usine de traitement des effluents et a d'autres installations pour le traitement des dechets. (author) [Spanish] La memoria describe las instalaciones previstas para la recogida, tratamiento y evacuacion de los desechos radiactivos en Lucas Heights, en relacion con las cantidades que se produciran segun los calculos. Los efluentes de baja actividad se dividen en tres tipos: a) Aguas de las cloacas, b) Desechos de funcionamiento, provenientes de la torre de refrigeracion del reactor, de los talleres mecanicos y otras zonas no activas, c) Efluentes de los laboratorios y otras zonas activas. La planta de tratamiento para los efluentes del ultimo tipo consiste en principio en tanques de mezcla y dosificacion de alcali, un clarificador de lodos (que emplea un sistema a base de calcio - herro - fosfato) y tanques receptores. Se estan estudiando metodos para concentrar los lodos y metodos de tratamiento secundario, que se discuten en la memoria. La memoria estudia la forma de descarga y el grado de dilucion que se espera obtener en el rio Woronora, asi como un experimento de dilucion que se

  18. Design Characteristics of Soft Control for APR+

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yongsoo; Sung, Chanho; Jung, Yeonsub [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    In the global nuclear industry, the design requirements have been largely divided into the US and the European ones. The APR+ design, based on the proven APR1400 design, was developed to fully comply with the US regulatory and utility requirements. It was also developed to improve the technical competitiveness and enlarge the export market share through design uniqueness and the improvement of safety. The robust design of safety and its validation were requested Post-Fukushima accident. So MMIS design and validation for reinforcing safety were accomplished in APR+ development project. In this paper, the design characteristics of soft control for APR+ are presented to enhance the safety of MMIS design. In this paper, the major design characteristics of soft control for APR+ were introduced to increase the safety of MMIS design. In addition to the design characteristics of soft control described above, the following should be investigated closely for APR+ to get into the global nuclear industry.

  19. Design Characteristics of Soft Control for APR+

    International Nuclear Information System (INIS)

    Kim, Yongsoo; Sung, Chanho; Jung, Yeonsub

    2016-01-01

    In the global nuclear industry, the design requirements have been largely divided into the US and the European ones. The APR+ design, based on the proven APR1400 design, was developed to fully comply with the US regulatory and utility requirements. It was also developed to improve the technical competitiveness and enlarge the export market share through design uniqueness and the improvement of safety. The robust design of safety and its validation were requested Post-Fukushima accident. So MMIS design and validation for reinforcing safety were accomplished in APR+ development project. In this paper, the design characteristics of soft control for APR+ are presented to enhance the safety of MMIS design. In this paper, the major design characteristics of soft control for APR+ were introduced to increase the safety of MMIS design. In addition to the design characteristics of soft control described above, the following should be investigated closely for APR+ to get into the global nuclear industry

  20. Diagnostic des lésions étiologiques de l'infertilité secondaire à ...

    African Journals Online (AJOL)

    SARAH

    31 août 2013 ... Objectif : L'infertilité est une préoccupation du couple et de la famille en milieu africain. Le but de cette étude est d'améliorer la prise en charge des femmes présentant une infertilité secondaire au Bénin. Méthodologie et résultats : Il s'est agi d'une étude descriptive de type transversal. Elle a porté sur 110 ...

  1. Effet de la mise en culture des forêts secondaires sur les ...

    African Journals Online (AJOL)

    L'impact de la mise en culture des forêts sur les peuplements de macroinvertébrés du sol a été étudié en moyenne Côte d'Ivoire avec pour objectif d'identifier les plus sensibles à la perturbation des forêts. Les macroinvertébrés du sol de parcelles de forêt secondaire et de cultures vivrières ont été échantillonnés en utilisant ...

  2. Constructibility assessment of APR1400

    International Nuclear Information System (INIS)

    Cho, Sung Jae; Kang, Yong Chul; Lee, Jae Gon; Lim, Woo Sang

    2003-01-01

    APR1400 (formerly KNGR) development is one of national G-7 projects sponsored by government and KHNP (Korea Hydro and Nuclear Power Co., LTD). It is an evolutionary standard reactor with the thermal output of 4000MWt and has been adopted for Shin-Kori Unit 3 and 4. The government organizations, research institutes, universities and industries have participated in the project since 1992 along with KHNP, and the standard design certification program was issued in May 2002. The project set up the top-tier requirements about the safety, economy, operability and maintainability, and constructibility in the early design stage. The requirements have been evaluated periodically during the design process, and the results were reflected to the design. This paper describes the methods for constructibility enhancement and the results of schedule analysis to assure meeting construction duration target, which is set to 48 months from the first concrete pouring to the commercial operation on the condition that learning effects are maximized at Nth plant. To meet the target schedule, the design characteristics and constructibility studies such as new construction methods and construction schedule analysis were performed. The new construction methods presented here are over the top method for NSSS components, deck plate and steel from for concrete wall and slab, automatic welding for large bore piping, and modularization of components and structure, etc. (author)

  3. Traitement de surface par explosif du cuivre polycristallin : caractérisation microstructurale et comportement en fatigue plastique

    Science.gov (United States)

    Gerland, M.; Dufour, J. P.; Presles, H. N.; Violan, P.; Mendez, J.

    1991-10-01

    A new surface treatment technique with a primary explosive deposited in thin layer was applied to a polycrystalline pure copper. After treatment, surface roughness remains of high quality especially when compared to shot peened surfaces. The treated zone extends over several hundreds microns in depth and the microhardness profile exhibits a significant increasing of hardness with a maximum reaching 100% at the surface. The transmission electron microscopy shows a microstructure which changes with depth : below the surface, there is a thin recrystallized layer with very small grains followed by a region with numerous mechanical twins the density of which decreases when depth increases. Tested in fatigue with a constant plastic strain amplitude, the treated copper specimens exhibit a strong hardening from the first cycles compared to the untreated specimen ; however this initial hardening erases after 2% of the fatigue life. The fatigue resistance is not modified by the treatment. Une nouvelle technique de traitement de surface à l'aide d'un explosif primaire déposé en couche mince a été utilisée sur du cuivre pur polycristallin. L'état de surface après traitement reste de très bonne qualité, surtout comparé aux surfaces grenaillées. La zone traitée s'étend sur une profondeur de quelques centaines de microns et le profil de microdureté montre une importante augmentation de dureté avec un maximum en surface pouvant atteindre 100%. La micrcrostructure, observée par microscopie électronique en transmission, est caractérisée par une fine recristallisation en surface, puis par un abondant maclage dont la densité décroît lorsque la profondeur augmente. Testé en fatigue à déformation plastique imposée, le cuivre traité présente un fort écrouissage initial dès les premiers cycles, mais qui s'efface progressivement au cours du cyclage après 2% de la durée de vie, cette dernière n'étant pas modifiée par le traitement.

  4. The treatment of effluents; Ameliorations apportees aux traitements des residus radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G; Rodier, J; Robien, E de; Fernandez, N [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    -nucleides, nos recherches ont naturellement porte sur I'amelioration des traitements utilises en France: la coprecipitation et l'evaporation. Dans nos etudes, nous avons tout specialement tenu compte des deux conditions imposees dans les centres francais: 1 - Tri tres severe des effluents a la source, afin de limiter dans chaque categorie, le volume des liquides a traiter. 2 - Necessite d'une decontamination tres complete liee a la forte densite de population de notre pays. Dans un dernier chapitre, nous presenterons l'etude de deux methodes originales de traitement d'effluents liquides: 1 - L'emploi de resines echangeuses d'ions pour des liquides relativement charges en sel. Les resines sont utilisees sous forme sodique; le regenerant a cet effet est une solution de sel de sodium qui, apres decontamination par coprecipitation, est reutilisee. Ce procede permet d'obtenir un volume de boue plus reduit. 2 - L'utilisation d'un evaporateur naturel. Ce procede utilise l'air ambiant non sature d'humidite et a temperature ordinaire pour extraire I'eau des effluents aqueux. (auteurs)

  5. Traitement De La Peripneumonie Contagieuse Bovine Par L ...

    African Journals Online (AJOL)

    Traitement De La Peripneumonie Contagieuse Bovine Par L'oxyteTracycline Longe Action Et Transmission Experimentale de la Maladie A Partir de Bovins Traites. ... Tous les 14 animaux ont séroconverti et l'analyse post-mortem a montré la présence des lésions chroniques dont des séquestres pulmonaires chez 4 d'entre ...

  6. Study of the aqueous chemical treatment of uranium zirconium fuels; Etude du traitement chimique des combustibles uraniumzirconium par voie seche

    Energy Technology Data Exchange (ETDEWEB)

    Bourgeois, M; Nollet, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    A dry process has been studied for separating the uranium from the zirconium-either for recovering the enriched uranium from fuel element production waste, or with a view to treating this waste after irradiation. In this process the alloy is treated with hydrochloric acid at 400 deg. C in a fluidized corundum bed which causes the zirconium to volatilize as tetrachloride and the uranium to form the trichloride. This latter is then converted to the hexafluoride by attack with fluorure. After the laboratory tests, a first pilot plant with a capacity of 1 kg of alloy was tried out at the Fontenay-aux-Roses Nuclear Research Centre; this made it possible to fix the operational conditions for the process. An industrial scale plant was then built with the collaboration of the from Kuhlmann, and operated until a satisfactory process had been developed for treating the waste. This installation treats 3 kg/h of alloy with a yield for the hydrochloric acid of about 50 per cent and with a uranium loss in the zirconium tetrachloride of about 0.1 per cent. An active pilot plant capable of treating of treating a few kilos of irradiated alloy is now being studied. (authors) [French] On a etudie un procede de voie seche pour effectuer la separation de l'uranium et du zirconium - soit en vue de la recuperation de l'uranium enrichi contenu dans les dechets de fabrication des elements combustibles - soit en vue du traitement de ceux-ci apres irradiation. Ce procede consiste a attaquer l'alliage par l'acide chlorhydrique a 400 deg. C dans un lit fluidise de corindon, ce qui a pour effet de volatiliser le zirconium sous forme de tetrachlorure et de transformer l'uranium en trichlorure. Ce dernier est ensuite converti en hexafluorure par action du fluor. Apres des essais de laboratoire, un premier pilote a l'echelle de 1 kg d'alliage a ete experimente au Centre d'Etudes Nucleaires de Fontenay-aux-Roses et a permis de determiner les conditions operatoires du procede. En collaboration avec

  7. Use of ion exchange and early treatment of radioactive contamination in the digestive tract; Utilisation des echangeurs d'ions et traitement precoce de la contamination radioactive par voie digestive

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The efficiency of cation exchange resins for the treatment of digestive contamination with strontium has been studied on rats. The results obtained show that the most efficient resins are those of sulfonic type when administered in the ammonium form. The treatment is still efficient when applied 45 minutes after the ingestion of strontium. In the most favourable cases, the radioactivity of the skeleton was lower by a factor 6 in the treated animals than in controls. This easily applicable, rather safe and non specific treatment deserves to be retained for use. (author) [French] Une etude de l'efficacite des resines echangeuses de cations dans le traitement d'une contamination digestive par le strontium a ete entreprise chez le rat. Les resultats montrent que parmi les resines, les plus efficaces sont celles de type sulfonique, administrees sous forme ammonium. Le traitement est encore efficace 45 minutes apres l'ingestion du strontium. Dans les meilleurs cas, le squelette des rats traites etait six fois moins radioactif que celui des temoins. Ce traitement d'emploi facile, peu dangereux, non specifique, merite d'etre retenu. (auteur)

  8. La métaplasie osteoide de l'endomètre après une grossesse à terme: à propos d'un cas rare

    Science.gov (United States)

    Jayi, Sofia; Bouguern, Hakima; Fatemi, Hind; Chaara, Hikmat; Laamarti, Afaf; Melhouf, Aabdelilah

    2013-01-01

    La métaplasie ostéoïde de l'endomètre (MOE) est une entité rare correspondant à la présence de tissu osseux dans l'endomètre, elle est le plus souvent diagnostiquée dans un contexte d'infertilité secondaire faisant suite à une grossesse interrompue. Même si plusieurs facteurs de risque sont répertoriés, sa physiopathologie reste mal connue et sa traduction clinique est très variable. Nous rapportons un cas de MOE apparu suite à un curetage pour rétention placentaire en post-partum. Le diagnostic a été suspecté par l'hystéroscopie et confirmé par l’étude anatomopathologique. A notre connaissance c'est le premier cas décrit suite à un accouchement à terme. A travers notre cas et à la lumière d'une revue de la littérature nous insistons sur les caractéristiques épidémiologiques, physiopathologiques, cliniques et para cliniques de cette entité rare, dont la connaissance est primordiale pour un diagnostic sûr et par conséquent un traitement adapté permettant souvent de récupérer la fertilité de la patiente. PMID:23898363

  9. APR1400 Fluidic Device Sensitivity Test

    International Nuclear Information System (INIS)

    Choi, Nam Hyun; Chu, In Cheol; Min, Kyong Ho; Song, Chul Hwa

    2005-12-01

    In the safety injection tank at the emergency core cooling system of APR1400, a new safety design feature, passive fluidic device is equipped which includes no active driving system. It is essential to evaluate the new design feature with various experiments. For this reason, three categories of sensitivity tests have been performed in the present study. As the first sensitivity experiment, the effect of the height of the stand pipe was investigated. The second sensitivity test was conducted with removing the insert plate gasket to examine its effect. The effect of the expansion of the control nozzle width was ascertained from the third sensitivity test. The results of each test showed that the passive fluidic device which will be equipped in the SIT tank of APR1400 has great integrity and repeatability

  10. Radiation exposure reduction in APR1400

    International Nuclear Information System (INIS)

    Bae, C. J.; Hwang, H. R.; Matteson, D. M.

    2002-01-01

    The primary contributors to the total occupational radiation exposure in operating nuclear power plants are operation and maintenance activities during refueling outages. The Advanced Power Reactor 1400 (APR1400) includes a number of design improvements and plans to utilize advanced maintenance methods and robotics to minimize the annual collective dose. The major radiation exposure reduction features implemented in APR1400 are a permanent refueling pool seal, quick opening transfer tube blind flange, improved hydrogen peroxide injection at shutdown, improved permanent steam generator work platforms, and more effective temporary shielding. The estimated average annual occupational radiation exposure for APR1400 based on the reference plant experience and an engineering judgment is determined to be in the order of 0.4 man-Sv, which is well within the design goal of 1 man-Sv. The basis of this average annual occupational radiation exposure estimation is an eighteen (18) month fuel cycle with maintenance performed to steam generators and reactor coolant pumps during refueling outage. The outage duration is assumed to be 28 days. The outage work is to be performed on a 24 hour per day basis, seven (7) days a week with overlapping twelve (12) hour work shifts. The occupational radiation exposure for APR1400 is also determined by an alternate method which consists of estimating radiation exposures expected for the major activities during the refueling outage. The major outage activities that cause the majority of the total radiation exposure during refueling outage such as fuel handling, reactor coolant pump maintenance, steam generator inspection and maintenance, reactor vessel head area maintenance, decontamination, and ICI and instrumentation maintenance activities are evaluated at a task level. The calculated value using this method is in close agreement with the value of 0.4 man-Sv, that has been determined based on the experience and engineering judgement

  11. RESPONSE OF SELECTED LOCAL PLANTAIN CULTIVARS TO PIBS (PLANTS ISSUS DE BOURGEONS SECONDAIRES TECHNIQUE

    Directory of Open Access Journals (Sweden)

    Beloved Mensah DZOMEKU

    2014-12-01

    Full Text Available One major constraint to plantain production has been inadequate healthy planting materials at the time of planting. Several technologies for multiplying healthy planting materials exist but could not meet farmers’ demand. A study was conducted to assess the performance of various landraces plantain to plants issus de bourgeons secondaires (PIBS technique. Five cultivars of Musa sapientum (Apantu (False Horn, Asamienu (True Horn, Oniaba (intermediate French plantain and FHIA-21 (tetraploid hybrid plantain were tested to determine their response to the PIBS technique. Sword suckers of each cultivar with weight of between 0.2-0.5 kg were prepared and buried in fine sawdust in a humidity chamber built using transparent polyethylene sheets. Results at harvest showed that removal of rooted sprouts started three weeks after planting and every week thereafter for eight weeks. The intermediate French plantain cultivar (Oniaba produced the least average number (about 20 of healthy planting. Apantu (False Horn produced an average of about 75 healthy planting materials. The hybrid FHIA-21 on the other hand generated an average of about 85 healthy planting materials. Asamienu (True Horn produced the highest healthy seedlings of about 90 healthy planting materials. The results revealed that the leaf scar carries a primary bud at the intersection of each leaf sheath and several eyes along the entire length of the leaf sheath which could not have developed into suckers. However, with this technique the eyes could be activated to sprout as healthy planting materials. The technique proved as an efficient method of multiplying healthy planting materials for plantain and could thus be recommended for adoption not only by peasant farmers but also to others who could become commercial seed producers. But there will be a need for certification guidelines for seed growing systems.

  12. Etude de pratiques d'enseignement relatives a la modelisation en sciences et technologies avec des enseignants du secondaire

    Science.gov (United States)

    Aurousseau, Emmanuelle

    Les modeles sont des outils amplement utilises en sciences et technologies (S&T) afin de representer et d’expliquer un phenomene difficilement accessible, voire abstrait. La demarche de modelisation est presentee de maniere explicite dans le programme de formation de l’ecole quebecoise (PFEQ), notamment au 2eme cycle du secondaire (Quebec. Ministere de l'Education du Loisir et du Sport, 2007a). Elle fait ainsi partie des sept demarches auxquelles eleves et enseignants sont censes recourir. Cependant, de nombreuses recherches mettent en avant la difficulte des enseignants a structurer leurs pratiques d’enseignement autour des modeles et de la demarche de modelisation qui sont pourtant reconnus comme indispensables. En effet, les modeles favorisent la conciliation des champs concrets et abstraits entre lesquels le scientifique, meme en herbe, effectue des allers-retours afin de concilier le champ experimental de reference qu’il manipule et observe au champ theorique relie qu’il construit. L’objectif de cette recherche est donc de comprendre comment les modeles et la demarche de modelisation contribuent a faciliter l’articulation du concret et de l’abstrait dans l’enseignement des sciences et des technologies (S&T) au 2eme cycle du secondaire. Pour repondre a cette question, nous avons travaille avec les enseignants dans une perspective collaborative lors de groupes focalises et d’observation en classe. Ces dispositifs ont permis d’examiner les pratiques d’enseignement que quatre enseignants mettent en oeuvre en utilisant des modeles et des demarches de modelisation. L’analyse des pratiques d’enseignement et des ajustements que les enseignants envisagent dans leur pratique nous permet de degager des connaissances a la fois pour la recherche et pour la pratique des enseignants, au regard de l’utilisation des modeles et de la demarche de modelisation en S&T au secondaire.

  13. Optimisation des proprietes fonctionnelles des alliages a memoire de forme suite a l'application de traitements thermomecaniques

    Science.gov (United States)

    Demers, Vincent

    L'objectif de ce projet est de determiner les conditions de laminage et la temperature de traitement thermique maximisant les proprietes fonctionnelles de l'alliage a memoire de forme Ti-Ni. Les specimens sont caracterises par des mesures de calorimetrie, de microscopie optique, de gene ration de contrainte, de deformation recuperable et des essais mecaniques. Pour un cycle unique, l'utilisation d'un taux d'ecrouissage e=1.5 obtenu avec l'application d'une force de tension FT = 0.1sigma y et d'une huile minerale resulte en un echantillon droit, sans microfissure et qui apres un recuit a 400°C, produit un materiau nanostructure manifestant des proprietes fonctionnelles deux fois plus grandes que le meme materiau ayant une structure polygonisee. Pour des cycles repetes, les memes conditions de laminage sont valables mais le niveau de deformation optimal est situe entre e=0.75-2, et depend particulierement du mode de sollicitation, du niveau de stabilisation et du nombre de cycles a la rupture requis par l'application.

  14. Review of APR+ Level 2 PSA

    International Nuclear Information System (INIS)

    Lehner, J.R.; Mubayi, V.; Pratt, W.T.

    2012-01-01

    Brookhaven National Laboratory (BNL) assisted the Korea Institute of Nuclear Safety (KINS) in reviewing the Level 2 Probabilistic Safety Assessment (PSA) of the APR+ Advanced Pressurized Water Reactor (PWR) prepared by the Korea Hydro and Nuclear Power Co., Ltd (KHNP) and KEPCO Engineering and Construction Co., Inc. (KEPCO-E and C). The work described in this report involves a review of the APR+ Level 2 PSA submittal (Ref. 1). The PSA and, therefore, the review is limited to consideration of accidents initiated by internal events. As part of the review process, the review team also developed three sets of Requests for Additional Information (RAIs). These RAIs were provided to KHNP and KEPCO-E and C for their evaluation and response. This final detailed report documents the review findings for each technical element of the PSA and includes consideration of all of the RAIs made by the reviewers as well as the associated responses. This final report was preceded by an interim report (Ref. 2) that focused on identifying important issues regarding the PSA. In addition, a final meeting on the project was held at BNL on November 21-22, 2011, where BNL and KINS reviewers discussed their preliminary review findings with KHNP and KEPCO-E and C staffs. Additional information obtained during this final meeting was also used to inform the review findings of this final report. The review focused not only on the robustness of the APR+ design to withstand severe accidents, but also on the capability and acceptability of the Level 2 PSA in terms of level of detail and completeness. The Korean nuclear regulatory authorities will decide whether the PSA is acceptable and the BNL review team is providing its comments for KINS consideration. Section 2.0 provides the basis for the BNL review. Section 3.0 presents the review of each technical element of the PSA. Conclusions and a summary are presented in Section 4.0. Section 5.0 contains the references.

  15. Syndrome de loge aiguë secondaire à une injection intraveineuse d ...

    African Journals Online (AJOL)

    Il s'agit d'un patient âgé de 27 ans, connu toxicomane depuis 2008 qui a présenté un syndrome de loge aigu suite à une injection d'héroïne en intraveineuse au niveau du pli du coude du membre supérieur droit. Le patient a consulté aux urgences 6 heures après l'injection d'héroïne, l'examen clinique initial a trouvé une ...

  16. Inhibition of Pseudomonas aeruginosa virulence: characterization of the AprA-AprI interface and species selectivity.

    Science.gov (United States)

    Bardoel, Bart W; van Kessel, Kok P M; van Strijp, Jos A G; Milder, Fin J

    2012-01-20

    Pseudomonas aeruginosa secretes the virulence factor alkaline protease (AprA) to enhance its survival. AprA cleaves one of the key microbial recognition molecules, monomeric flagellin, and thereby diminishes Toll-like receptor 5 activation. In addition, AprA degrades host proteins such as complement proteins and cytokines. P. aeruginosa encodes a highly potent inhibitor of alkaline protease (AprI) that is solely located in the periplasm where it is presumed to protect periplasmic proteins against secreted AprA. We set out to study the enzyme-inhibitor interactions in more detail in order to provide a basis for future drug development. Structural and mutational studies reveal that the conserved N-terminal residues of AprI occupy the protease active site and are essential for inhibitory activity. We constructed peptides mimicking the N-terminus of AprI; however, these were incapable of inhibiting AprA-mediated flagellin cleavage. Furthermore, we expressed and purified AprI of P. aeruginosa and the homologous (37% sequence identity) AprI of Pseudomonas syringae, which remarkably show species specificity for their cognate protease. Exchange of the first five N-terminal residues between AprI of P. syringae and P. aeruginosa did not affect the observed specificity, whereas exchange of only six residues located at the AprI surface that contacts the protease did abolish specificity. These findings are elementary steps toward the design of molecules derived from the natural inhibitor of the virulence factor AprA and their use in therapeutic applications in Pseudomonas and other Gram-negative infections. Copyright © 2011 Elsevier Ltd. All rights reserved.

  17. Vingt ans après…

    Directory of Open Access Journals (Sweden)

    François Burgat

    2002-05-01

    Full Text Available Le dixième numéro des Chroniques Yéménites, publié vingt ans après la création du Centre Français d'Archéologie et de Sciences Sociales de Sanaa reflète des ambitions souvent exprimées: donner une chance aux jeunes chercheurs et couvrir un large éventail disciplinaire au service de l'affirmation de la vocation régionale du Centre. Depuis Sanaa ou Paris, chercheurs, doctorants ou stagiaires, de l'Ecole normale supérieure, de l'INALCO, de l'Université de Sanaa et de bon nombre d'institu...

  18. MELCOR code modeling for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young; Park, S. Y.; Kim, D. H.; Ahn, K. I.; Song, Y. M.; Kim, S. D.; Park, J. H

    2001-11-01

    The severe accident phenomena of nuclear power plant have large uncertainties. For the retention of the containment integrity and improvement of nuclear reactor safety against severe accident, it is essential to understand severe accident phenomena and be able to access the accident progression accurately using computer code. Furthermore, it is important to attain a capability for developing technique and assessment tools for an advanced nuclear reactor design as well as for the severe accident prevention and mitigation. The objective of this report is to establish technical bases for an application of the MELCOR code to the Korean Next Generation Reactor (APR1400) by modeling the plant and analyzing plant steady state. This report shows the data and the input preparation for MELCOR code as well as state-state assessment results using MELCOR code.

  19. Development of Reactor Coolant Pump for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Sang-Youn; Chu, Sung-Min; Chang, Jin-Young [Doosan Heavy Industries and Construction, Changwon (Korea, Republic of)

    2015-10-15

    The development was focused on the performance requirements for APR1400 and to achieve the goals of the safety, reliability and adaptability for APR1400 system design. In addition, APR1400 RCP design was customized considering convenience of installation, operation and maintainability. This paper describes the details of the development process, improved design feature and type test results. Based on development of core technology of RCP, DOOSAN supplies the localized and improved APR1400 RCP to Shin-Hanul 1 and 2 Project. This would be good experience that the RCP core technology can break foreign monopoly in supplying the domestic nuclear industry. Also, there expect APR1400 RCP can be sustainable revenue models in nuclear industry. Moreover, development of RCP will be a catalyst to enhance design capacity for equipment and system of nuclear power plant as well as evaluation and verification skills of Korean nuclear industry.

  20. The APR1400 Core Design by Using APA Code System

    International Nuclear Information System (INIS)

    Choi, Yu Sun; Koh, Byung Marn

    2008-01-01

    The nuclear design for APR1400 has been performed to prepare the core model for Automatic Load Follow Operation Simulation. APA (ALPHA/ PHOENIXP/ ANC) code system is a tool for the multi-cycle depletion calculations for APR1400. Its detail versions for ALPHA, PHOENIX-P and ANC are 8.9.3, 8.6.1 and 8.10.5, respectively. The first and equilibrium core depletion calculations for APR1400 have been performed to assure the target cycle length and confirm the safety parameters. The parameters are satisfied within limitation about nuclear design criteria. This APR1400 core models will be based on the design parameters for APR1400 Simulator

  1. The processing and management of wastes from atomic reactors; Nouvelles installations industrielles du C.E.A. pour le traitement des dechets radioactifs liquides et solides

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E; Bourdrez, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    particulier: - Pour les liquides, les traitements par voie physique, chimique et physicochimique. - Pour les solides, les techniques de decontamination, de reduction de volume et de conditionnement de longue duree. Nous developpons egalement dans ce rapport les differents modes de collecte et de stockage avant et apres traitement des dechets solides. La communication se termine par un rapide expose des etudes en cours, tant techniques qu'economiques sur ce sujet. (auteurs)

  2. Lambeaux autofermants pour le traitement des brulures electriques du scalp par haut voltage

    Science.gov (United States)

    Hafidi, J.; El Mazouz, S.; El Mejatti, H.; Fejjal, N.; Gharib, N.E.; Abbassi, A.; Belmahi, A.M.

    2011-01-01

    Summary Les brûlures électriques par haut voltage sont responsables de gros dégâts tissulaires en immédiat et dans les jours suivant l’accident du fait de la chaleur importante dégagée par effet joule et de la thrombose microvasculaire évolutive. Les pertes de substances du scalp secondaires à ces brûlures nécessitent une couverture par lambeaux vu la destruction du périoste et du calvarium en regard. De juin 1997 à juin 2008, 15 patients ont été traités pour des pertes de substance du scalp secondaires à des brûlures électriques par haut voltage de diamètre allant de 8 à 11 cm et siégeant dans la région tonsurale. Ces patients ont été opérés dans la première semaine suivant l’accident. Les pertes de substance du scalp de taille moyenne secondaires à ces brûlures peuvent être couvertes per primam de façon fiable par des lambeaux locaux axialisés et multiples. Nous relatons l’expérience du Service de Chirurgie Plastique du Centre Hospitalier Universitaire Ibn-Sina, Rabat, Maroc, dans la gestion et la prise en charge de ces brûlures. PMID:22262963

  3. Évaluation des émissions de gaz à effet de serre des filières de traitement et de valorisation des boues issues du traitement des eaux usées

    OpenAIRE

    Reverdy, A.L.; Pradel, M.

    2011-01-01

    / Ce rapport présente l'inventaire des différentes consommations énergétiques, en consommables et des GES pour chaque poste de traitement et de valorisation des boues issues du traitement des eaux usées.

  4. EU-APR Design in compliance with EUR Grid Requirement

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong-Hwan; Lee, Keun-Sung [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    European Utility Requirements (EUR) provides technical requirements for the generation III nuclear power plant in the European countries. EUR grid requirements present the plant requirements to satisfy the needs of the grid network. The grid requirements are the precondition for the operation of a generating plant on the network. This paper describes EU-APR design which has taken account of EUR grid requirements. In this paper, EU-APR designs according to the EUR grid requirements were described. EU-APR was designed in compliance with the voltage and frequency operation field and also designed to have the capability of load following such as primary control, secondary control, and daily load following. Consequently, the EU-APR design according to the EUR grid requirements is expected to get competitiveness and enhance the license feasibility in the European nuclear market.

  5. A Probability Analysis of the Generating Cost for APR1000+

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Gag-Hyeon; Kim, Dae-Hun [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The nuclear power plant market is expected to grow rapidly in order to address issues of global warming, cutting CO{sub 2} emissions and securing stable electricity supplies. Under these circumstances, the main primary goal of the APR1000+ development is to ensure export competitiveness in the developing countries in the Middle East and Southeast Asia. To that end, APR1000+(1,000MWe, 3.5 generation) will be developed based on APR+ (1,500MWe, 3.5 generation). And comparing to OPR1000(Korean Standard Nuclear power Plant, 2.5 generation), APR1000+ have many design features such as the 60 year design life time, comprehensive site requirement of 0.3g seismic design, stability improvement, operability improvement and provisions for severe accidents. In this simulation, the results of generating cost for APR1000+ preliminary conceptual design using a probability method was shown to be 48.37 ~ 74.22 won/kWh(median value 56.51 won/kWh). Those of OPR1000 was 42.08 ~ 61.77 won/kWh(median value 48.63 won/kWh). APR1000+ has -16.2% cost advantage over OPR1000 nuclear power plant. The main reason of this results is due to adding several safety designs.

  6. ITAAC Development for APR1400 NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Jin Kwon; Kim, Myoung Ki

    2013-01-01

    ITAAC (Inspections, Tests, Analyses and Acceptance Criteria) is essential document for Design Certification, which is certified by NRC and ruled as the Appendix of the 10 CFR Part 52. Approximately 870 ITAAC items were selected for APR1400 Design Certification to be submitted to NRC. In this paper, the code and standard related to ITAAC and process of ITACC development are discussed to seek the way to complete the best ITAAC to get the Design Certification of APR1400 from NRC through the lessons learned from other competitive applicants. For saving the time and manpower to complete ITAAC of APR1400 NRC DC and reduction of the RAIs (Request Additional Information) from NRC, we took advantage of the lessons learned from the competitive designs like US-APWR and AP1000 based on KNGR ITAAC. Finally new and different ITAAC from ITAAC of KNGR was developed for APR1400 DC from NRC. RG 1.206 and SRPs were applied first in Korea to the APR1400 DCD preparation. For testability and acceptability check, ITAAC V and V table was completed by the system designers. APR1400 DCD will be submitted by the end of September this year and we hope that NRC issues lees RAIs on ITAAC document

  7. Optimization Strategy of the APR+ BOP Technical Specifications

    International Nuclear Information System (INIS)

    Cho, Yoon Sang; Lee, Jae Gon; Han, Sung Heum

    2016-01-01

    The BOP is one of the key factors for successful project implementation of NPP. In constructing the APR1400 NPP, the BOP procurement has been one of the biggest concerns. Due to the design changes and increased capacity of equipment in NPP, lots of BOPs should be ‘first supplied equipment’ [hereinafter, ‘FSE’]. The manufacture-ability, and the performances of FSEs have not been fully proved and tested, manufacturers and suppliers are requested to submit Reports for Equipment Qualification Evaluation in accordance with 10 CFR 50.49, IEEE 323. They need at least 1-2 years’ tests for Environment Qualification (EQ) and Seismic Qualification (SQ). This study is focused how to prepare the BOP purchase specifications in order to control the FSEs, especially in safety class equipment. With the optimization plan for BOP packages of this study, the FSEs’ occurrence can be reasonably controlled as low as possible. For successful NPP project, the concerns in procuring BOPs shall be fully analyzed beforehand. Now Korea is preparing new era of APR+, with closing the time of APR1400. The technical specification of APR+ BOPs can be developed and prepared successfully and very effectively according to this optimization plan. This will be a great contribution not only in constructing APR+ in time, but also in exporting APR+ overseas, all over the world in the future

  8. Optimization Strategy of the APR+ BOP Technical Specifications

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Yoon Sang; Lee, Jae Gon; Han, Sung Heum [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The BOP is one of the key factors for successful project implementation of NPP. In constructing the APR1400 NPP, the BOP procurement has been one of the biggest concerns. Due to the design changes and increased capacity of equipment in NPP, lots of BOPs should be ‘first supplied equipment’ [hereinafter, ‘FSE’]. The manufacture-ability, and the performances of FSEs have not been fully proved and tested, manufacturers and suppliers are requested to submit Reports for Equipment Qualification Evaluation in accordance with 10 CFR 50.49, IEEE 323. They need at least 1-2 years’ tests for Environment Qualification (EQ) and Seismic Qualification (SQ). This study is focused how to prepare the BOP purchase specifications in order to control the FSEs, especially in safety class equipment. With the optimization plan for BOP packages of this study, the FSEs’ occurrence can be reasonably controlled as low as possible. For successful NPP project, the concerns in procuring BOPs shall be fully analyzed beforehand. Now Korea is preparing new era of APR+, with closing the time of APR1400. The technical specification of APR+ BOPs can be developed and prepared successfully and very effectively according to this optimization plan. This will be a great contribution not only in constructing APR+ in time, but also in exporting APR+ overseas, all over the world in the future.

  9. What about sexual life after therapy for prostate cancer?; Y a t-il une vie sexuelle apres traitement d'un cancer prostatique?

    Energy Technology Data Exchange (ETDEWEB)

    Cosset, J.M. [Institut Curie, 75 - Paris (France)

    2002-05-01

    The precise assessment of sexual dysfunction after treatment of prostatic cancer cannot be avoided in 2002. These iatrogenic complications may significantly alter the quality of life of the patients. In addition, sexual toxicity is progressively becoming a cardinal parameter for the treatment choice, both for the patient and the physician. Significant efforts allowed to reduce sexual toxicity after therapy in the recent years. As an example, nerve-sparing surgical techniques have been proposed, whenever reasonable. However, in spite of these surgical advances, data suggest that overall, the new irradiation techniques (conformal radiotherapy and brachytherapy) are responsible for less alteration of sexual life than surgery. Another potential advantage is that sildenafil (Viagra) is able to restore potency in a majority of cases after radiotherapy, while it is usually poorly effective after surgery. (author)

  10. Les filtres et lits plantés de roseaux en traitement d'eaux usées domestiques. Perspectives pour le traitement d'eaux pluviales

    OpenAIRE

    Boutin, C.; Esser, D.; Molle, P.; Liénard, A.

    2000-01-01

    L'article decrit puis compare le fonctionement des filtres plantes de roseaux a flux vertical puis horizontal a partir d'experiences francaises ou internationales sur le traitement des eaux usees domestiques. La discussion finale signale, par l'intermediaire d'experiences, la possibilite de traiter des eaux pluviales par ces techniques; pour autant, les bases de dimensionnement ne sont pas établies. / This article presents and describes vertical and horizontal reed beds filters for domestic w...

  11. Un solveur HLLT pour les equations de Saint-Venant et traitement ...

    African Journals Online (AJOL)

    Un solveur HLLT pour les equations de Saint-Venant et traitement des ... Enfin, des applications numériques sur des cas tests sont présentées. ... the system of partial-differential equations is completed by a trivial equation for the bathymetry.

  12. Un solveur HLLTpour les equations de Saint-vVenant et traitement ...

    African Journals Online (AJOL)

    Un solveur HLLTpour les equations de Saint-vVenant et traitement des ... Enfin, des applications numériques sur des cas tests sont présentées. ... the system of partial-differential equations is completed by a trivial equation for the bathymetry.

  13. Résultats du traitement chirurgical des traumatismes du rachis à l ...

    African Journals Online (AJOL)

    incomplète était prédictive de bon pronostic P< 0,001. Les traumatismes du rachis cervical sont des urgences neurologiques qui mettent en jeu le pronostic vital et fonctionnel des patients. Mots clés : Traumatisme, rachis, traitement. The purpose of this series was to describe the results of surgical treatment of spinal injury.

  14. Development of Reference Source Terms for EU-APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, ByungIl; Lee, Chonghui; Lee, Dongsu; Ko, Heejin; Kang, Sangho [KEPCO Engineering and Construction Co. Inc., Yongin (Korea, Republic of)

    2014-05-15

    These source terms are developed for the typical U. S. NPP and do not reflect the design characteristics of EU-APR1400 (1,400 MWe PWR) which will be applied for the EUR certification in European countries. The process of developing the RST for EU-APR1400 is to undergo a similar process that NUREG-1465 had gone through when it came out with its proposed source terms. The purpose of this study is to develop the EU-APR1400 design-specific RST complied with the EUR. The Large LOCA is the reference equence used in the NUREG-1465 evaluation, whereas the EUAPR1400 risk-significant sequences are dominated by small LOCA and non-LOCA sequences. Moreover, when considering the EU-APR1400 has many design features to mitigate the consequences of severe accident phenomena, it is not surprising that the aspects of both release fractions and durations are distinctly different from NUREG-1465. This RST will be continuously updated to reflect to the design features of EU-APR1400, and then, be used as the reference for design purposes such as criteria satisfaction of radioactivity releases, equipment survivability, control room habitability for severe accident, and so on.

  15. APR1400 CEA Withdrawal at Power Accident Analysis using KNAP

    International Nuclear Information System (INIS)

    Lee, Dong-Hyuk; Yang, Chang-Keun; Kim, Yo-Han; Sung, Chang-Kyung

    2006-01-01

    KEPRI (Korea Electric Power Research Institute) has been developing safety analysis methodology for non- LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code. RETRAN code is a non- LOCA safety analysis code developed by EPRI. The new methodology will replace existing CE (Combustion Engineering) supplied codes and methodologies currently used in non-LOCA analysis of OPR1000. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400). The CEA (Control Element Assembly) withdrawal at power accident is one of the 'reactivity and power distribution anomalies' events and the results are typically described in the chapter 15.4.2 of SAR (Safety Analysis Report). The APR1400 has been designed to generate 1,400MWe of electricity with advanced features for greatly enhanced safety and economic goals. The CEA withdrawal at power analysis in APR1400 SSAR (Standard Safety Analysis Report) is analyzed with CESEC-III computer code. In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, CEA withdrawal at power accident is analyzed using RETRAN code and it is compared with results from APR1400 SSAR

  16. Evaluation of the Planned Outage Durations in EU-APR

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Byung Joon; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    EU-APR has been designed to comply with European Utility Requirements (EUR) and nuclear design requirements of the European countries. And it is modified and improved from its original design of APR1400. The whole duration varies depending on items for additional process. Refueling and regular maintenance outage is comprised of basic processes and Main turbine-generator outage includes dismantling inspection of main generator and high pressure turbine as a critical path in addition to basic processes. In-Service Inspection Outage includes Automatic ultrasonic inspection on the upper side/lower side of a nuclear reactor as a critical path in addition to basic processes. The planned outage durations of EU-APR are optimized according to the above results. And they are complied with EUR Requirement (EUR 2.2.7.2.2 B), respectively. In addition, outage duration can be reduced with improved operating technology and more maintenance friendly environment including betterment of filling, drain and ventilation.

  17. Evaluation of the Planned Outage Durations in EU-APR

    International Nuclear Information System (INIS)

    Jung, Byung Joon; Lee, Keun Sung

    2016-01-01

    EU-APR has been designed to comply with European Utility Requirements (EUR) and nuclear design requirements of the European countries. And it is modified and improved from its original design of APR1400. The whole duration varies depending on items for additional process. Refueling and regular maintenance outage is comprised of basic processes and Main turbine-generator outage includes dismantling inspection of main generator and high pressure turbine as a critical path in addition to basic processes. In-Service Inspection Outage includes Automatic ultrasonic inspection on the upper side/lower side of a nuclear reactor as a critical path in addition to basic processes. The planned outage durations of EU-APR are optimized according to the above results. And they are complied with EUR Requirement (EUR 2.2.7.2.2 B), respectively. In addition, outage duration can be reduced with improved operating technology and more maintenance friendly environment including betterment of filling, drain and ventilation

  18. Development of Nanosatellite Technology with APRS Module for Disaster Mitigation

    Science.gov (United States)

    Prahyang, S. Y.; Dhiya’Ulhaq, M. Z.; Golim, O. P.; Gunawan, R.; Suhandinata; Jahja, E.; Nelwan, E. R. G.; Ananta, C.; Chow, I. M.; Mali, N. D. F.

    2018-05-01

    Development of nanosatellite technology has enabled satellites to be developed with multiple capabilities for a specific mission in a short time with a low cost. Satellite communications are proved to be more effective in delivering information due to its large coverage area. Surya Satellite-1 will become the first Indonesian nanosatellite developed by undergraduate students. It is designed with low-cost commercial payloads, including an APRS module for communication and operated on VHF and UHF amateur radio frequencies. The mission of the satellites focused on disaster mitigation through APRS communication network with remote stations located on disaster-prone areas.

  19. Comment ameliorer la selection et le traitement des messages verbaux? (How to Improve the Selection and Processing of Verbal Messages)

    National Research Council Canada - National Science Library

    Rivenez, Marie; Darwin, Chris; Guillaume, Anne

    2005-01-01

    L'objectif de cette recherche est d'ameliorer la selection des messages verbaux. Nous cherchons a determiner les facteurs influencant le traitement d'un message verbal lorsque l'attention est portee sur un autre message...

  20. Améliorer le traitement de la douleur chez les enfants en Thaïlande ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    21 avr. 2016 ... FLIKR/ROSS POLLOCK. Des lignes directrices sur la gestion de la douleur dans les hôpitaux thaïlandais aident à prévenir ou à traiter la douleur chez les enfants. Global Health Research Initiative. Les enfants sont plus susceptibles que les adultes de souffrir de l'absence de traitement ou de traitement ...

  1. APR1400 Locked Rotor Transient Analysis using KNAP

    International Nuclear Information System (INIS)

    Lee, Dong-Hyuk; Kim, Yo-Han; Ha, Sang Jun

    2007-01-01

    KEPRI (Korea Electric Power Research Institute) has developed safety analysis methodology for non-LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code for most transients. For locked rotor transient DNBR analysis, UNICORN-TM code is used. UNICORN-TM is the unified code of RETRAN, MASTER and TORC. The UNICORN-TM has 1-D and 3-D neutron kinetics calculation capability. For locked rotor DNBR analysis, 1-D neutron kinetics is used. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400) locked rotor analysis and compare the results with those in the APR1400 SSAR(Standard Safety Analysis Report). The locked rotor transient is one of the 'decrease in reactor coolant system flow rate' events and the results are typically described in the chapter 15.3.3 of SAR (Safety Analysis Report). In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, locked rotor transient is analyzed using UNICORN-TM code and the results are compared with those from APR1400 SSAR

  2. System Response Analysis of LOCV for APR1400 Using KNAP

    International Nuclear Information System (INIS)

    Kim, Yo-Han; Sung, Chang-Kyung; Jun, Hwang-Yong

    2006-01-01

    Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has been developed the non-loss-of-coolant accident (non-LOCA) analysis methodology, called as the Korea Non-LOCA Analysis Package (KNAP), for the typical Optimized Power Reactor 1000 (OPR1000) plants. Considering current licensing methodology conducted by ABB-CE, however, the KNAP could be applied to Advanced Power Reactor 1400 (APR1400). In spite of some difference in components of two plant types, there is a close resemblance between their nuclear steam supply systems (NSSS). So, in this study, the loss of condenser vacuum (LOCV) event were analyzed using KNAP for APR1400 to estimate the feasibility of the application and the results were compared with those given in APR1400 Standard Safety Analysis Report (SSAR), which were calculated using the CESEC-III code of ABB-CE. Through the study, it was concluded that the KNAP could be applicable to APR1400 on the view point of LOCV event

  3. Functional Requirement Analysis and Function Allocation for APR 1400

    International Nuclear Information System (INIS)

    Nuraslinda, Anuar; Florah, Kamanja; Noloyiso, Mtoko and others

    2013-01-01

    This paper intends to fulfill the FRA and FA of the HFE as required in Chapter 4 of NUREG-0711 rev. 3 for APR1400 to satisfy both plant safety and power generation objectives. This paper aims to evaluate the FRA and FA for APR1400. The allocation of function is done at the system level for all processes for both the power generation and safety goals, following the NUREG/CR-3331 guideline. As a conclusion, this paper has successfully implemented the requirements and methodology specified in NUREG-0711 for APR 1400. The Functional Requirement Analysis (FRA) and Function Allocation (FA) are required by the regulation in the Human Factors Engineering (HFE) program. The FRA defines the functions, processes, and system for plant safety and power generation. The FA allocates the functions to human operator, automation, or a combination of two. The FRA and FA for APR1400 have been performed in the very early stage of development but only for the plant safety. However, the analysis did not include the goal of power generation and also did not fully satisfy the latest revision of NUREG-0711

  4. Resultats visuels et complications apres chirurgie de la cataracte ...

    African Journals Online (AJOL)

    Resultats visuels et complications apres chirurgie de la cataracte: cas de l' Hopital Ophtalmologique Saint Andre de Tinre au nord-Benin. K.M. Amedome, C.R.A. Assavedo, M Aboudou, K Vonor, N Maneh, K Nonon Saa, K Dzidzinyo, K.D. Ayena, M Banla, K Balo ...

  5. APR1400 Locked Rotor Transient Analysis using KNAP

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong-Hyuk; Kim, Yo-Han; Ha, Sang Jun [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    KEPRI (Korea Electric Power Research Institute) has developed safety analysis methodology for non-LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code for most transients. For locked rotor transient DNBR analysis, UNICORN-TM code is used. UNICORN-TM is the unified code of RETRAN, MASTER and TORC. The UNICORN-TM has 1-D and 3-D neutron kinetics calculation capability. For locked rotor DNBR analysis, 1-D neutron kinetics is used. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400) locked rotor analysis and compare the results with those in the APR1400 SSAR(Standard Safety Analysis Report). The locked rotor transient is one of the 'decrease in reactor coolant system flow rate' events and the results are typically described in the chapter 15.3.3 of SAR (Safety Analysis Report). In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, locked rotor transient is analyzed using UNICORN-TM code and the results are compared with those from APR1400 SSAR.

  6. 1001.pdf | 25apr2010 | currsci | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    2010-04-25

    Apr 25, 2010 ... error. The page your are looking for can not be found! Please check the link or use the navigation bar at the top. YouTube · Twitter · Facebook · Blog. Academy News. IAS Logo. Summer Research Fellowship Programme 2018. Dates Extended To 7 December 2017. Register here · Focus Area Science ...

  7. Procédé de traitement d'une ressource fluide, programme d'ordinateur et module de traitement associés

    OpenAIRE

    Rapaport, Alain; Rousseau, Antoine; Harmand, Jérôme

    2014-01-01

    Pour la bio-remédiation de ressources en eau (bassins, lacs..) qui nécessitent d’être traitées par une unité externe de purification à l’aide de bioprocédés, l’invention consiste à mettre en place un réseau « intelligent » de pompes qui s’adaptent au cours du temps à l’hydrodynamique et à la pollution du milieu. L’objectif est d’optimiser la durée du traitement et/ou la qualité de la remédiation.

  8. Pseudomonas syringae evades host immunity by degrading flagellin monomers with alkaline protease AprA.

    Science.gov (United States)

    Pel, Michiel J C; van Dijken, Anja J H; Bardoel, Bart W; Seidl, Michael F; van der Ent, Sjoerd; van Strijp, Jos A G; Pieterse, Corné M J

    2014-07-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of bacterial species. In addition, we investigated the role of AprA in virulence of the bacterial plant pathogen P. syringae pv. tomato DC3000. The AprA-deficient DC3000 ΔaprA knockout mutant was significantly less virulent on both tomato and Arabidopsis thaliana. Moreover, infiltration of A. thaliana Col-0 leaves with DC3000 ΔaprA evoked a significantly higher level of expression of the defense-related genes FRK1 and PR-1 than did wild-type DC3000. In the flagellin receptor mutant fls2, pathogen virulence and defense-related gene activation did not differ between DC3000 and DC3000 ΔaprA. Together, these results suggest that AprA of DC3000 is important for evasion of recognition by the FLS2 receptor, allowing wild-type DC3000 to be more virulent on its host plant than AprA-deficient DC3000 ΔaprA. To provide further evidence for the role of DC3000 AprA in host immune evasion, we overexpressed the AprA inhibitory peptide AprI of DC3000 in A. thaliana to counteract the immune evasive capacity of DC3000 AprA. Ectopic expression of aprI in A. thaliana resulted in an enhanced level of resistance against wild-type DC3000, while the already elevated level of resistance against DC3000 ΔaprA remained unchanged. Together, these results indicate that evasion of host immunity by the alkaline protease AprA is important for full virulence of strain DC3000 and likely acts by preventing flagellin monomers from being recognized by its cognate immune receptor.

  9. Co-infection tuberculose et VIH: Hausse des CD4 avec le traitement ...

    African Journals Online (AJOL)

    INTRODUCTION: L'administration parallèle d'antituberculeux et d'antirétroviraux chez nos patients co-infectés par la tuberculose et le virus de l'immunodéficience humaine (VIH) nous a fait observer près de 25 % d'hépatites toxiques conduisant à l'arrêt de tous traitements. Nous avons ainsi dû mener ce travail en ...

  10. Le don après un décès d'origine cardiocirculatoire au Canada

    Science.gov (United States)

    Shemie, Sam D.; Baker, Andrew J.; Knoll, Greg; Wall, William; Rocker, Graeme; Howes, Daniel; Davidson, Janet; Pagliarello, Joe; Chambers-Evans, Jane; Cockfield, Sandra; Farrell, Catherine; Glannon, Walter; Gourlay, William; Grant, David; Langevin, Stéphan; Wheelock, Brian; Young, Kimberly; Dossetor, John

    2006-01-01

    Résumé Ces recommandations sont le fruit d'un processus multidisciplinaire national ayant duré un an et visant à déterminer si et comment l'on pourrait procéder au don d'organes après un décès d'origine cardiocirculatoire («don après le décès cardiocirculatoire», ou DDC) au Canada. Le forum national organisé en février 2005 a permis aux participants de discuter et d'élaborer des recommandations sur les principes, interventions et pratiques se rapportant au DDC. Les aspects éthiques et juridiques ont été abordés dans les discussions. À la fin du Forum, la majorité des participants ont été favorables à l'implantation de programmes de DDC au Canada. Les participants du Forum ont également convenu qu'il fallait formuler et prôner des valeurs fondamentales pour orienter l'élaboration de programmes et de protocoles basés sur le cadre médical, éthique et juridique établi lors de cette réunion. Même si la possibilité d'un don d'organes et de tissus doit faire partie intégrante des soins de fin de vie, il faut insister sur le fait que le devoir de diligence envers les patients mourants et leurs familles doit demeurer la priorité des équipes soignantes. La complexité et les répercussions profondes du décès sont reconnues et doivent être respectées, de même que les différences personnelles, ethnoculturelles et religieuses face à la mort et au don d'organes. Les décisions d'arrêter le traitement de maintien des fonctions vitales, la prise en charge des derniers moments de la vie et le diagnostic de décès selon des critères cardiocirculatoires doivent être distincts et indépendants des processus de don et transplantation. Ce rapport contient des recommandations destinées aux gestionnaires de program, aux autorités sanitaires régionales et aux instances appelés à élaborer les protocoles de DDC. Les programmes doivent être conçus en fonction des éléments suivants : direction et planification locales, éducation et

  11. Economic Management of a Centre for Processing Radioactive Residues; Gestion Economique D'un Centre de Traitement de Residus Radioactifs; Ehkonomicheskij aspekt obrashcheniya s radioaktivnymi otkhodami v obrabatyvayushchem tsentre; Gestion Economica de un Centro de Tratamiento de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Van Lint, J. M. [BELGONUCLEAIRE, Bruxelles (Belgium)

    1966-02-15

    The paper shows the differences between the operations of an industrial undertaking and an installation for residue processing and describes the auditing system of an industry concerned with various phases of processing. It shows that the auditing programme is necessarily and intimately connected with the general organization of the entire undertaking and that it is a useful tool of economic management. In this connection, the paper deals at length with the auditing principles used in arriving at - the overall cost of the final product, - the specific cost of each processing phase,. (author) [French] Apres avoir expose les differences existant entre les operations effectuees par une entreprise industrielle et par une installation de traitement des residus, le memoire decrit la comptabilite d'une industrie comprenant plusieurs phases de traitement. Il montre comment le plan comptable est necessairement et intimement lie a l'organisation generale de l'ensemble de l'entreprise et est un outil utile de gestion economique, A cette fin, le memoire developpe les principes comptables permettant d'etablir: - le prix de revient global du produit final obtenu, - les prix de revient specifiques de chaque phase de traitement partiel. (author) [Spanish] Despues de exponer las diferencias que existen entre las operaciones efectuadas en una empresa industrial y en una instalacion de tratamiento de desechos, el autor analiza la contabilidad de una industria que comprende diversas fases de tratamiento. Muestra como el plan contable esta necesaria e intimamente vinculado a la organizacion general del conjunto de la empresa y es un instrumento util de gestion economica. Con este fin, desarrolla los principios contables que permiten establecer: - el precio de costo global del producto final obtenido, - los precios de costo especificos de cada fase de tratamiento parcial. (author) [Russian] Posle Izlozhenija Razlichij, Sushhestvujushhih Mezhdu Operacijami Na Promyshlennom Predprijatii I

  12. Implementation and Analysis for APR1400 Soft Control System

    International Nuclear Information System (INIS)

    2015-01-01

    Due to the rapid advancement of digital technology, the definite technical advantages of digital control system compared to analog control system are accelerating the implementation of advanced distributed digital control system in the nuclear power plant. One of the major advantages of digital control system is the capability of Soft Control System. The design of Soft Control System for Advanced Power Reactor 1400 (APR1400) plant of Man-Machine Interface System (MMIS) is based on full digital technologies to enhance reliability, operability and maintainability. Computer-based compact workstation has been adopted in the APR1400 Main Control Room (MCR) to provide convenient working environment. This paper introduces the approaches and methodologies of Soft Control System for the Advanced Control Room (ACR). This paper also explains major design features for operation and display of the Soft Control System and its implementation to cope with regulatory requirements. (authors)

  13. Development of the APR+ Auxiliary Building General Arrangement (GA)

    International Nuclear Information System (INIS)

    Moon, Hyung Keun; Park, Young Sheop; Kang, Yong Chul

    2011-01-01

    The general arrangement (GA) drawing of a nuclear power plant is the most basic drawing which contains all of the plant equipment, systems, and rooms. Therefore, it should be issued at an early design stage to provide the contours of the overall plant structure. This type of drawing is typically used widely throughout the design stages. The development project of APR+ (Advanced Power Reactor+), as a succeeding model of the APR1400 (Advanced Power Reactor 1400) design, has its own GA that encompasses all of its power buildings. This was developed starting in October of 2009. Among several of the buildings in this design, the Auxiliary Building (AB) is one of the most important buildings to produce electricity, and to protect against undesirable radiation emissions. This paper focuses on the design characteristics of the general arrangement of the AB

  14. Verbal Communication in the APR1400 Advanced Control Room

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Shin, Young Cheol

    2007-01-01

    This paper introduces the characteristics of communication in advanced main controlghd rooms (MCRs) and some observations from a case study performed for APR1400 MCR. In advanced MCRs, operators need not maintain the same communication patterns as they do in conventional ones. For example, a senior reactor operator (SRO) does not have to rely on board operators for information acquisition and can get any information from his/her own workstation. This situation may also bring about new problems in MCRs such as lack of shared situation awareness and collaboration between MCR operators. To cope with these problems, the APR1400 MCR adapts several approaches in design and training for encouraging operators to communicate with each other. This paper introduces the possible changes of communication patterns and the countermeasures in design and training. Some findings from an integrated system validation for Shin Kori Units 3 and 4 are also presented

  15. Preliminary Results Of LOCA Problem For APR1400 Reactor

    International Nuclear Information System (INIS)

    Le Dai Dien; Hoang Minh Giang; Le Thi Thu; Vo Thi Huong; Le Van Hong

    2011-01-01

    Several features of NPP with APR1400 nuclear reactor during a loss of coolant accident (LOCA) are investigated in this study. The report describes some main design characteristics of an engineering safety systems of APR1400 and the thermal hydraulic calculation results for steady-state using MARS and RELAP/SCDAPSIM codes. Large Break LOCA accident has been analyzed and evaluated based on acceptable criteria for ECCS given by US NRC. The results from cold leg break LOCA with broken area of 0.0465 m 2 in case of high pressure safety injection system (HPSI) failed to operate or 2 and 4 HPSI pumps are activated. The preliminary results of this work is a part of collaboration between INST researchers and KAERI experts in using RELAP tool for safety analysis of NPPs. (author)

  16. 967.pdf | 10apr2010 | currsci | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    2010-04-10

    Apr 10, 2010 ... error. The page your are looking for can not be found! Please check the link or use the navigation bar at the top. YouTube; Twitter; Facebook; Blog. Academy News. IAS Logo. 29th Mid-year meeting. Posted on 19 January 2018. The 29th Mid-year meeting of the Academy will be held from 29–30 June 2018 ...

  17. Design features of Advanced Power Reactor (APR) 1400 steam generator

    International Nuclear Information System (INIS)

    Park, Tae-Jung; Park, Jun-Soo; Kim, Moo-Yong

    2004-01-01

    Advanced Power Reactor 1400 (APR 1400) which is to achieve the improvement of the safety and economical efficiency has been developed by Korea Hydro and Nuclear Power Co., Ltd. (KHNP) with the support from industries and research institutes. The steam generator for APR 1400 is an evolutionary type from System 80 + , which is the recirculating U-tube heat exchanger with integral economizer. Compared to the System 80 + steam generator, it is focused on the improved design features, operating and design conditions of APR 1400 steam generator. Especially, from the operation experience of Korean Standard Nuclear Power Plant (KSNP) steam generator, the lessons-learned measures are incorporated to prevent the tube wear caused by flow-induced vibration (FIV). The concepts for the preventive design features against FIV are categorized to two fields; flow distribution and dynamic response characteristics. From the standpoint of flow distribution characteristics, the egg-crate flow distribution plate (EFDP) is installed to prevent the local excessive flow loaded on the most susceptible tube to wear. The parametric study is performed to select the optimum design with the efficient mitigation of local excessive flow. ATHOS3 Mod-01 is used and partly modified to analyze the flow field of the APR 1400 steam generator. In addition, the upper tube bundle support is designed to eliminate the presence of tube with a low natural frequency. Based on the improved upper tube bundle support, the modal analysis is performed and compared with that of System 80 + . Using the results of flow distribution and modal analysis, the two mechanisms of flow-induced vibration are investigated; fluid-elastic instability (FEI) and random turbulence excitation (RTE). (authors)

  18. 897.pdf | apr102004 | currsci | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    Home; currsci; apr102004; 897.pdf. 404! error. The page your are looking for can not be found! Please check the link or use the navigation bar at the top. YouTube; Twitter; Facebook; Blog. Academy News. IAS Logo. 29th Mid-year meeting. Posted on 19 January 2018. The 29th Mid-year meeting of the Academy will be held ...

  19. Pseudomonas syringae evades host Immunity by degrading flagellin monomers with alkaline protease AprA

    OpenAIRE

    Pel, M.J.C.; Van Dijken, A.J.H.; Bardoel, B.W.; Seidl, M.F; Van der Ent, S.; Van Strijp, J.A.G.

    2014-01-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of bacterial species. In addition, we investigated the role of AprA in virulence of the bacterial plant athogen P. syringae pv. tomato DC3000. The AprA-deficient DC3000 ΔaprA knockout mutant was significantl...

  20. La m?taplasie osteoide de l'endom?tre apr?s une grossesse ? terme: ? propos d'un cas rare

    OpenAIRE

    Jayi, Sofia; Bouguern, Hakima; Fatemi, Hind; Chaara, Hikmat; Laamarti, Afaf; Melhouf, Aabdelilah

    2013-01-01

    La m?taplasie ost?o?de de l'endom?tre (MOE) est une entit? rare correspondant ? la pr?sence de tissu osseux dans l'endom?tre, elle est le plus souvent diagnostiqu?e dans un contexte d'infertilit? secondaire faisant suite ? une grossesse interrompue. M?me si plusieurs facteurs de risque sont r?pertori?s, sa physiopathologie reste mal connue et sa traduction clinique est tr?s variable. Nous rapportons un cas de MOE apparu suite ? un curetage pour r?tention placentaire en post-partum. Le diagnos...

  1. Au XXIème siècle, qui sont les patients dialysés souffrant d'une hyperparathyroïdie secondaire sévère ? Cohorte prospective, multicentrique de patients dialysés, incidents pour l'hyperparathyroïdie secondaire. EPHEYL (Etude PHarmacoEpidémiologique de l'hYperparathyroïdie secondaire en Lorraine)

    OpenAIRE

    Thomas-Laurain , Emmanuelle

    2013-01-01

    Non disponible / Not available; L'hyperparathyroïdie secondaire (HPTS) est une complication fréquente de l'insuffisance rénale chronique. Mais son diagnostic et sa prise en charge sont encore complexes et mal codifiés. Dans notre étude, nous faisons l'hypothèse que la population de patients atteints d'HPTS est hétérogène. L'objectif de notre étude était d'identifier des sous-groupes de patients présentant un profil d'HPTS commun à partir des données cliniques, biologiques et thérapeutiques di...

  2. Un système d'aide au traitement des informations de veille stratégique : concepts, méthode et résultats

    NARCIS (Netherlands)

    Rouibah, K.

    2001-01-01

    RÉSUMÉ Cette recherche s¿inscrit dans le cadre du traitement des informations fragmentaires et incertaines (IFI) de veille stratégique. Le traitement des IFI est un problème peu structuré, pour lequel il existe peu de recherches utiles aux dirigeants d¿entreprises. Devenu un axe de recherche assez

  3. Les représentations des métiers des adolescent(e-s) scolarisé(e-s) dans l’enseignement secondaire

    OpenAIRE

    Stevanovic, Biljana; Mosconi, Nicole

    2011-01-01

    À la demande de la Direction de l’animation de la recherche, des études et des statistiques (DARES) du ministère du Travail et des affaires sociales qui a financé et en convention avec l’université Paris X-Nanterre, une étude de la littérature a été élaborée sur les représentations des métiers chez les adolescentes et les adolescents scolarisé(e-s) dans l’enseignement secondaire afin de comprendre pourquoi filles et garçons font des projets professionnels aussi différenciés. L’objectif de cet...

  4. Applications of Qualitative Microanalysis to the Determination of Secondary Species Associated with Uranium; Application de la microanalyse qualitative a la determination des especes secondaires d'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Agrinier, H

    1959-02-01

    Microanalytical techniques are described which allow rapid determinations of secondary species associated with uranium. They consist in exposing the constituent elements of the ores by means of characteristic microchemical reactions. Because of their rapidity and the small amount of apparatus needed, these techniques can be used either in the field or in the laboratory. (author) [French] Les techniques de microanalyse decrites dans cet ouvrage permettent la determination rapide des especes secondaires d'uranium. Elles consistent a mettre en evidence les elements constitutifs des mineraux par des reactions microchimiques caracteristiques. En raison de leur rapidite et du peu de materiel qu'elles necessitent, ces techniques peuvent etre utilisees aussi bien sur le terrain qu'au laboratoire. (auteur)

  5. Appendicite aigue non compliquée: y a-t- il une place pour le traitement conservateur

    Science.gov (United States)

    El Khader, Ahmed; Lahkim, Mohamed; El Barni, Rachid; Achour, Abdessamad

    2015-01-01

    Le but de cette étude a été d’évaluer l'efficacité de l'antibiothérapie seule dans le traitement des appendicites aigues non compliquées. C'est une étude prospective, intéressant 68 patients ayant eu une appendicite aigue simple, de confirmation radiologique, traités par l'amoxicilline associée à l'acide clavulanique pendant 10 jours. L'appendicectomie a été réalisée en cas d'aggravation ou en cas de non amélioration au bout de 48heures de traitement. Le traitement conservateur a été efficace dans 82,35% avec une résolution complète des symptômes chez 56 patients. Les 12 cas restants (17,65%) ont subit une appendicectomie. l'appendicite a été gangréneuse dans 8 cas et phlegmoneuse dans 4 cas. Cinq des 56 patients, qui ont bien évolué sous traitement conservateur, ont été réadmis et opérés pour récidive, soit 8,9%. Deux cas ont eu une appendicite compliquée. L'appendicectomie reste le traitement de référence pour l'appendicite aigue, mais le traitement antibiotique peut être proposé en première intension à des patients présentant une appendicite aigue non compliquée. PMID:26327981

  6. Profils des enfants infectes par le vih en debut du traitement ...

    African Journals Online (AJOL)

    But : Décrire les profils des enfants infectés par le VIH au début du traitement antirétroviral. Matériels et méthode: Les dossiers des enfants infectés par le VIH dans la région maritime ont été analysés de mai 2008 à février 2010 par le comité thérapeutique. Résultats: Parmi les 96 dossiers analysés, 66,67% venaient du ...

  7. Profils des porteurs du VIH/SIDA au début du traitement ...

    African Journals Online (AJOL)

    But : Décrire les profils des porteurs de VIH/sida au début du traitement antirétroviral. Matériels et méthode: Les dossiers des porteurs du VIH/sida de la région maritime ont été analysés de mai 2008 à avril 2009 par le comité thérapeutique. Résultats: Parmi les 641 dossiers analysés, 67,40% venaient du district de Yoto.

  8. Non-Integrated Standalone Tests of APR1400 Simulator

    International Nuclear Information System (INIS)

    Hwang, Su Hyun; Lee, Jeong Ik; Hong, Soon Joon; Lee, Byung Chul; Seo, Jeong Gwan; Lee, Myung Soo

    2007-01-01

    APR1400 being developed for the construction of New Kori 3 and 4 Units has improved safety and more economical efficiency compared with previous PWR. The ESF(Engineered Safety Features) newly introduced to enhance safety are as follows: DVI (Direct Vessel Injection), Fluidic Device, IRWST (In-containment Refueling Water Storage Tank). So the transient pattern of anticipated accidents will show different characteristics from previous PWR. There are multidimensional flow phenomena like as emergency core cooling coolant bypass discharge in the downcomer, downcomer boiling, and different safety injection characteristics due to fluidic device during LBLOCA. Also there is the phenomenon of critical flow due to the open of pressurizer POSRV (Pilot Operated Safety Relief valve) connected to IRWST and safety depressurization system and the prediction of discharge flow is very important. KEPRI is developing APR1400 simulator using RELAP-RT . RELAP-RT was developed by DS and S (Data systems and Solutions) based on RELAP5/MOD3.2. The improved features of RELAP-RT to function as a simulator are as follows: Add simulator functionality - Control by simulator executive - IC snap and reset capability - Back-track snap and reset capability - Fast time capability. Fast time capability(examples) - The rate of condensation has been limited. - Fictional choking model has been developed for internal junctions. - Wall heat transfer coefficients and heat fluxes has been limited. In this study, various NISTs (Non-Integrated Standalone Tests) were performed to verify the capability of RELAP-RT as APR1400 simulator by the comparison with RELAP5/MOD3.3

  9. Design of a Load Following Controller for APR+ Nuclear Plants

    International Nuclear Information System (INIS)

    Lee, Sim Won; Kim, Jae Hwan; Kim, Dong Su; Na, Man Gyun; Yu, Keuk Jong

    2011-01-01

    The load-following operation of an APR+ nuclear plants is required to restrain the adjustment of boric acid concentration and to efficiently control the control rods for the flexibility of the operation. Especially, axial flux distribution disproportion that is usually caused by load-following operation in a reactor core induces xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. Rapid and smooth power maneuvering has its benefits in view of the economical and safe operation of reactors, so it is required that the controller is efficiently designed. Therefore, the load-following operation of an APR+ nuclear plants needs the ultimate automatic control and the advanced control method that satisfies the conditions such as the flexibility, safety and convenience. A model predictive control (MPC) method is applied to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for an APR+ nuclear plants. Some tracking controllers use only the current tracking command. On the other hand, since MPC considers future commands in addition to the current tracking command, the MPC can achieve better tracking performance. Therefore, the MPC has been applied very much to the control of industrial process systems. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the second control input is not implemented and the procedure to solve the optimization problem is then repeated. The power level and the ASI are controlled by the regulating control banks and part-strength control banks together with the automatic adjustment of boric acid concentration. The 3-dimensional MASTER code, which models the APR+ nuclear

  10. Design of a Load Following Controller for APR+ Nuclear Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sim Won; Kim, Jae Hwan; Kim, Dong Su; Na, Man Gyun [Chosun University, Gwnagju (Korea, Republic of); Yu, Keuk Jong [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2011-08-15

    The load-following operation of an APR+ nuclear plants is required to restrain the adjustment of boric acid concentration and to efficiently control the control rods for the flexibility of the operation. Especially, axial flux distribution disproportion that is usually caused by load-following operation in a reactor core induces xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. Rapid and smooth power maneuvering has its benefits in view of the economical and safe operation of reactors, so it is required that the controller is efficiently designed. Therefore, the load-following operation of an APR+ nuclear plants needs the ultimate automatic control and the advanced control method that satisfies the conditions such as the flexibility, safety and convenience. A model predictive control (MPC) method is applied to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for an APR+ nuclear plants. Some tracking controllers use only the current tracking command. On the other hand, since MPC considers future commands in addition to the current tracking command, the MPC can achieve better tracking performance. Therefore, the MPC has been applied very much to the control of industrial process systems. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the second control input is not implemented and the procedure to solve the optimization problem is then repeated. The power level and the ASI are controlled by the regulating control banks and part-strength control banks together with the automatic adjustment of boric acid concentration. The 3-dimensional MASTER code, which models the APR+ nuclear

  11. Quality Control of Concrete Structure For APR1400 Construction

    International Nuclear Information System (INIS)

    Seo, Inseop; Song, Changhak; Kim, Duill

    2012-01-01

    Nuclear structure shall be constructed to protect internal facilities in the normal operation against external accidents such as the radiation shielding, earthquakes and to be leak-proof of radioactive substances to the external environment in case of loss of coolants. containment and auxiliary building of nuclear power plants are built in reinforced concrete structures to maintain these protection functions. Nuclear structures shall be designed to ensure soundness in operation since they are located on the waterfront where is easy do drain the cooling water and so deterioration and damage of concrete structures caused by seawater can occur. Durability is ensured for concrete structures of APR1400, a Korea standard NPP, in compliance with all safety requirements. In particular, owners perform quality control directly on the production and pouring of cast in place concrete for the concrete structure construction to make sure concrete structures established with quality homogeneity and durability. This report is to look into the quality control standard and management status of cast in place concrete for APR1400 construction

  12. Vibration Analysis for Steam Dryer of APR1400 Steam Generator

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sung-heum; Ko, Doyoung [KHNP CRI, Daejeon (Korea, Republic of); Cho, Minki [Doosan Heavy Industry, Changwon (Korea, Republic of)

    2016-10-15

    This paper is related to comprehensive vibration assessment program for APR1400 steam generator internals. According to U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20 (Rev.3, March 2007), we conducted vibration analysis for a steam dryer as the second steam separator of steam generator internals. The vibration analysis was performed at the 100 % power operating condition as the normal operation condition. The random hydraulic loads were calculated by the computational fluid dynamics and the structural responses were predicted by power spectral density analysis for the probabilistic method. In order to meet the recently revised U.S. NRC RG 1.20 Rev.3, the CVAP against the potential adverse flow effects in APR1400 SG internals should be performed. This study conducted the vibration response analysis for the SG steam dryer as the second moisture separator at the 100% power condition, and evaluated the structural integrity. The predicted alternating stress intensities were evaluated to have more than 17.78 times fatigue margin compared to the endurance limit.

  13. Application of Nuclear Application Programs to APR1400 Simulator

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Myeong Soo; Hong, Jin Hyuk

    2012-01-01

    Advanced Power Reactor 1400MWe (APR1400) simulator has been developed and installed at Kori Training Center for operators of ShinKori no.3, 4 nuclear power plant by Korea Hydro and Nuclear Power,s Central Research Institute (KHNP CRI). NAPS (Nuclear Application Programs) is a computerbased system which provides operators with past and real-time information for monitoring and controlling NSSS (Nuclear Steam Supply System), BOP (Balance Of Plant) and Electric system. NAPS consists of several programs such as COLSS (Core Operating Limit Supervisory System), SPADES+ (Safety Parameter Display and Evaluation System), CEA (Control Element Assembly) Application Program, and so on. Each program makes calculations based on its own algorithm and provides information available for operation. In order to use NAPS programs with a simulator even though they are being used in a real plant, they should be modified to add several simulation functions such as reset, snap, run/freeze and backtrack required by ANSI/ANS-3.5 to the original NAPS functionality. On top of that, interfacing programs should be developed for the data communication between respective NAPS programs and simulator sever. The purpose of this paper is to provide the overall architecture of the communication system between NAPS and simulator model, and to describe the method to apply NAPS to APR1400 simulator

  14. Application of Standardized ITAAC to the APR1400 Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Deogji; Kim, Yunho [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Design certification applications (DCAs) submitted pursuant to 10 CFR Part 52 contain two tiers of information, Tier 1 and Tier 2. Tier 1 contains information that is to be certified through rulemaking, and includes the inspections, tests, analyses, and acceptance criteria (ITAAC). Tier 2 contains more detailed information and is the source for information included in Tier1. DC applicants have developed the ITAAC with their own format and contents. This has caused the ineffectiveness of the review process by Nuclear Regulatory Commission (NRC) at the design certification stage. Standardizing the format and content of Tier 1 and ITAAC will achieve greater efficiency and effectiveness for Tier 1 and ITAAC development and NRC review, and for ITAAC implementation and verification. NRC provided the proposed standardized ITAAC for APR1400, and KHNP is considering the application of the proposed ITAAC. The strategy for application of the NRC proposed standardized ITAAC to the APR1400 design certification is now under developing, and a meeting with NRC to review the NRC proposed standardized ITAAC is expected to be held in the near future. In this review process, establishment of industry position on the NRC proposed standardized ITAAC is very important. The support from NEI and US industry is expected to be gained.

  15. Application of Standardized ITAAC to the APR1400 Design Certification

    International Nuclear Information System (INIS)

    Kang, Deogji; Kim, Yunho

    2016-01-01

    Design certification applications (DCAs) submitted pursuant to 10 CFR Part 52 contain two tiers of information, Tier 1 and Tier 2. Tier 1 contains information that is to be certified through rulemaking, and includes the inspections, tests, analyses, and acceptance criteria (ITAAC). Tier 2 contains more detailed information and is the source for information included in Tier1. DC applicants have developed the ITAAC with their own format and contents. This has caused the ineffectiveness of the review process by Nuclear Regulatory Commission (NRC) at the design certification stage. Standardizing the format and content of Tier 1 and ITAAC will achieve greater efficiency and effectiveness for Tier 1 and ITAAC development and NRC review, and for ITAAC implementation and verification. NRC provided the proposed standardized ITAAC for APR1400, and KHNP is considering the application of the proposed ITAAC. The strategy for application of the NRC proposed standardized ITAAC to the APR1400 design certification is now under developing, and a meeting with NRC to review the NRC proposed standardized ITAAC is expected to be held in the near future. In this review process, establishment of industry position on the NRC proposed standardized ITAAC is very important. The support from NEI and US industry is expected to be gained

  16. Calculation of reactivity by digital processing; Calcul de la reactivite par traitement numerique

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-12-01

    With a view to exploring the new possibilities offered by digital techniques, a description is given of the optimum theoretical conditions of a computation of the realtime reactivity using counting samples (obtained from a nuclear reactor). The degree to which these optimum conditions can be attained depends on the complexity of the processing which can be accepted. A compromise thus has to be made between the accuracy required and the simplicity of the equipment carrying out the processing. An example is given, using a relatively simple structure, which gives an idea of the accuracy of the results obtained over a wide range of reactor power. (author) [French] Dans le but d'explorer les possibilites nouvelles des techniques numeriques, on decrit les conditions theoriques optimales d'un calcul de la reactivite en temps reel a partir d'echantillons de comptage (en provenance d'un reacteur nucleaire). Ces conditions optimales peuvent etre approchees d'autant mieux que l'on accepte un traitement plus complexe. Un compromis est donc a faire entre la precision desiree et la simplicite du materiel assurant le traitement. Un exemple adoptant une structure de complexite reduite permet de juger de la precision des resultats obtenus sur une importante plage d'evolution de la puissance. (auteur)

  17. Calculation of reactivity by digital processing; Calcul de la reactivite par traitement numerique

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-12-01

    With a view to exploring the new possibilities offered by digital techniques, a description is given of the optimum theoretical conditions of a computation of the realtime reactivity using counting samples (obtained from a nuclear reactor). The degree to which these optimum conditions can be attained depends on the complexity of the processing which can be accepted. A compromise thus has to be made between the accuracy required and the simplicity of the equipment carrying out the processing. An example is given, using a relatively simple structure, which gives an idea of the accuracy of the results obtained over a wide range of reactor power. (author) [French] Dans le but d'explorer les possibilites nouvelles des techniques numeriques, on decrit les conditions theoriques optimales d'un calcul de la reactivite en temps reel a partir d'echantillons de comptage (en provenance d'un reacteur nucleaire). Ces conditions optimales peuvent etre approchees d'autant mieux que l'on accepte un traitement plus complexe. Un compromis est donc a faire entre la precision desiree et la simplicite du materiel assurant le traitement. Un exemple adoptant une structure de complexite reduite permet de juger de la precision des resultats obtenus sur une importante plage d'evolution de la puissance. (auteur)

  18. Implementasi Automatic Packet Reporting System (APRS) Untuk Paket Data Pemantauan dan PengukuranUntuk Paket Data Pemantauan dan Pengukuran

    OpenAIRE

    Arief Goeritno

    2016-01-01

    Telah dilakukan implementasi Automatic Packet Reporting System (APRS) untuk paket data pemantauan dan pengukuran melalui tujuan penelitian, berupa: a) penyetelan program aplikasi pada jaringan APRS dan b) pengukuran terhadap penerimaan data berdasarkan kinerja sensor-sensor. Penyetelan program aplikasi APRS merupakan konfigurasi perangkat lunak untuk APRS yang akan digunakan pada stasiun penerimaan data APRS dengan program aplikasi yang biasa digunakan, yaitu hyperterminal dan UI-View 32. Pen...

  19. A treatment station for solid radio-active waste at the Saclay nuclear research centre (1962); Station de traitement des dechets radioactifs solides au centre d'etudes nucleaires de Saclay (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E; Lebrun, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    The waste from an atomic centre is very varied in nature, in form, and in activity, going from weakly contaminated laboratory waste to objects actuated in a pile and strongly radioactive. After one year's working of a pilot plant, a factory has been built, in which solide waste is treated and then conditioned in concrete blocks. The present communication describes the treatment and conditioning techniques in this factory which uses to a maximum remotely controlled operation. (authors) [French] Les dechets d'un Centre Atomique sont de natures, de forme et d'activites extremement variees, allant des dechets de laboratoires faiblement contamines, aux dispositifs actives en pile et fortement radioactifs. Apres l'exploitation pendant un an d'une unite pilote, une usine a ete construite dans laquelle les dechets solides sont traites, puis conditionnes en bloc de beton. La presente communication a pour objet la description des techniques de traitement et de conditionnement dans cette usine ou les operations sont au maximum commandees automatiquement et a distance. (auteurs)

  20. Traitement de la margine brute d'huile d'olive par distillation suivi de ...

    African Journals Online (AJOL)

    SARAH

    31 juil. 2014 ... Research on optimization of the distillate and residue are in progress. Keywords: olive oil ... des composés phénoliques de ce distillat avant et après sa ..... Ranalli A. (1991a) the effluent from olive mills: Proposals for re-use ...

  1. Écrire (d’après

    Directory of Open Access Journals (Sweden)

    Denis Saint-Amand

    2009-03-01

    Full Text Available De l’allusion à la citation, de l’emprunt criard au plagiat déguisé, les jeux d’influences et d’aller-retour avec tel ou tel modèle, grand ou mineur, ont toujours participé de l’élaboration du texte littéraire. Si l’intertextualité est sans aucun doute née en même temps que l’écriture (ou quelques minutes après et que, comme ont pu le montrer notamment Jacques-Philippe Saint-Gérand et Daniel Sangsue, les facettes multiples qu’elle déploie ont toujours suscité l’attention des hommes de lettre...

  2. Economic Aspects of Radiation Treatment; Considerations Economiques sur le Traitement par Irradiation; Ehkonomicheskie aspekty obrabotki produktov metodom oblucheniya; Consideraciones Economicas Sobre el Tratamiento por Irradiacion

    Energy Technology Data Exchange (ETDEWEB)

    Leveque, P. [Centre d' Etudes Nucleaires de Saclay (France)

    1966-11-15

    In May 1963, at the Conference held by the International Atomic Energy Agency on the Industrial Uses of Large Radiation Sources, there was considerable discussion of costs. This general exchange of views led to a number of assessments of the cost of treatment by radioactive sources and machines. After three years it seems appropriate to review the basic hypotheses, and in particular to take account of the drop in price: of radioisotopes, especially {sup 137}Cs. This affects the cost both of the installed kW and of the KWh of energy produced. In the light of the experience gained in the past: three years it is possible to define the efficiencies and the load factors observed in plants at present in operation. It is true that in most cases these are treating medical equipment and supplies, but the problems are comparable. (author) [French] En mai 1963, lors de la Conference organisee par l'AIEA sur l'emploi des sources de rayonnements intenses dans l'industrie, un large debat s'etait engage sur les prix de revient. De cette confrontation generale, on a pu tirer quelques evaluations du cout de traitement par sources radioactives et machines. Il est bon, trois ans apres, de revoir les hypotheses de base et surtout de tenir compte de l'abaissement du prix des radioelements et tout specialement du {sup 137}Cs. Ceci influe a la fois sur le prix du kW installe et du kWh d'energie produit. A la lumiere de l'experience acquise pendant ces trois dernieres annees, il est possible de preciser les rendements et facteurs de charge observes dans des installations actuellement en fonctionnement. Il s'agit il est vrai, dans la majorite des cas, de traitements d'accessoires medicaux, mais les problemes sont comparables. (author) [Spanish] En la Conferencia sobre las aplicaciones industriales de las fuentes de radiacion de elevada intensidad, celebrada.en mayo de 1963 bajo los auspicios del OIEA, se inicio un amplio debate sobre los precios de costo. De esta confrontacion general se

  3. Industrial treatment of solutions of fission products. Separation of caesium-137; Traitement industriel de solutions de produits de fission. Separation du cesium-137

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, C; Raggenbass, A [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    Two types of chemical treatment can be considered for the manufacture of solid sources for industrial uses from fission product solutions remaining after plutonium extraction: a) concentration of the solution and preparation of solid sources from the bulk material, without separation, b) separation of one or several fission products from which the sources are made. Examination of the radio-chemical composition of the mixture of fission products that will be available from the Marcoule reactors (G1, G2 and G3) shows that caesium-137 accounts for 30 per cent of the {gamma} energy available immediately after the plutonium separation, 70 per cent two years after and 100 per cent after five years. There is practically no advantage in making sources from bulk fission products, since the separation of caesium-137 is no more complicated and yet it results in a material with more potential uses. The separation of caesium-137 by a method based on the standard phospho-tungstate precipitation method has been considered. Previously, the precipitated caesium phospho-tungstate was dissolved and caesium was recovered from the solution by cation-exchange or by removal of phosphate and tungstate ions by anion-exchange. A study has now been made, of the metathesis of caesium phospho-tungstate to barium phosphate and tungstate by the action of barium hydroxide, the caesium being obtained in solution as the hydroxide. The advantages of this new procedure are: - greater decontamination of caesium-137 without further purification, - possibility of direct transformation to caesium sulphate, - general simplification of the procedure and, consequently, of the equipment. (author) [French] Deux types de traitement chimique peuvent etre envisages pour amener a l'etat de sources solides utilisables industriellement les produits de fission contenus dans les solutions residuaires de l'extraction du plutonium. Ces traitements sont les suivants: a) concentration des solutions et confection de

  4. Industrial treatment of solutions of fission products. Separation of caesium-137; Traitement industriel de solutions de produits de fission. Separation du cesium-137

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, C.; Raggenbass, A. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    Two types of chemical treatment can be considered for the manufacture of solid sources for industrial uses from fission product solutions remaining after plutonium extraction: a) concentration of the solution and preparation of solid sources from the bulk material, without separation, b) separation of one or several fission products from which the sources are made. Examination of the radio-chemical composition of the mixture of fission products that will be available from the Marcoule reactors (G1, G2 and G3) shows that caesium-137 accounts for 30 per cent of the {gamma} energy available immediately after the plutonium separation, 70 per cent two years after and 100 per cent after five years. There is practically no advantage in making sources from bulk fission products, since the separation of caesium-137 is no more complicated and yet it results in a material with more potential uses. The separation of caesium-137 by a method based on the standard phospho-tungstate precipitation method has been considered. Previously, the precipitated caesium phospho-tungstate was dissolved and caesium was recovered from the solution by cation-exchange or by removal of phosphate and tungstate ions by anion-exchange. A study has now been made, of the metathesis of caesium phospho-tungstate to barium phosphate and tungstate by the action of barium hydroxide, the caesium being obtained in solution as the hydroxide. The advantages of this new procedure are: - greater decontamination of caesium-137 without further purification, - possibility of direct transformation to caesium sulphate, - general simplification of the procedure and, consequently, of the equipment. (author) [French] Deux types de traitement chimique peuvent etre envisages pour amener a l'etat de sources solides utilisables industriellement les produits de fission contenus dans les solutions residuaires de l'extraction du plutonium. Ces traitements sont les suivants: a) concentration des solutions et

  5. Analysis of Turbine Load Rejection for APR1400 using SPACE

    International Nuclear Information System (INIS)

    Kim, Sang Jin; Park, Chan Eok; Choi, Jong Ho; Lee, Gyu Cheon

    2016-01-01

    Turbine Load Rejection event is one of the Performance Related Design Basis Event (PRDBE) that can be stabilized using plant control systems without any safety system actuation. The initiation of the event is turbine load rejection from 100% to 5% in 0.019 seconds. The NSSS control systems of APR1400 is composed of the Power Control System (PCS) and the Process-Component Control System (P-CCS). The PCS includes Reactor Regulating System (RRS), Reactor Power Cutback System (RPCS) and Digital Rod Control System (DRCS). The P-CCS includes the Pressurizer Pressure Control System (PPCS), the Pressurizer Level Control System (PLCS), the Feedwater Control System (FWCS) and the Steam Bypass Control System (SBCS). Turbine load rejection results in the increase of secondary pressure due to sudden blocking of steam flow to turbine. Then the Reactor Coolant System (RCS) cooling through steam generators is decreased rapidly and the RCS temperature will be increased. Turbine load rejection is a typical event to test NSSS control systems since it requires the automatic response of all major NSSS control systems. It is shown that the NSSS control systems of APR1400 have the capability to stabilize the plant without any safety system actuation for turbine load rejection event. This analysis results show that SPACE code has the capability to analyze the turbine load rejection event. However, further validation is necessary for other PRDBEs such as Two Main Feedwater Pumps Trip, Turbine Load Step Change and Turbine Load Ramp Down (5%/min) to verify the capability of SPACE for the full range of performance analyses

  6. Analysis of Turbine Load Rejection for APR1400 using SPACE

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Jin; Park, Chan Eok; Choi, Jong Ho; Lee, Gyu Cheon [KEPCO Engineering and Construction Co. Ltd., Deajeon (Korea, Republic of)

    2016-10-15

    Turbine Load Rejection event is one of the Performance Related Design Basis Event (PRDBE) that can be stabilized using plant control systems without any safety system actuation. The initiation of the event is turbine load rejection from 100% to 5% in 0.019 seconds. The NSSS control systems of APR1400 is composed of the Power Control System (PCS) and the Process-Component Control System (P-CCS). The PCS includes Reactor Regulating System (RRS), Reactor Power Cutback System (RPCS) and Digital Rod Control System (DRCS). The P-CCS includes the Pressurizer Pressure Control System (PPCS), the Pressurizer Level Control System (PLCS), the Feedwater Control System (FWCS) and the Steam Bypass Control System (SBCS). Turbine load rejection results in the increase of secondary pressure due to sudden blocking of steam flow to turbine. Then the Reactor Coolant System (RCS) cooling through steam generators is decreased rapidly and the RCS temperature will be increased. Turbine load rejection is a typical event to test NSSS control systems since it requires the automatic response of all major NSSS control systems. It is shown that the NSSS control systems of APR1400 have the capability to stabilize the plant without any safety system actuation for turbine load rejection event. This analysis results show that SPACE code has the capability to analyze the turbine load rejection event. However, further validation is necessary for other PRDBEs such as Two Main Feedwater Pumps Trip, Turbine Load Step Change and Turbine Load Ramp Down (5%/min) to verify the capability of SPACE for the full range of performance analyses.

  7. Le recours aux modeles dans l'enseignement de la biologie au secondaire : Conceptions d'enseignantes et d'enseignants et modes d'utilisation

    Science.gov (United States)

    Varlet, Madeleine

    Le recours aux modeles et a la modelisation est mentionne dans la documentation scientifique comme un moyen de favoriser la mise en oeuvre de pratiques d'enseignement-apprentissage constructivistes pour pallier les difficultes d'apprentissage en sciences. L'etude prealable du rapport des enseignantes et des enseignants aux modeles et a la modelisation est alors pertinente pour comprendre leurs pratiques d'enseignement et identifier des elements dont la prise en compte dans les formations initiale et disciplinaire peut contribuer au developpement d'un enseignement constructiviste des sciences. Plusieurs recherches ont porte sur ces conceptions sans faire de distinction selon les matieres enseignees, telles la physique, la chimie ou la biologie, alors que les modeles ne sont pas forcement utilises ou compris de la meme maniere dans ces differentes disciplines. Notre recherche s'est interessee aux conceptions d'enseignantes et d'enseignants de biologie au secondaire au sujet des modeles scientifiques, de quelques formes de representations de ces modeles ainsi que de leurs modes d'utilisation en classe. Les resultats, que nous avons obtenus au moyen d'une serie d'entrevues semi-dirigees, indiquent que globalement leurs conceptions au sujet des modeles sont compatibles avec celle scientifiquement admise, mais varient quant aux formes de representations des modeles. L'examen de ces conceptions temoigne d'une connaissance limitee des modeles et variable selon la matiere enseignee. Le niveau d'etudes, la formation prealable, l'experience en enseignement et un possible cloisonnement des matieres pourraient expliquer les differentes conceptions identifiees. En outre, des difficultes temporelles, conceptuelles et techniques peuvent freiner leurs tentatives de modelisation avec les eleves. Toutefois, nos resultats accreditent l'hypothese que les conceptions des enseignantes et des enseignants eux-memes au sujet des modeles, de leurs formes de representation et de leur approche

  8. Traitement statistique des distorsions non-linéaires pour la restauration des enregistrements sonores.

    OpenAIRE

    Picard , Guillaume

    2006-01-01

    L'objet de la thèse est l'étude, la modélisation et le traitement des distorsions non linéaires sonores, pour lesquelles les techniques actuelles s'avèrent impuissantes. L'approche retenue consiste à représenter, globalement, à la fois le signal audio à restaurer et le processus de distorsion, dans le cadre d'un modèle statistique. Cette approche présente un bon compromis entre une souhaitable généricité -possibilité de traiter à l'aide d'une méthode globale plusieurs types de distorsions- et...

  9. Le traitement de l’idéologie dans la sociologie de Luc Boltanski

    Directory of Open Access Journals (Sweden)

    David Vrydaghs

    2006-10-01

    Full Text Available IntroductionLe concept d’idéologie apparaît dans la sociologie de Luc Boltanski à partir du Nouvel Esprit du capitalisme, publié en 1999. L’auteur y revient dans La Condition fœtale, paru en 2004. On aurait donc pu se contenter de ces ouvrages pour examiner le traitement réservé à l’idéologie dans la sociologie de Luc Boltanski. On préférera pourtant revenir aux travaux antérieurs du sociologue, et ce pour deux raisons.D’abord parce que le concept d’idéologie tel qu’il est employé dans Le Nou...

  10. Pseudomonas syringae evades host immunity by degrading flagellin monomers with alkaline protease AprA

    NARCIS (Netherlands)

    Pel, Michiel J C; van Dijken, Anja J H; Bardoel, Bart W; Seidl, Michael F; van der Ent, Sjoerd; van Strijp, Jos A G; Pieterse, Corné M J

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of

  11. Pseudomonas syringae evades host Immunity by degrading flagellin monomers with alkaline protease AprA

    NARCIS (Netherlands)

    Pel, M.J.C.; Van Dijken, A.J.H.; Bardoel, B.W.; Seidl, M.F; Van der Ent, S.; Van Strijp, J.A.G.

    2014-01-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of

  12. 48 CFR 1552.235-76 - Treatment of Confidential Business Information (APR 1996).

    Science.gov (United States)

    2010-10-01

    ... Business Information (APR 1996). 1552.235-76 Section 1552.235-76 Federal Acquisition Regulations System... Provisions and Clauses 1552.235-76 Treatment of Confidential Business Information (APR 1996). As prescribed in 1535.007-70(c), insert the following clause: Treatment of Confidential Business Information (TSCA...

  13. A Probability Analysis of the Generating Cost for EU-APR1400 Single Unit

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Gak Hyeon; Kim, Sung Hwan [KHNP CRI, Seoul (Korea, Republic of)

    2014-10-15

    The nuclear power plant market is expected to grow rapidly in order to address issues of global warming, reducing CO{sub 2} emissions and securing stable electricity supplies. Under these circumstances, the main primary goal of the EU-APR100 development is to ensure export competitiveness in the European countries. To this end, EU-APR1400 have been developed based one te APR1400 (Advanced Power Reactor, GEN Type) The EU-APR1400 adds many advanced design features to its predecessor, as outlined below in Table 1. In this simulation, the results of the generating cost of the EU-APR1400 single unit were determined using the probability cost analysis technique, the generating cost range was shown to be 56.16 ∼ 70.92 won/kWh.

  14. A Probability Analysis of the Generating Cost for EU-APR1400 Single Unit

    International Nuclear Information System (INIS)

    Ha, Gak Hyeon; Kim, Sung Hwan

    2014-01-01

    The nuclear power plant market is expected to grow rapidly in order to address issues of global warming, reducing CO 2 emissions and securing stable electricity supplies. Under these circumstances, the main primary goal of the EU-APR100 development is to ensure export competitiveness in the European countries. To this end, EU-APR1400 have been developed based one te APR1400 (Advanced Power Reactor, GEN Type) The EU-APR1400 adds many advanced design features to its predecessor, as outlined below in Table 1. In this simulation, the results of the generating cost of the EU-APR1400 single unit were determined using the probability cost analysis technique, the generating cost range was shown to be 56.16 ∼ 70.92 won/kWh.

  15. État des connaissances sur le traitement thermique des produits lourds State of the Art of the Thermal Treatment of Heavy Products

    Directory of Open Access Journals (Sweden)

    Blouri B.

    2006-11-01

    Full Text Available Après rappel du traitement thermique des hydrocarbures comme un moyen de viscoréduction des charges lourdes, craquage en oléfines gazeuses, ou pyrolyse totale en gaz de synthèse, le mécanisme réactionnel de vapocraquage des produits lourds constitue la première partie de l'article. Le craquage des huiles lourdes s'effectue selon un mécanisme radicalaire, tandis que les dépôts de carbone sont formés par des réactions de cycloadditions et polycondensations à des températures moyennes et par l'intermédiaire des radicaux à haute température. L'étude expérimentale du craquage thermique du n-tétracosane, du méthyl-6 eicosane et du dodécylbenzène constitue la deuxième partie de l'article et elle met en évidence, grâce à un mécanisme réactionnel du type moléculaire, la possibilité de craquage contrôlé d'une isoparaffine ou d'un hydrocarbure aromatique lourd en hydrocarbure liquide plus léger. After reviewing the thermal treatment of hydrocarbons as a way of visbreaking heavy feedstock, cracking them into gaseous olefins, or totally pyrolyzing them into synthetic gas, the first part of this article describes the reac-tion mechanism of the steam cracking of heavy products. Heavy oils are cracked by a radical mechanism, while carbon deposits are formed by cycloaddition and polycondensation reactions at mean temperatures and by the intermediary of radicals at high temperature. An experimental investigation of the thermal cracking of n-tetracosane, 6-methyleicosane and dodecylbenzene makes up the second part of the article. A reaction mechanism of the molecular type is used to describe the possibility of the controlled cracking of an isoparaffin or of a heavy aromatic hydrocarbon into a lighter liquid hydrocarbon.

  16. The trauma registry compared to All Patient Refined Diagnosis Groups (APR-DRG).

    Science.gov (United States)

    Hackworth, Jodi; Askegard-Giesmann, Johanna; Rouse, Thomas; Benneyworth, Brian

    2017-05-01

    Literature has shown there are significant differences between administrative databases and clinical registry data. Our objective was to compare the identification of trauma patients using All Patient Refined Diagnosis Related Groups (APR-DRG) as compared to the Trauma Registry and estimate the effects of those discrepancies on utilization. Admitted pediatric patients from 1/2012-12/2013 were abstracted from the trauma registry. The patients were linked to corresponding administrative data using the Pediatric Health Information System database at a single children's hospital. APR-DRGs referencing trauma were used to identify trauma patients. We compared variables related to utilization and diagnosis to determine the level of agreement between the two datasets. There were 1942 trauma registry patients and 980 administrative records identified with trauma-specific APR-DRG during the study period. Forty-two percent (816/1942) of registry records had an associated trauma-specific APR-DRG; 69% of registry patients requiring ICU care had trauma APR-DRGs; 73% of registry patients with head injuries had trauma APR-DRGs. Only 21% of registry patients requiring surgical management had associated trauma APR-DRGs, and 12.5% of simple fractures had associated trauma APR-DRGs. APR-DRGs appeared to only capture a fraction of the entire trauma population and it tends to be the more severely ill patients. As a result, the administrative data was not able to accurately answer hospital or operating room utilization as well as specific information on diagnosis categories regarding trauma patients. APR-DRG administrative data should not be used as the only data source for evaluating the needs of a trauma program. Copyright © 2016 Elsevier Ltd. All rights reserved.

  17. Utilisation de données secondaires et signature scientifique lors de l'évaluation d'une intervention en santé mondiale

    Directory of Open Access Journals (Sweden)

    Valéry Ridde

    2018-03-01

    Full Text Available Dans le domaine de la santé mondiale, les bailleurs de fonds internationaux financent de nombreuses interventions dont ils souhaitent l'efficacité. Ils financent ainsi parfois des évaluations externes, le plus souvent menées par des chercheurs du Nord, pour en faire la démonstration. En outre, il existe de multiples bases de données, souvent collectées par les chercheurs du Sud, utiles pour réaliser ce type d'études. Mais cette multiplicité d'acteurs, de collaboration, d'enjeux et de potentiels conflits d'intérêts pose des défis importants sur le plan de l'utilisation de données secondaires et de la signature scientifiques des publications qui peuvent en découler. Cette étude de cas propose une réflexion à cet égard.

  18. Development of Core Simulator (CoSi) for APR1400 And Analysis of LPPT Result using APR1400-CoSi

    International Nuclear Information System (INIS)

    Moon, Sang-Rae; Kim, Yong-Bae; Lee, Eun-Ki

    2014-01-01

    According to NRC guidelines, Low Power Physics Test (LPPT) is required to be performed in low temperature/low pressure (160 .deg. C/42.2 kg/cm 2 ) as well as NOT/NOP (291.3 .deg. C/158.2 kg/cm 2 ) because Shin-Kori Unit 3 is FOAK nuclear power plant. Low Power Physics Test (LPPT) is essential to verify the nuclear design and robustness of reactor safety. LPPT consists of initial criticality, Point of Adding Heat (POAH), All Rod Out (ARO) Boron Concentration, Isothermal Temperature Coefficient (ITC), Control Rod Worth measurements and so on. KHNP-CRI has developed the Core Simulator for APR1400 (APR1400-CoSi) in order to improve the ability performing the LPPT. Especially, APR1400-CoSi has enhanced capability to calculate the full Core neutronic parameters by revising RAST-K that is three dimensional real time core kinetic program. APR1400-CoSi has been developed for education-training of Low Power Physics Test(LPPT). Particularly, APR1400-CoSi has an enhanced capability to calculate the full core neutronic parameters by revising RAST-K which is a three dimensional real time core kinetics program. Low Power Physics Test (LPPT) was performed using APR1400-CoSi and the results showed very similar values with the predicted ones. In other words, the initial core model of Shin-Kori Unit 3 in APR1400-CoSi system has been verified to be appropriate enough. Also, it was confirmed that the test range of Low Power Physics Test (LPPT) reamains effective even though the largest incremental bank reactivity is inserted in core by analyzing the power change during the rod SWAP test

  19. le traitement chirurgical des poches de rétraction tympaniques

    African Journals Online (AJOL)

    16 juin 2006 ... L'évolution naturelle de l'otite atelectasique vers la maladie cholestéatomateuse complique d'avantage la prise en charge des poches de rétraction. ... risque de cholestéatome résiduel était important. Après un recul minimum de 21 mois, le résultat anato- mique été satisfaisant dans 88%. Ailleurs ...

  20. Analysis on Containment Response Following a LBLOCA of APR1400

    International Nuclear Information System (INIS)

    Han, Kyu Hyun

    2016-01-01

    The predictions are in good agreements with the final safety analysis report, which implies the containment integrity is maintained during or after an accident like loss of coolant accident. In this study, the CONTEMPT-LT/028 was used to calculate the pressure and temperature, and in the follow-up study, CONTAIN 2.0 will be used for the pressure and temperature predictions in APR1400 reactors. Shin-Hanul Units 1 and 2 may possess different characteristics of peak pressure and temperature in containment following a large break loss-of-coolant-accident. To assess the important performance independently and to compare with prediction results presented in the final safety analysis report (FSAR) of Shin-Hanul Units 1 and 2 might be helpful to regulatory review for identifying validity of the FSAR. The end of blowdown (EOB) time during a LOCA could largely affect the peak pressure and temperature in the containment. This paper provides CONTEMPT-LT/028 prediction of the peak pressure and temperature of Shin-Hanul Units 1 and 2 following a large break loss-of-coolant-accident and compares with licensee's prediction results.

  1. Analysis on Containment Response Following a LBLOCA of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kyu Hyun [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    The predictions are in good agreements with the final safety analysis report, which implies the containment integrity is maintained during or after an accident like loss of coolant accident. In this study, the CONTEMPT-LT/028 was used to calculate the pressure and temperature, and in the follow-up study, CONTAIN 2.0 will be used for the pressure and temperature predictions in APR1400 reactors. Shin-Hanul Units 1 and 2 may possess different characteristics of peak pressure and temperature in containment following a large break loss-of-coolant-accident. To assess the important performance independently and to compare with prediction results presented in the final safety analysis report (FSAR) of Shin-Hanul Units 1 and 2 might be helpful to regulatory review for identifying validity of the FSAR. The end of blowdown (EOB) time during a LOCA could largely affect the peak pressure and temperature in the containment. This paper provides CONTEMPT-LT/028 prediction of the peak pressure and temperature of Shin-Hanul Units 1 and 2 following a large break loss-of-coolant-accident and compares with licensee's prediction results.

  2. Verification of SAMG entry condition for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Junghyun; Kim, Taewan; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    In the wake of the Fukushima accident, severe accident management has become important more than ever. While Emergency Operating Procedures (EOPs) focuses on cooling down the core during a design basis accident, the prime objective of severe accident management guideline (SAMG) is to prevent the release of radioactive material into the environment during a severe accident. Only one fixed value of core exit temperature (CET) has been applied for several decades to different types of nuclear power plants (NPPs) in Korea. Although the different types of NPPs have different cladding materials and system designs, the identical CET, i. e., 650 .deg. C, is applied as the entry condition to the SAMG of all the NPPs (except CANDU plants), i. e., Westinghouse type, OPR1000, and APR1400. In this paper, the transition point is re-evaluated for dominant severe accident sequences; station black-out (SBO), small break loss of coolant accident (SBLOCA), and me dium break loss of coolant accident (MBLOCA). In cases of SBO and SBLOCA, the current SAMG entry condition seems proper, while it needs to be reconsidered for MBLOCA case.

  3. Aircraft Impact Assessment of APR1400 Reactor Containment Building

    International Nuclear Information System (INIS)

    Moon, Il Hwan; Kim, Do Yeon; Kim, Jae Hee; Kim, Sang Yun

    2011-01-01

    The implementation of a protection to withstand aircraft impact on safety-related structures and systems is basically based on a probabilistic evaluation for each site, if the licensing body doesn't require a deterministic approach. Existing nuclear power plants in Korea were designed based on the probabilistic approach, and the aircraft impact hazard remained less than a probability of 10 -7 . However, a man-made aircraft impact have been considered as a possible external accident for the nuclear power plant. New plant designs that are to be constructed in the U.S. after July 2009 must consider the effect of impact from a large commercial aircraft according to the requirements of 10 CFR 50.150. Especially, Reactor Containment Building (RCB) housing the safety-related equipment and fuels should be protected safely against aircraft crash without perforation and scabbing failure of external wall. APR1400 RCB is constructed as a prestressed concrete containment vessel (PCCV) which is surrounded by the auxiliary building housing additional safety-related equipment and other systems. In this study, the aircraft impact analyses for the RCB are carried out using Riera forcing function and aircraft model. Considered external wall thickness is 4 ft 6 in. for the cylindrical wall and 4 ft for the dome. Actual strengths of concrete and steel are considered as the material properties. For these analyses, the dynamic increment factor and concrete aging effect are considered in accordance with NEI 07-13(2011)

  4. Résultats positifs de traitements de prévention de venues d'eau en Russie Successful Application Cases of Water Control Treatments in Russia

    Directory of Open Access Journals (Sweden)

    Kolher N.

    2006-11-01

    'hydrocarbures. Les résultats de quelques traitements de puits réalisés en Russie en 1993 sont présentés ci-après dans cet article. Water encroachment in oil or gas producing wells is generally responsible for both a rapid productivity decline and an increase in operating costs caused by the handling and treating of large quantities of water. It also induces some secondary problems such as fines or sand production, corrosion and scale deposits. The result is often a premature shut-in of these wells because production has become uneconomic. To face these problems and to extend the lifetime of the wells, some companies have tried to inject cements, resins or either organic or inorganic strong gels into the water producing intervals. These impermeable barriers, which require zone isolation for their placement, aim to stop the flow of all fluids. These treatments are nevertheless very risky if the oil and water bearing zones are not easily distinguishable or if the completion of the candidate well does not allow zone isolation. To overcome these problems studies were performed since 1984 in IFP's lab in order to develop systems able to reduce selectively water production without affecting in a great extent the flow of hydrocarbons. These systems are based on the use of either single highmolecular-weight water soluble polymers or of weak gels obtained from these polymers in the presence of some X-linking additives. Several processes have been developed, each of them adapted to the specific reservoir characteristics of bottom-hole temperature and produced brine salinity. All these processes have the advantage to reduce selectively the permeability to brine while maintaining or even improving the production of hydrocarbons. This paper presents the results of some well tests conducted in Russia in 1993.

  5. 48 CFR 1552.235-75 - Access to Toxic Substances Control Act Confidential Business Information (APR 1996).

    Science.gov (United States)

    2010-10-01

    ... Control Act Confidential Business Information (APR 1996). 1552.235-75 Section 1552.235-75 Federal... Confidential Business Information (APR 1996). As prescribed in 1535.007(b), insert the following provision: Access to Toxic Substances Control Act Confidential Business Information (APR 1996) In order to perform...

  6. Study on Maintenance Personnel Development Plan For The Exported APR1400 Commissioning

    International Nuclear Information System (INIS)

    Cho, Sungbae; Kim, Jongdae; Jun, Hokwang; Hwang, Inok; Kang, Jaeyuel

    2012-01-01

    This paper indicates ways to develop maintenance personnel for the exported APR1400 commissioning. The exported APR1400 has not been experienced ay maintenance yet, and requirements for maintenance personnel have not been clarified yet. Based on sound maintenance experience, KEPCO Plant Service and Engineering Company (KEPCO KPS) has studied on maintenance training and career requirement to establish a development plan of the maintenance personnel for the exported nuclear power plant. By defining manpower and training requirement, and mobilization plan, we expect to secure reliability of the exported APR1400

  7. Development of LBB Piping Evaluation Diagram for APR 1000 Main Steam Line Piping

    International Nuclear Information System (INIS)

    Yang, J. S.; Jeong, I. L.; Park, C. Y.; Bai, S. Y.

    2010-01-01

    This paper presents the piping evaluation diagram (PED) to assess the applicability of Leak-Before- Break(LBB) for APR 1000 main steam line piping. LBB-PED of APR 1000 main steam line piping is independent of its piping geometry and has a function of the loads applied in piping system. Also, in order to evaluate LBB applicability during construction process with only the comparative evaluation of material properties between actually used and expected, the expected changes of material properties are considered in the LBB-PED. The LBB-PED, therefore, can be used for quick LBB evaluation of APR 1000 main steam line piping of both design and construction

  8. Fuel assembly design for APR1400 with low CBC

    Energy Technology Data Exchange (ETDEWEB)

    Hah, Chang Joo, E-mail: changhah@kings.ac.kr [Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-04-29

    APR 1400 is a PWR (Pressurized Water Reactor) with rated power of 3983 MWth and 241 assemblies. Recently, demand for extremely longer cycle up to 24 months is increasing with challenge of higher critical boron concentration (CBC). In this paper, assembly design method of selecting Gd-rods is introduced to reduce CBC. The purpose of the method is to lower the critical boron concentration of the preliminary core loading pattern (PLP), and consequently to achieve more negative or less positive moderator temperature coefficient (MTC). In this method, both the ratio of the number of low-Gd rod to the number of high-Gd rod (r) and assembly average Gd wt% (w) are the decision variables. The target function is the amount of soluble boron concentration reduction, which can be converted to Δk{sub TARGET}. A set of new designed fuel assembly satisfies an objective function, min [f=∑{sub i}(Δk{sub FA}−Δk{sub i})], and enables a final loading pattern to reach a target CBC. The constraints required to determine a set of Δk are physically realizable pair, (r,w), and the sum of Δk of new designed assemblies as close to Δk{sub TARGET} as possible. New Gd-bearing assemblies selected based on valid pairs of (r,w) are replaced with existing assemblies in a PLP. This design methodology is applied to Shin-Kori Unit 3 Cycle 1 used as a reference model. CASMO-3/MASTER code is used for depletion calculation. CASMO-3/MASTER calculations with new designed assemblies produce lower CBC than the expected CBC, proving that the proposed method works successful.

  9. Le domaine des co-infections et des maladies concomitantes du Réseau canadien pour les essais VIH des IRSC : lignes directrices canadiennes pour la prise en charge et le traitement de la co-infection par le VIH et l’hépatite C chez les adultes

    Science.gov (United States)

    Hull, Mark; Giguère, Pierre; Klein, Marina; Shafran, Stephen; Tseng, Alice; Côté, Pierre; Poliquin, Marc; Cooper, Curtis

    2014-01-01

    HISTORIQUE : De 20 % à 30 % des Canadiens qui vivent avec le VIH sont co-infectés par le virus de l’hépatite C (VHC), lequel est responsable d’une morbidité et d’une mortalité importantes. La prise en charge du VIH et du VHC est plus complexe en raison de l’évolution accélérée de la maladie hépatique, du choix et des critères d’initiation de la thérapie antirétrovirale et du traitement anti-VHC, de la prise en charge de la santé mentale et des toxicomanies, des obstacles socioéconomiques et des interactions entre les nouvelles thérapies antivirales à action directe du VHC et les antirétroviraux OBJECTIF : Élaborer des normes nationales de prise en charge des adultes co-infectés par le VHC et le VIH dans le contexte canadien. MÉTHODOLOGIE : Le Réseau canadien pour les essais VIH des Instituts de recherche en santé du Canada a réuni un groupe d’experts possédant des compétences cliniques en co-infection par le VIH et le VHC pour réviser les publications à jour ainsi que les lignes directrices et les protocoles en place. Après une vaste sollicitation afin d’obtenir des points de vue, le groupe de travail a approuvé des recommandations consensuelles, qu’il a caractérisées au moyen d’une échelle de qualité des preuves fondée sur la classe (bienfaits par rapport aux préjudices) et sur la catégorie (degré de certitude). RÉSULTATS : Toutes les personnes co-infectées par le VIH et le VHC devraient subir une évaluation en vue de recevoir un traitement du VHC. Les personnes qui ne sont pas en mesure d’entreprendre un traitement du VHC devraient être soignées pour le VIH afin de ralentir l’évolution de la maladie hépatique. La norme de traitement du VHC de génotype 1 est un régime comprenant de l’interféron pégylé et de la ribavirine dosée en fonction du poids, associés à un inhibiteur de la protéase du VHC. Pour les génotypes 2 ou 3, une bithérapie classique est recommandée pendant 24 semaines s

  10. GPM GROUND VALIDATION AIRBORNE SECOND GENERATION PRECIPITATION RADAR (APR-2) GCPEX V1

    Data.gov (United States)

    National Aeronautics and Space Administration — The GPM Ground Validation Airborne Second Generation Precipitation Radar (APR-2) GCPEx dataset was collected during the GPM Cold-season Precipitation Experiment...

  11. GPM GROUND VALIDATION AIRBORNE SECOND GENERATION PRECIPITATION RADAR (APR-2) GCPEX V1

    Data.gov (United States)

    National Aeronautics and Space Administration — The Second Generation Airborne Precipitation Radar (APR-2) is a dual-frequency (13 GHz and 35 GHz), Doppler, dual-polarization radar system. It has a downward...

  12. Current status of integrated HFE V and V system of APR1400

    International Nuclear Information System (INIS)

    Lee, M. S.; Hong, J. H.; Lee, S. H.; Lee, Y. K.

    2006-01-01

    The first Advanced Light Water Reactor called Advanced Power Reactor (APR1400) has many specific features such as passive safety features, digital I and C, and digitalized main control room design. This digital-based neo-concept main control room design needs comprehensive verification and validation process to get the license for construction. An integrated system for APR1400 MMIS design validation is under development by KEPRI with the participating of KHNP. The facility which is based on the NUREG/CR-6393 and ANS3.5 can simulate all of the dynamic functions and responses of APR1400, and measure the human factors by using conventional subject methods and measuring the operator's biological signals. This system will be used in human factors V and V process of the PRM (NUREG0711) of APR1400 MMIS design. (authors)

  13. Treatment and final conditioning of solid radioactive wastes; Traitement et conditionnement definitif des dechets radioactifs solides

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The storage of solid radioactive wastes on a site is so cumbersome and dangerous that we have developed a method of treatment and conditioning by means of which the volume of waste is considerably reduced and very long-lasting shielding can be provided. This paper describes the techniques adopted at Saclay, where the wastes are sheared, compressed and enveloped in concrete of variable thickness. The main part of the report is devoted to a description of the corresponding remote handling installation. (author) [French] L'encombrement et le danger que presentent sur un site le stockage de dechets radioactifs solides nous ont amenes a etudier un mode de traitement et de conditionnement permettant une sensible reduction du volume des dechets et une protection de tres longue duree. La presente communication expose les techniques adoptees a Saclay ou les dechets sont cisailles, comprimes et enrobes dans du beton d'epaisseur variable. La description de l'installation telecommandee correspondante fait l'objet principal de cette communication. (auteur)

  14. Exigences réglementaires et recommandations concernant le traitement de l'eau vis-à-vis des agents pathogènes en entrée et en sortie d'écloseries conchylicoles

    OpenAIRE

    Bonvarlet, Florence

    2011-01-01

    Ce document présente les exigences réglementaires et recommandations relatives aux différents traitement de l'eau en entrée et en sortie d'écloseries conchylicoles. Afin de respecter cette réglementation des solutions, des méthodes de traitement y sont mentionnées.

  15. Evaluation of late effects, esthetic results and quality of life after conservative treatment of breast cancer?; Evaluation des effets tardifs, du resultat esthetique et de la qualite de vie apres traitement conservateur du cancer du sein

    Energy Technology Data Exchange (ETDEWEB)

    Geffrelot, J.; Toudic-Emily, F.; Delozier, T.; Switsers, O.; Allouache, D.; Delcambre, C.; Segura, C.; Levy, C.; Dupont, M.; Joly, F. [Centre Francois-Baclesse, 14 - Caen (France)

    2009-10-15

    Purpose: to evaluate the delayed toxicity of two patterns of adjuvant radiotherapy including a breast irradiation, at the dose of 48 Gy in 20 seances and five weeks or 57.60 Gy in 24 seances and six weeks in case of majored factors of local recurrence risk. The secondary objective were the auto evaluation by the patient of the esthetic result and the influence of this last one on the quality of life. Conclusion: the delayed toxicity was dominated by the fibrosis low to moderated one, without any significant difference between the doses of 48 Gy and 57.60 Gy. The esthetic result evaluated by the patient, globally good, seemed however, damaged with the last pattern. A bad esthetic result, without affected the global quality of life was associated to more specific breast symptoms and damaged the perception of the body image. (N.C.)

  16. Gated blood-pool SPECT assessment of Wolff-Parkinson-White syndromes before and after radiofrequency ablation of accessory pathways; Evaluation fonctionnelle par tomographie cavitaire du syndrome de Wolff-Parkinson-White, avant et apres traitement par radiofrequence

    Energy Technology Data Exchange (ETDEWEB)

    Bontemps, L.; Ben Brahim, H.; Kraiem, T.; Chevalier, P.; Kirkorian, G.; Touboul, P.; Itti, R. [Hopital Cardiologique de Lyon, 69 (France)

    1997-08-01

    Radiofrequency (RF) ablation of accessory pathways in Wolff-Parkinson-White (WPW) syndrome is supposed to be less aggressive than fulguration while providing excellent results. The aims of our study were therefore the evaluation of the functional results of this therapy in terms of left or right ejection fractions and its effects on the contraction synchronism between both ventricular chambers, derived from bi-ventricular Fourier phase histograms. A consecutive series of 44 patients has been investigated within 48 hours before and after RF therapy: 14 patients had right sided WPW and 30 patients left sided WPW. Only patients for whom RF treatment was considered as a success have been included in the study. Gated blood pool tomography has been performed in order to localize the site of pre-excitation and to build-up the phase histograms for both ventricles, and planar gated imaging has been used for right and left ejection fraction determination. Functional results demonstrate the absence of deleterious effect of RF on ventricular contraction and rather a slight increase of ejection fractions, with a more statistically significant difference for left WPW (LVEF = 62.2 % before RF vs 64.4 % after RF; p = 0.02) than for right WPW (RVEF = 36.3 % before RF vs 39.7 after RF; p = 0.16). Phase analysis, on the contrary, show only significant differences for right WPW, with a noticeable decrease of the pre-excitation (left-to-right phase difference 14.4 deg before RF vs 7.5 deg after RF; p = 0.03) and a significant reduction of the right ventricular phase dispersion (right phase standard deviation 26.5 deg before RF vs 19.0 deg after RF; p = 0.03). For left WPW no measurable differences can be demonstrated in the basal state and it is suggested to use stimulation techniques in order to enhance the competition between the normal and accessory conduction pathways. (authors). 17 refs.

  17. Radioinduced optic nerve neuropathy after treatment for nasopharynx cancer. About two cases and literature review; Neuropathie radio-induite du nerf optique apres traitement pour cancer du nasopharynx. A propos de deux cas et revue de la litterature

    Energy Technology Data Exchange (ETDEWEB)

    Mnejja, W.; Siala, W.; Daoud, J. [Centre Hospitalier Universitaire Habib-Bourguiba, Service de Radiotherapie Carcinologique, Sfax (Tunisia); Fki, J. [Centre Hospitalier Universitaire Habib-Bourguiba, Service d' Ophtalmologie, Sfax (Tunisia); Ghorbel, M. [Centre Hospitalier Universitaire Habib-Bourguiba, Service d' ORL, Sfax (Tunisia); Frikha, M. [Centre Hospitalier Universitaire Habib-Bourguiba, Service de Carcinologie Medicale, Sfax (Tunisia)

    2007-11-15

    The radioinduced neuropathy of the optic nerve is a rare and delayed complication. Its incidence is difficult to evaluate in the literature. It depends on the whole irradiation dose, fractionation and irradiated volume. Currently, it does not exist any efficient treatment, only the prevention play an important part on avoiding the high doses, and the broad irradiation volumes. The innovating techniques using conformal radiotherapy with or without modulated intensity could contribute to reduce this toxicity incidence. (N.C.)

  18. Processing ore from Forez; Etude pour le traitement du minerai du Forez

    Energy Technology Data Exchange (ETDEWEB)

    Kremer, M

    1957-12-01

    A new process is given for the chemical separation, simply and economically, of the uranium contained in solutions formed by sulfuric acid attack of low uranium content ores. The attacking solution is processed in two stages. The solution is neutralized to pH 2,7 to 3 with milk of lime and a portion of the dissolved impurities are precipitated. Then milk of lime of the uranium is precipitated to pH 6,5 to 7. The uranium concentrate is then subjected to controlled sulfuric attack for its total reduction to a solution containing a minimum of foreign ions. The uranium solution thus obtained is purified by extraction with TBP. (author) [French] Ce nouveau procede permet de separer par voie chimique et de facon simple et economique des solutions obtenues par l'attaque a l'acide sulfurique des minerais d'uranium a faible teneur. Le traitement de la solution d'attaque se fait en deux temps: 1) neutralisation de la solution a pH 2,7-3, par un lait de chaux et elimination par precipitation d'une partie des impuretes dissoutes a l'attaque. 2) precipitation par un lait de chaux, de l'uranium a pH 6,5-7. Le concentre d'uranium est ensuite soumis a une attaque sulfurique qui fait repasser tout l'uranium en solution avec le minimum d'ions etrangers. La solution d'uranium ainsi obtenue est purifiee par extraction au TBP. (auteur)

  19. Besoins perçus et adaptation des démarches d’enseignement: le cas de l’enseignement des sciences et technologies au secondaire

    Directory of Open Access Journals (Sweden)

    Jean-Claude Kalubi

    2009-07-01

    Full Text Available Cet article traite de l’adaptation des démarches d’enseignement en cours d’action, adoptées par les enseignants des sciences et technologies de l’école secondaire. Il vise à comprendre les processus dynamiques de l’adaptation de l’enseignement. Il s’appuie sur des données qui ont été obtenues grâce à un protocole de recherche qualitative axé sur des techniques de groupes de réflexion. Les résultats de la recherche mettent en évidence l’hétérogénéité des parcours d’adaptation des enseignants. Ils soulignent la nécessité du professionnalisme de l’enseignant des sciences et technologies. Ils suggèrent de prendre en considération la complexité des besoins d’adaptation. Ceux-ci commandent en définitive la compatibilité entre les démarches de l’enseignant et les besoins de ses élèves. Le processus d’adaptation est aussi guidé par le plaisir de la reconnaissance, les rapports de l’enseignant aux savoirs, de même que par la défense des valeurs collectives.Mots clé: adaptation de l’enseignement, perception des besoins, enseignement des sciences et technologies This article deals with the adjustment of teaching approaches made by high school science and technology teachers while teaching. It aims at achieving a better understanding of the dynamic processes of teaching adjustment. It relies on a qualitative methodology using focus groups. Data analysis shows the multiplicity of ways that teachers use to adjust their teaching. It stresses out the importance of science and technology teachers’ professionalism and suggests taking into account the complexity of teacher and student needs in the equation of teaching adjustment. Those needs call for an increased compatibility between teaching approaches and students’ needs. The adjustment of teaching approaches is also related to the quest for recognition, the teacher relationship with knowledge and the collective values in place

  20. Traitement du foisonnement filamenteux dû à Microthrix parvicella par ajout de sels métalliques

    OpenAIRE

    Durban, N.; Juzan, L.; Krier, J.; Héduit, A.; Gillot, S.

    2012-01-01

    National audience; Les dysfonctionnements biologiques dus au développement de bactéries filamenteuses posent de nombreux problèmes d’exploitation aux stations d'épuration du type boues activées. Le filament le plus souvent mis en cause dans ce type de dysfonctionnement en France est Microthrix parvicella. La solution curative la plus utilisée actuellement est la chloration, traitement efficace mais non spécifique, qui impacte également la biologie des boues activées. Une solution émergente co...

  1. Chemical treatment of uranium ores in France; Le traitement chimique des minerais d'uranium en France

    Energy Technology Data Exchange (ETDEWEB)

    Mouret, P; Sartorius, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The various processes of chemical treatmenturanium ores, from the oldest to the more recent, are exposed, considering the following conditions: economics, geography, techniques and safety. The interest of obtaining a final concentrate as uranyl nitrate is discussed. (author)Fren. [French] Les differents procedes de traitement chimique des minerais uraniferes sont exposes depuis les premiers jusqu'aux plus recents, en tenant compte des facteurs economiques, geographiques, techniques et de salubrite. L'interet d'obtenir un concentre final a l'etat de nitrate d'uranyle est discute. (auteur)

  2. Design characteristics of EU-APR1400 on-site power system

    International Nuclear Information System (INIS)

    Kim, D.H.; Kim, Y.S.; Kim, Y.S.

    2014-01-01

    In the global nuclear market, US and European design requirements have been largely used to develop the design of nuclear power plants(NPPs). The APR1400 design was developed on the basis of US regulatory guide and EPRI utility requirements document(URD). In order to enlarge the export market of APR1400, KHNP (Korea Hydro & Nuclear Power Co., Ltd) has developed the EU-APR1400 design which complies with the European nuclear design requirements. In this paper, the design characteristics of EU-APR1400 on-site power system developed according to the European design requirements of electrical power system are described. The European main design requirements of electrical power system involve 50 Hz rated frequency, 400/110 kV grid voltage, the application of the diversity and the redundancy, and so on. The EU-APR1400 on-site power system has been developed on the basis of these requirements. The representative designs include the redundancy, diversity, independence design, the emergency power supply design, the design for providing electrical power to the dedicated severe accident systems, and the design for European grid requirements. (author)

  3. Conceptual Designs for the Performance Improvement of APR1400 SIT and Preliminary Performance Evaluation

    International Nuclear Information System (INIS)

    Chu, In-Cheol; Kwon, Tae-Soon; Song, Chul-Hwa

    2008-01-01

    Some evolutionary type PWRs such as APR1400 and APWR adopt advanced safety injection tank (SIT). The SIT of APR1400 has a fluidic device (FD) which passively controls ECC water injection flow rate into reactor coolant system during refill and reflood phases of LB-LOCA (i.e., a high injection flow rate during the refill phase and a low injection flow rate during the reflood phase). The benefit of the FD is the elimination of the function of low pressure safety injection pump from the safety injection system. The flow controlling performance of the APR1400 FD was evaluated using a prototypical full-scale test facility, called VAPER (Valve Performance Evaluation Rig). Even though the performance of the APR1400 FD satisfied major design and licensing requirements, further improvement of the performance is expected such as the extension of total injection period, the delay of nitrogen gas discharge. Several conceptual designs have been being drawn out in order to improve the performance of the APR1400 SIT. The performance of some designs was evaluated using a small scale SIT test rig. The present paper introduces some of the conceptual designs and shows the performance evaluation experimental results

  4. Spectral Matrix Filtering Applied to Vsp Processing Application du filtrage matriciel au traitement des profils sismiques verticaux

    Directory of Open Access Journals (Sweden)

    Glangeaud F.

    2006-11-01

    ère peut être extraite après horizontalisation et application d'un filtrage matriciel avec une forte moyenne en fréquence. Ce traitement est alors équivalent à un filtrage en vitesse apparente classique. Le filtrage matriciel peut conduire à une séparation d'onde sans connaissance a priori sur la vitesse apparente des différentes ondes. Dans le domaine fréquentiel, une onde W(f peut s'écrire comme le produit d'une ondelette A(f par un vecteur normalisé S(f caractérisant la surface d'onde. Pour un modèle à deux ondes W1(f = A1(f S1(f et W2(f = A2(f S2(f, quatre cas sont possibles : a Si les amplitudes des deux ondes W1 et W2 sont identiques à toutes les fréquences et si les ondes sont orthogonales ( = 0, représente le produit scalaire; les deux ondes sont projetées sur les 2 premiers vecteurs de façon équipotente et la séparation est impossible. b Si les amplitudes des deux ondes W1 et W2 sont identiques à toutes les fréquences et si les ondes ont des vitesses apparentes très proches ( ~ 1; les deux ondes sont projetées sur le premier vecteur propre et la séparation est impossible. c Si les amplitudes des ondes W1 et W2 sont différentes à toutes les fréquences et si les ondes sont orthogonales ( = 0, la séparation est parfaitement bien réalisée, chaque onde se projetant sur un vecteur propre. d Si les ondes ont des amplitudes très différentes et des vitesses apparentes très proches ( ~1, la séparation est partiellement réalisée. L'onde de plus forte amplitude est projetée sur le premier vecteur propre. L'onde de plus faible amplitude est projetée partiellement sur le deuxième vecteur propre. Les amplitudes relatives de chaque onde ne sont pas conservées. Les cas (c et (d sont illustrés par des exemples synthétiques présentés en figures 3 et 4. L'application de la technique de filtrage matriciel est illustrée à l'aide de deux exemples. Le premier exemple montre des données sismiques obtenues dans un puits vertical avec un g

  5. Questions de mathématiques élémentaires à l'usage des candidats aux écoles du Gouvernement, des aspirants au baccalauréat ès sciences et des élèves des établissements d'enseignement secondaire

    CERN Document Server

    Vuibert, Henry

    1879-01-01

    Questions de mathématiques élémentaires à l'usage des candidats aux écoles du Gouvernement, des aspirants au baccalauréat ès sciences et des élèves des établissements d'enseignement secondaire

  6. GOTHIC Simulation of APR1400 Auxiliary Charging Pump room heat up

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Hui-Un; Heo, Sun [KHNP, Daejeon (Korea, Republic of)

    2014-10-15

    As a part of the Advanced Power Reactor 1400 (APR1400) U. S. Nuclear Regulatory Commission Design Certification (NRC DC) project, we have been investigating Auxiliary Charging Pump (ACP) room heat up. With reference to the design specification of the ACP room, we determined input information and developed a GOTHIC model of the APR1400 ACP room. This calculation model is described herein, and representative results from the calculation are presented as well. The results of the present paper are used to determine the integrity of ACP operating in the accident. APR 1400 GOTHIC model was developed for ACP room heat up calculation. Calculation results confirm that door opening is cooling the room properly. It is found that the difference due to the surface option of heat conductors is insignificant. Based on this result, further studies should be performed to confirm integrity of ACP.

  7. The Ongoing Rediscovery of Après-Coup as a Central Freudian Concept.

    Science.gov (United States)

    House, Jonathan

    2017-10-01

    Après-coup, Freud's Nachträglichkeit, is an essential psychoanalytic concept structuring each of four concepts, four mental processes that lie at the foundation of Freud's thinking: psychic trauma, repression, the creation of the unconscious, and the creation of infantile sexuality. It is argued here that infantile sexual drives, in contrast to the self-preservative instincts, arise from a two-step process of translation and repression in which the residues of failed translation become source-objects of the drives. These residues of failed translation have an associative resonance with adult sexuality, and the child is driven to ongoing attempts to translate them, to make them meaningful après coup. Thus, après-coup is at the heart of the human subject as a sexual creature who requires, desires, and creates meaning.

  8. Probability Analysis of the Construction Cost of an APR1000 Single Unit

    International Nuclear Information System (INIS)

    Ha, Gak Hyeon; Suh, Yong Pyo; Kang, Yong Chul

    2011-01-01

    The nuclear power plant market is expected to grow rapidly in order to address issues of global warming, cutting CO 2 emissions and securing stable electricity supplies. Under these circumstances, the main primary goal of the APR1000 development is to ensure export competitiveness in the developing countries in the Middle East and Southeast Asia. To that end, APR1000 (1,000MWe, 3 rd generation) will be developed based on the OPR1000 (Korean standard nuclear power plant, 2.5 generation) by incorporating and improving the general requirements such as the 60 year design life time, comprehensive site requirement of 0.3g seismic design, stability improvement, operability improvement and provisions for severe accidents. The APR1000 adds 16 advanced design features to its predecessor, as outlined below in Table 1

  9. Seismic analysis of APR1400 RCS for site envelope using big mass method

    International Nuclear Information System (INIS)

    Kim, J. Y.; Jeon, J. H.; Lee, D. H.; Park, S. H.

    2002-01-01

    One of design concepts of APR1400 is the site envelope considering various soil sites as well as rock site. The KSNP's are constructed on the rock site where only the translational excitations are directly transferred to the plant. On the other hand, the rotational motions affect the responses of the structures in the soil cases. In this study, a Big Mass Method is used to consider rotational motions as excitations at the foundation in addition to translational ones to obtain seismic responses of the APR1400 RCS main components. The seismic analyses for the APR1400 excited simultaneously by translation and rotational motions were performed. The results show that the effect of soil sites is not significant for the design of main components and supports of the RCS, but it may be considerable for the design of reactor vessel internals, piping, and nozzles which have lower natural frequencies

  10. APR-246/PRIMA-1Met Inhibits and Reverses Squamous Metaplasia in Human Conjunctival Epithelium.

    Science.gov (United States)

    Li, Jing; Li, Cheng; Wang, Guoliang; Liu, Zhen; Chen, Pei; Yang, Qichen; Dong, Nuo; Wu, Huping; Liu, Zuguo; Li, Wei

    2016-02-01

    Squamous metaplasia is a common pathologic condition in ocular surface diseases for which there is no therapeutic medication in clinic. In this study, we investigated the effect of a small molecule, APR-246/PRIMA-1(Met), on squamous metaplasia in human conjunctival epithelium. Human conjunctival explants were cultured for up to 12 days under airlifting conditions. Epithelial cell differentiation and proliferation were assessed by Cytokeratin 10 (K10), K14, K19, Pax6, MUC5AC, and p63 immunostaining patterns. β-catenin and TCF-4 immunofluorescent staining and real-time PCR characterized Wnt signaling pathway involvement. Pterygium clinical samples were cultured under airlifting conditions with or without APR-246 for 4 days. p63, K10, β-catenin, and TCF-4 expression in pterygial epithelium was determined by immunofluorescent staining and real-time PCR. Airlift conjunctival explants resulted in increased stratification and intrastromal epithelial invagination. Such pathology was accompanied by increases in K10, K14, and p63 expression, whereas K19 and Pax6 levels declined when compared to those in freshly isolated tissue. On the other hand, APR-246 reversed all of these declines in K10, K14, and p63 expression. Furthermore, K19 and Pax6 increased along with rises in goblet cell density. These effects of APR-246 were accompanied by near restoration of normal conjunctival epithelial histology. APR-246 also reversed squamous metaplasia in pterygial epithelium that had developed after 4 days in ex vivo culture. Reductions in squamous metaplasia induced by APR-246 suggest it may provide a novel therapeutic approach in different squamous metaplasia-associated ocular surface diseases.

  11. Introduction au traitement mathématique des images méthodes déterministes

    CERN Document Server

    Bergounioux, Maïtine

    2015-01-01

    Ce cours est une introduction au traitement d'image mathématique déterministe. Les principales problématiques en traitement et analyse d’image y sont présentées: débruitage/filtrage/restauration, segmentation, rehaussement/défloutage, ainsi qu’un aperçu de quelques techniques d’acquisition. Les méthodes mathématiques utilisées ont essentiellement déterministes : transformation de Fourier, ondelettes, équations aux dérivées partielles, morphologie mathématique et méthodes variationnelles. Quelques applications y sont brièvement présentées pour illustrer le propos : la stéganographie, la compression et l’inpainting (ou désocclusion). Le livre comprend également un rappel des principales notions mathématiques utilisées (il se veut auto-suffisant) et la bibliographie abondante doit permettre au lecteur d’approfondir les techniques qui l’intéressent. Cet ouvrage s’adresse à des étudiants de MASTER, élèves-ingénieurs ou chercheurs désireux de comprendre ou d’approfond...

  12. Evolution de films de cuivre sur un substrat de cordiérite au cours de traitements thermiques

    Science.gov (United States)

    Guille, Jean-Louis; Gondolf, Marc

    1993-04-01

    Copper films were applied on low sintering temperature cordierite substrates either by sputtering or screen printing. Their behaviour during thermal treatments was studied as a function of various parameters : deposition technique, thickness, firing atmosphere, physical state of the substrate (green or sintered). Films were most often broken during the treatment. In the case of screen printed films the effects of an oxydation-reduction cycle of copper are pointed out. Des films de cuivre ont été déposés sur un substrat de cordiérite à basse température de frittage par deux techniques, pulvérisation cathodique et sérigraphie. On étudie leur comportement au cours de traitements thermiques en fonction de différents paramètres : technique de déposition, épaisseur, atmosphère de traitement, état physique du substrat (cru ou fritté). On constate le plus souvent une fragmentation du film. Dans le cas des films sérigraphiés on met en évidence les effets dus à l'oxydation et à la réduction du cuivre.

  13. Decontamination of irradiated-fuel processing waste using manganese dioxide hydrate; Decontamination des effluents de traitement des combustibles irradies par le bioxyde de manganese hydrate

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M; Gaudier, J F [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1969-07-01

    The 'manganese dioxide' process is designed to replace the 'calcium carbonate' treatment for low and medium activity wastes. The objective to attain during the research for a new process was the diminution of the volume of the sludge without decreasing the decontamination factor of the wastes. The new process involves addition in series of twice over 100 ppm of Mn{sup 2+} in the waste which has previously been made basic and oxidizing; the precipitate formed in situ is separated after each addition. The process has the advantage of increasing the decontamination of strontium. The treatment can be used in a plant including two decantation units and has given effective results when applied in such a plant. (author) [French] Le procede au ''bioxyde de manganese'' est destine a remplacer le traitement ''carbonate de calcium'' dans les effluents de moyenne activite. L'objectif poursuivi lors de la recherche d'un procede nouveau etait de diminuer le volume des boues sans diminuer le facteur de decontamination des effluents. Le nouveau traitement consiste a effectuer en cascade sur les effluents rendus basiques et oxydants une double precipitation de 100 ppm de Mn{sup 2+} avec separation intermediaire du precipite. Il presente en outre l'avantage d'ameliorer la decontamination en strontium. Le traitement est utilisable dans la chaine des deux decanteurs et a donne satisfaction lors de son exploitation industrielle. Le volume des boues seches a ete reduit d'un facteur 3 a 4 par rapport au traitement carbonate. (auteur)

  14. Les usages de la flexibilité temporelle chez les enseignantes du secondaire The uses of flexible time by female secondary-school teachers

    Directory of Open Access Journals (Sweden)

    Julie Jarty

    2009-09-01

    Full Text Available De par sa flexibilité temporelle, il existe une perception largement répandue selon laquelle la profession enseignante serait woman-friendly, « bien pour une femme ». Le « plafond de verre » est pourtant une réalité pour de nombreuses femmes au sein de l’enseignement du second degré. Centré sur une étude des perceptions et des pratiques temporelles au sein de ce groupe professionnel dans une perspective de genre, cet article s’appuie sur une analyse critique des discours de 40 entretiens individuels réalisés auprès d’hommes et de femmes enseignant-e-s du secondaire et de leurs « carnets-temps ». Il s’agit d’explorer la manière dont ils et elles utilisent leur temps et cette flexibilité professionnelle. Le résultat de cette recherche permet de montrer que les expériences temporelles sexuées sont particulièrement prédominantes, ce qui contribue à expliquer les difficultés des femmes enseignantes à accéder aux positions les plus prestigieuses et les mieux rémunérées de la hiérarchie. Néanmoins, la mobilisation d’une typologie des expériences temporelles des enseignantes nous conduit à identifier l’existence de discours alternatifs, reconnaissant ainsi les contrastes du degré selon lequel les rapports sociaux de sexe sont reproduits, reconfigurés ou transformés au sein de la profession.Because of its temporal flexibility, there is a widespread notion that the teaching profession is ‘woman-friendly’ or “good for women”. However, there is extensive evidence that a ‘glass ceiling’ exists for female secondary school teachers too. Based on a study of temporal perceptions and practices within the teaching profession in a gendered perspective, this paper draws on the critical discourse analysis of forty individual interviews conducted with male and female secondary school teachers and of their schedules. The aim was to examine the use they make of their time and professional flexibility

  15. Facteurs influençant l'initiation au traitement antirétroviral des personnes vivant avec le VIH dans les Centres de Traitement Agréés de Bamenda et de Bertoua au Cameroun

    Science.gov (United States)

    Mbopi-Keou, Francois-Xavier; Voundi, Esther Voundi; Kalla, Ginette Claude Mireille; Emah, Irène; Angwafo, Fru; Muna, Walinjom

    2014-01-01

    Introduction L'objectif de ce travail était de déterminer les facteurs influençant l'initiation au traitement antirétroviral des personnes vivant avec le VIH (PVVIH) dans les centres de traitements agrées (CTA) de Bamenda et de Bertoua au Cameroun. Méthodes Il s'agissait d'une étude transversale, analytique réalisée de Janvier à Avril 2011, dans les CTA de Bamenda et de Bertoua. Pour cette étude, nous avons obtenu une clairance éthique. Résultats Nous avons étudiés 460 dossiers de patients séropositifs en phase d'initiation au traitement antirétroviral dans les CTA de Bamenda et de Bertoua, 53,9% et 46,1% respectivement. L ‘âge médian était de 36 ans. La plupart des séropositifs à Bertoua (41) avaient fait un dépistage volontaire du VIH par rapport à ceux de Bamenda (22) (p= 0.008). Il y ‘avait plus de VIH de type 1 et 2 dans le CTA de Bamenda (15) par rapport à Bertoua (3) (p= 0.011). La majorité des patients était classé au stade clinique II à Bamenda (54,0%) tandis qu ‘à Bertoua le stade clinique III était prédominant (52,4%) (p = 0,000). Le taux médian de CD4 était de 133 cellules/mm3 dans le CTA de Bamenda et de 175 cellules/mm3 à Bertoua (p = 0,008). La Zidovudine était plus prescrit à Bamenda et le Ténofovir à Bertoua (p = 0,000). L ‘Efavirenz était plus prescrit à Bertoua tandis que la Névirapine l ‘était plus à Bamenda (p = 0,000). Le Lopinavir/r était plus prescrit à Bamenda qu ‘à Bertoua (p = 0,017). Conclusion Il apparait urgent de standardiser la prise en charge des PVVIH dans les CTA du Cameroun. PMID:25184023

  16. Evaluation du niveau de connaissance des patients sur la gestion du traitement par les antis vitamines K dans le service de cardiologie de Ouagadougou

    Science.gov (United States)

    Samadoulougou, André; Temoua Naibe, Dangwé; Mandi, Germain; Yameogo, Relwendé Aristide; Kabore, Elisé; Millogo, Georges; Yameogo, Nobila Valentin; Kologo, Jonas Koudougou; Thiam/Tall, Anna; Toguyeni, Boubacar Jean Yves; Zabsonre, Patrice

    2014-01-01

    Introduction Les antivitamines K (AVK), traitement anticoagulant oral le plus largement prescrit, posent un réel problème de santé publique du fait de leur risque iatrogène. L'objectif de cette étude était de préciser le niveau de connaissance des patients sur la gestion de leur traitement par les AVK. Méthodes Il s'est agi d'une enquête transversale descriptive réalisée au CHU-Yalgado Ouédraogo, sur une période de 03 mois : du 1er mars au 31 mai 2012. Un questionnaire a été administré aux patients bénéficiant d'un traitement AVK depuis au moins un mois. Résultats Soixante-dix patients ont été inclus dans l'étude dont 30 hommes. L'âge moyen était de 49 ans ± 16 ans. Les cardiopathies et la maladie thromboembolique veineuse justifiant l'institution du traitement AVK étaient retrouvées respectivement dans 58,6% et 41,4% des cas. Le nom de l'AVK et la raison exacte du traitement étaient connus respectivement dans 91,4% et 67,1% des cas. Plus de la moitié des patients (68,6%) savaient que les AVK rendaient le sang plus fluide. Quarante-six patients (65,7%) citaient l'INR comme examen biologique de surveillance du traitement et seulement 28 patients (40%) connaissaient les valeurs cibles. La majorité des patients ne connaissait pas les risques encourus en cas de surdosage (72,8%) et de sous-dosage (71,4%). Une automédication par anti-inflammatoire non stéroïdien était signalée par 18 patients (25,7%). Les choux (74,3%) et la laitue (62,9%), aliments à consommer avec modération, étaient les plus cités. Conclusion Les connaissances des patients sur la gestion des AVK étaient fragmentaires et insuffisantes pour assurer la sécurité et l'efficacité du traitement. La création d'un programme d'éducation thérapeutique sur les AVK s'avère alors nécessaire. PMID:25870741

  17. Using a Classroom Response System to Improve Multiple-Choice Performance in AP[R] Physics

    Science.gov (United States)

    Bertrand, Peggy

    2009-01-01

    Participation in rigorous high school courses such as Advanced Placement (AP[R]) Physics increases the likelihood of college success, especially for students who are traditionally underserved. Tackling difficult multiple-choice exams should be part of any AP program because well-constructed multiple-choice questions, such as those on AP exams and…

  18. Effectiveness of External Reactor Vessel Cooling (ERVC) strategy for APR1400 and issues of phenomenological uncertainties

    International Nuclear Information System (INIS)

    Oh, S.J.; Kim, H.T.

    2007-01-01

    The APR1400(Advanced Power Reactor 1400) is an evolutionary advanced light water reactor with rated thermal power of 4000 MWt. For APR1400, External Reactor Vessel Cooling (ERVC) is adopted as a primary severe accident management strategy for in-vessel retention (IVR) of corium. The ERVC is a method of IVR by submerging the reactor vessel exterior. At the early stage of the APR1400 design, only ex-vessel cooling, cooling of the core melt outside the vessel after vessel is breached, is considered based on the EPRI Utility Requirement Document for Evolutionary LWR. However, based on the progress in implementation of Severe Accident Management Guidance (SAMG) for operating plants, as well as the research findings related to ERVC, ERVC strategy is adopted as a part of key severe accident management strategies. To improve its success, the strategy is reviewed and we implemented necessary design arrangement to increase its usefulness in managing the severe accident. In this paper, we examine the evolution of ERVC concept and its implementation in APR1400. Then, we review possible approach, including Risk-Oriented Accident Analysis Methodology (ROAAM), to evaluate the effectiveness of the strategy. (authors)

  19. An investigation of major influences on the seismic response of APR1400 reactor vessel internals - 15145

    International Nuclear Information System (INIS)

    Byun, Y.J.; Kim, J.G.; Sung, K.K.; Lee, D.H.

    2015-01-01

    This paper deals with 3 topics concerning the APR1400 reactor vessel internals (RVI) seismic analysis: nonlinear problems, approaches to account for uncertainties of seismic model, and dynamic responses to various seismic excitations. First, the noticeable nonlinear characteristics of the RVI seismic model are discussed, and the modeling methods for properly simulating the nonlinear behaviors of RVI under seismic loads are presented. By applying these methods to the seismic model, the seismic analysis can correctly predict the dynamic response of RVI. Next, two approaches to account for the uncertainties of seismic model are evaluated: the time history broadening method, and the sensitivity analysis based on NUREG-0800, Section 4.2, Appendix A. From the evaluation results, it is confirmed that the time history broadening method employed in the seismic analysis of APR1400 RVI sufficiently accounts for the uncertainty of seismic model. Finally, the response characteristics of APR1400 RVI to various seismic excitations are investigated. The seismic excitations corresponding to various soil profiles, including the effects of cracked and un-cracked concrete stiffness on the reactor containment building structure, are used as forcing functions. From this study, the effects of various site conditions on the dynamic response of APR1400 RVI are identified. As a result, the enveloped seismic responses obtained from this study will contribute to the development of RVI seismic design that covers a wide range of potential site conditions. (authors)

  20. System Response Analysis of Rod Ejection Accident for APR1400 Using KNAP Hot Spot Model

    International Nuclear Information System (INIS)

    Kim, Yo-Han; Ha, Sang-Jun; Jun, Hwang-Yong

    2006-01-01

    Korea Electric Power Research Institute (KEPRI) has been developed the non-loss-of-coolant accident (non- LOCA) analysis methodology, called as the Korea Non- LOCA Analysis Package (KNAP), for the typical Optimized Power Reactor 1000 (OPR1000) plants. Considering current licensing methodology conducted by ABB-CE, however, the KNAP could be applied to Advanced Power Reactor 1400 (APR1400) also. In spite of some difference in design concepts of two plant types, there is a close resemblance between their nuclear steam supply systems (NSSS). So, in this study, the rod ejection accident (REA) event was analyzed using KNAP hot spot model (HSM) for APR1400 to estimate the feasibility of the application and the results were compared with those given in APR1400 Standard Safety Analysis Report (SSAR), which were calculated using the CESEC-III and STRIKIN-II code of ABB-CE. Through the study, it was concluded that the KNAP could be applicable to APR1400 on the view point of REA

  1. The Alberta Pregnancy Outcomes and Nutrition (APrON) cohort study : rationale and methods

    NARCIS (Netherlands)

    Kaplan, Bonnie J.; Giesbrecht, Gerald F.; Leung, Brenda M. Y.; Field, Catherine J.; Dewey, Deborah; Bell, Rhonda C.; Manca, Donna P.; O'Beirne, Maeve; Johnston, David W.; Pop, Victor J.; Singhal, Nalini; Gagnon, Lisa; Bernier, Francois P.; Eliasziw, Misha; McCargar, Linda J.; Kooistra, Libbe; Farmer, Anna; Cantell, Marja; Goonewardene, Laki; Casey, Linda M.; Letourneau, Nicole; Martin, Jonathan W.

    The Alberta Pregnancy Outcomes and Nutrition (APrON) study is an ongoing prospective cohort study that recruits pregnant women early in pregnancy and, as of 2012, is following up their infants to 3 years of age. It has currently enrolled approximately 5000 Canadians (2000 pregnant women, their

  2. The Alberta Pregnancy Outcomes and Nutrition (APrON) cohort study : Rationale and methods

    NARCIS (Netherlands)

    Kaplan, B.J.; Giesbrecht, G.F.; Leung, B.M.; Field, C.J.; Dewey, D.; Bell, R.C.; Manca, D.P.; O'Beirne, M.; Johnston, D.W.; Pop, V.J.M.; Singhal, N.; Gagnon, L.; Bernier, F.P.; Eliasziw, M.; McCargar, L.J.; Kooistra, L.; Farmer, A.; Cantell, M.; Goonewardene, L.; Casey, L.M.; Letourneau, N.; Martin, J.W.

    2014-01-01

    The Alberta Pregnancy Outcomes and Nutrition (APrON) study is an ongoing prospective cohort study that recruits pregnant women early in pregnancy and, as of 2012, is following up their infants to 3 years of age. It has currently enrolled approximately 5000 Canadians (2000 pregnant women, their

  3. Greta Kaits 9. apr. 1928 - 29. aug. 1946 : [luuletused] / Mats Traat

    Index Scriptorium Estoniae

    Traat, Mats, 1936-

    2008-01-01

    Sisu : Greta Kaits 9. apr. 1928 - 29. aug. 1946 ; Villem Hänilane 1898 - 1952 ; Peeter Pedak 1897 - 1953 ; Max Äidse 1903 - 1959 ; Lavinia Laidam ; Buchard Pruus ; Sergei Krivokopõtov ; Allan Luht 5. VII 1962 - 17. V 2007 ; Karl Saarmets 9. III 1924 - 14. IX 1981 ; Raimo Ritsik

  4. Neuchatel ne gardera pas le Palais de l'equilibre apres Expo.02

    CERN Multimedia

    2002-01-01

    "La ville de Neuchatel ne souhaite pas conserver le Palais de l'equilibre apres Expo.02. Par 24 voix contre 7, le Conseil general a rejete le plan special du Conseil communal qui proposait de transformer l'edifice en un centre de congres" (1/2 page).

  5. Functional similarities between the dictyostelium protein AprA and the human protein dipeptidyl-peptidase IV.

    Science.gov (United States)

    Herlihy, Sarah E; Tang, Yu; Phillips, Jonathan E; Gomer, Richard H

    2017-03-01

    Autocrine proliferation repressor protein A (AprA) is a protein secreted by Dictyostelium discoideum cells. Although there is very little sequence similarity between AprA and any human protein, AprA has a predicted structural similarity to the human protein dipeptidyl peptidase IV (DPPIV). AprA is a chemorepellent for Dictyostelium cells, and DPPIV is a chemorepellent for neutrophils. This led us to investigate if AprA and DPPIV have additional functional similarities. We find that like AprA, DPPIV is a chemorepellent for, and inhibits the proliferation of, D. discoideum cells, and that AprA binds some DPPIV binding partners such as fibronectin. Conversely, rAprA has DPPIV-like protease activity. These results indicate a functional similarity between two eukaryotic chemorepellent proteins with very little sequence similarity, and emphasize the usefulness of using a predicted protein structure to search a protein structure database, in addition to searching for proteins with similar sequences. © 2016 The Protein Society.

  6. Functional similarities between the dictyostelium protein AprA and the human protein dipeptidyl‐peptidase IV

    Science.gov (United States)

    Herlihy, Sarah E.; Tang, Yu; Phillips, Jonathan E.

    2017-01-01

    Abstract Autocrine proliferation repressor protein A (AprA) is a protein secreted by Dictyostelium discoideum cells. Although there is very little sequence similarity between AprA and any human protein, AprA has a predicted structural similarity to the human protein dipeptidyl peptidase IV (DPPIV). AprA is a chemorepellent for Dictyostelium cells, and DPPIV is a chemorepellent for neutrophils. This led us to investigate if AprA and DPPIV have additional functional similarities. We find that like AprA, DPPIV is a chemorepellent for, and inhibits the proliferation of, D. discoideum cells, and that AprA binds some DPPIV binding partners such as fibronectin. Conversely, rAprA has DPPIV‐like protease activity. These results indicate a functional similarity between two eukaryotic chemorepellent proteins with very little sequence similarity, and emphasize the usefulness of using a predicted protein structure to search a protein structure database, in addition to searching for proteins with similar sequences. PMID:28028841

  7. 75 FR 44847 - Proposed Collection; Comment Request for Forms 943, 943-PR, 943-A, and 943A-PR

    Science.gov (United States)

    2010-07-29

    ... 943, 943-PR, 943- A, and 943A-PR AGENCY: Internal Revenue Service (IRS), Treasury. ACTION: Notice and... comments concerning Forms 943, Employer's Annual Tax Return for Agricultural Employees, 943-PR, Planilla..., Agricultural Employer's Record of Federal Tax Liability, and 943A-PR, Registro De La Obligacion Contributiva...

  8. 78 FR 47051 - Proposed Collection; Comment Request for Forms 943, 943-PR, 943-A, and 943A-PR

    Science.gov (United States)

    2013-08-02

    ... 943, 943-PR, 943- A, and 943A-PR AGENCY: Internal Revenue Service (IRS), Treasury. ACTION: Notice and..., 943-PR, Planilla Para La Declarcion Anual De La Contribucion Federal Del Patrono De Empleados Agricolas, 943-A, Agricultural Employer's Record of Federal Tax Liability, and 943A-PR, Registro De La...

  9. Soutenir le cheminement de stage d’apprentis enseignants au secondaire par un environnement d’apprentissage hybride / Supporting the advancement of student-teachers in their practica with the use of a hybrid learning environment

    Directory of Open Access Journals (Sweden)

    Stéphane Allaire

    2009-03-01

    Full Text Available Résumé : Dans un contexte de pratiques éducatives en renouvellement, la recherche participative étudie l’apport d’un environnement d’apprentissage hybride pour l’analyse réflexive de stagiaires en enseignement secondaire. Des analyses qualitatives et quantitatives descriptives illustrent le potentiel des dispositifs mis en place pour soutenir l’intégration à un contexte de stage innovateur, une réflexivité diversifiée et la coélaboration de connaissances. Abstract : In the context of evolving educational practices, participatory research is used to study the contribution of a hybrid learning environment when used by student teachers in secondary teaching for reflective analysis. Both quantitative analysis and qualitative descriptives illustrate the potential of the devices and strategies used to support the student teachers in their integration into an innovative practicum context, a diversified reflective practice and knowledge building.

  10. Processing Th C{sub 2} - UC{sub 2} fuel extracted from high temperature reactors HTGCR; Etude du traitement des combustibles Th C{sub 2} - UC{sub 2} issus de reacteurs a haute temperature

    Energy Technology Data Exchange (ETDEWEB)

    Derrien, C; Lessart, P; Pianezza, E; Verry, C; Villain, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    The object of this investigation is solubilisation head-end (from crushing and grinding phase to non included first purification phase) of pulverulent ({sup 233}U/{sup 232}Th)C{sub 2} (200 - 500 microns diameter) contained in a graphite matrix extracted from a 4.10{sup 13} n.cm{sup -2}.s{sup -1} thermalized neutrons average flux with an irradiation of 80000 MWjT{sup -1} HTGCR reactor. After having succinctly described different bibliographic processes we have chosen the burn - leach of reactor fuel and graphite matrix containing it. The technology of burner is original in nuclear field and still more by utilizing ultra-sounds to intensify burning reaction and to minimize the weight of unburnables. The mixture of ThO{sub 2}, U{sub 3}O{sub 8}, and fission products oxides is solubilized by boiling HNO{sub 3} 13 M + HF 0.05 M. This process is profit-learning in a thorium recuperation and reprocessing point of view. In the contrary-case it would be interesting to consider a dry-process which would permit to separate solid ThF{sub 4} from gaseous UF{sub 6}. (authors) [French] Cette etude a pour objet le traitement initial de mise en solution ou 'head-end' (allant de la phase broyag-concassage a la phase de premiere purification exclue) d'un combustible ({sup 233}U/{sup 232}Th)C{sub 2} pulverulent (de 200 a 500 {mu} de diametre) contenu dans une matrice de graphite issu d'un reacteur HTGCR surgenerateur a neutrons thermiques de flux moyen 4. l0{sup 13} n.cm{sup -2}.s{sup -1} et taux d'irradiation 80000 MWjT{sup -1}. Apres exposition succincte des differents procedes bibliographiques decrits, nous avons finalement choisi le traitement par combustion-attaque ('Burn-Leach') du combustible et de la matrice etanche graphite qui le contient. La technologie du bruleur est originale dans le domaine nucleaire d'autant qu'elle utilise les ultra-sons pour ameliorer le rendement de la reaction de combustion et reduire au minimum le poids des imbrules. Le melange ThO{sub 2}, U{sub 3}O

  11. Traitement des diagraphies acoustiques. Deuxième partie : séparation des ondes en diagraphie acoustique Full-Waveform Acoustic Data Processing. Second Part: Wave Separation in Acoustic Well Logging

    OpenAIRE

    Gavin P.; Mari J. L.

    2006-01-01

    L'utilisation d'outils acoustiques à émetteurs-récepteurs multiples et enregistrement numérique permet de faire une microsismique de puits en utilisant des techniques de traitement dérivées du traitement sismique. Comme les enregistrements acoustiques sont composés de différents types d'ondes (ondes de volume réfractées ou réfléchies et ondes d'interface), une étape importante du traitement acoustique est la séparation des ondes. Cet article montre que la séparation des ondes peut être optimi...

  12. Preliminary Design of Optimized Reactor Insulator for Severe Accident Mitigation of APR1400

    International Nuclear Information System (INIS)

    Heo, Sun; Lee, Jae-Gon; Kang, Yong-Chul

    2007-01-01

    APR1400, a Korean evolutionary advance light water reactor, has many advanced safety feature to prevent and mitigate of design basis accident (DBA) and severe accident. When reactor cooling system (RCS) fails to cooling its core, the core melted down and the molten core gathers together on bottom of reactor vessel. The molten core hurts reactor vessel and is released to containment, which raises the release of radioactive isotopes and the heating of the containment atmosphere. Finally, the corium is accumulated in the bottom of reactor cavity and it also raises the Molten Core and Concrete Interaction (MCCI) and the heating of containment atmosphere. There are two strategies to cooling molten core. Those are in-vessel retention and ex-vessel cooling. At the early stage of APR1400 design, only ex-vessel cooling which is cooling of the molten core outside the vessel after vessel failure is considered based on EPRI Utility Requirement Document (URD) for Evolutionary LWR. However, a need has been arisen to reflect current research findings on severe accident phenomena and mitigation technologies to Korean URD and IVRERVC (In-Vessel corium Retention using Ex-Reactor Vessel Cooling) was adopted APR1400. The ERVC is not considered as a licensing design basis but based on the defense-in-depth principle and safety margin basis, which is the top-tier requirement of the severe accident mitigation design as stated in the KURD. The Severe Accident Management strategy for APR1400 is intended to aid the plant operating staff to secure reactor vessel integrity in the early stage of the severe accident. As a part of a design implementation of IVR-ERVC for APR1400, we developed the preliminary design requirement, design specification and conceptual design

  13. [Evaluation of the capacity of the APR-DRG classification system to predict hospital mortality].

    Science.gov (United States)

    De Marco, Maria Francesca; Lorenzoni, Luca; Addari, Piero; Nante, Nicola

    2002-01-01

    Inpatient mortality has increasingly been used as an hospital outcome measure. Comparing mortality rates across hospitals requires adjustment for patient risks before making inferences about quality of care based on patient outcomes. Therefore it is essential to dispose of well performing severity measures. The aim of this study is to evaluate the ability of the All Patient Refined DRG system to predict inpatient mortality for congestive heart failure, myocardial infarction, pneumonia and ischemic stroke. Administrative records were used in this analysis. We used two statistics methods to assess the ability of the APR-DRG to predict mortality: the area under the receiver operating characteristics curve (referred to as the c-statistic) and the Hosmer-Lemeshow test. The database for the study included 19,212 discharges for stroke, pneumonia, myocardial infarction and congestive heart failure from fifteen hospital participating in the Italian APR-DRG Project. A multivariate analysis was performed to predict mortality for each condition in study using age, sex and APR-DRG risk mortality subclass as independent variables. Inpatient mortality rate ranges from 9.7% (pneumonia) to 16.7% (stroke). Model discrimination, calculated using the c-statistic, was 0.91 for myocardial infarction, 0.68 for stroke, 0.78 for pneumonia and 0.71 for congestive heart failure. The model calibration assessed using the Hosmer-Leme-show test was quite good. The performance of the APR-DRG scheme when used on Italian hospital activity records is similar to that reported in literature and it seems to improve by adding age and sex to the model. The APR-DRG system does not completely capture the effects of these variables. In some cases, the better performance might be due to the inclusion of specific complications in the risk-of-mortality subclass assignment.

  14. Study of secondary electronic emission in some piezo-electric materials: application to ultrasonic visualization; Etude de l'emission electronique secondaire de quelques materiaux piezoelectriques: application a la visualisation ultrasonore

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Methods allowing the visualization of acoustic images appear at the moment to be of great interest in the field of non-destructive testing as well as in that of underwater detection. In order to carry out certain calculations on the operation of an ultrasonic camera, it has been necessary to study the secondary electron emission of some piezoelectric materials liable to be incorporated into the equipment. The secondary electron emission of insulators is a rather complex phenomenon; in order to find a rational explanation for the observations made, a theory has been developed for the energy spectrum of the emitted electrons. The experimental results of this work have then been used to build an ultrasonic visualization installation. Some examples of acoustic images which have been visualized are also presented. (author) [French] Les methodes qui permettent de visualiser des images acoustiques trouvent a l'heure actuelle un grand interet dans le domaine du controle non destructif comme dans celui de la detection sous-marine. De maniere a effectuer certains calculs sur le fonctionnement d'une camera ultrasons, il a ete necessaire d'etudier l'emission electronique secondaire de quelques materiaux piezoelectriques susceptibles d'etre utilises dans sa construction. L'emission electronique secondaire des isolants est un phenomene assez complexe et de maniere a trouver des explications coherentes aux observations effectuees, une theorie du spectre energetique des electrons emis a ete elaboree. Une installation de visualisation ultrasonore a alors ete realisee a partir des donnees experimentales de cette etude. Quelques exemples d'images acoustiques visualisees par cette methode sont egalement presentees. (auteur)

  15. Study of secondary electronic emission in some piezo-electric materials: application to ultrasonic visualization; Etude de l'emission electronique secondaire de quelques materiaux piezoelectriques: application a la visualisation ultrasonore

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Methods allowing the visualization of acoustic images appear at the moment to be of great interest in the field of non-destructive testing as well as in that of underwater detection. In order to carry out certain calculations on the operation of an ultrasonic camera, it has been necessary to study the secondary electron emission of some piezoelectric materials liable to be incorporated into the equipment. The secondary electron emission of insulators is a rather complex phenomenon; in order to find a rational explanation for the observations made, a theory has been developed for the energy spectrum of the emitted electrons. The experimental results of this work have then been used to build an ultrasonic visualization installation. Some examples of acoustic images which have been visualized are also presented. (author) [French] Les methodes qui permettent de visualiser des images acoustiques trouvent a l'heure actuelle un grand interet dans le domaine du controle non destructif comme dans celui de la detection sous-marine. De maniere a effectuer certains calculs sur le fonctionnement d'une camera ultrasons, il a ete necessaire d'etudier l'emission electronique secondaire de quelques materiaux piezoelectriques susceptibles d'etre utilises dans sa construction. L'emission electronique secondaire des isolants est un phenomene assez complexe et de maniere a trouver des explications coherentes aux observations effectuees, une theorie du spectre energetique des electrons emis a ete elaboree. Une installation de visualisation ultrasonore a alors ete realisee a partir des donnees experimentales de cette etude. Quelques exemples d'images acoustiques visualisees par cette methode sont egalement presentees. (auteur)

  16. Re-irradiation after salvage mastectomy for local recurrence after a conservative treatment: a retrospective analysis of twenty patients (Nancy: 1988-2001); Re-irradiation parietale apres mastectomie de rattrapage pour recidive d'un cancer du sein apres traitement conservateur: etude retrospective sur 20 patientes (Nancy: 1988-2001)

    Energy Technology Data Exchange (ETDEWEB)

    Racadot, S.; Marchal, C.; Charra-Brunaud, C.; Peiffert, D.; Bey, P. [Centre Alexis-Vautrin, Service de Radiotherapie, 54 - Vandoeuvre-les-Nancy (France); Verhaeghe, J.L. [Centre Alexis-Vautrin, Service de Chirurgie, 54 - Vandoeuvre-les-Nancy (France)

    2003-12-01

    Purpose. - To retrospectively assess the efficacy of post-mastectomy re-irradiation for local relapse of breast cancer. Patients and methods. - Twenty patients, initially treated by conservative surgery and radiotherapy (50 Gy in 25 fractions over 5 weeks) were treated from 1998 to 2001 for a local relapse by salvage mastectomy and re-irradiation (either electron or photon beams). Mean age was 53 years (31-71). Reasons for re-irradiation were that the local relapses were inflammatory (4 pts), multifocal (5 pts), cutaneous (5 pts), involved the nipple (3 pts) or because the surgical margins (either muscle or skin) were involved (3 pts). The median dose of re-irradiation was 45 Gy (33-65) in 15 fractions over 33 days. Mean follow-up was 48 months (5-97). Results. - Fifteen patients remained free of a second local recurrence and 10 were still alive, without metastasis. Neither the dose of re-irradiation nor the irradiated surfaces were prognostic factors of local control (P = 0.877 and P = 0.424). Five patients developed radiation-induced pneumonitis without functional respiratory impairment. The incidence of pneumonitis seemed to be related to the biological dose of re-irradiation (P = 0.037). Other late complications occurred such as pigmentation changes (12 pts), telangiectasia (8 pts), chondritis (2 pts), parietal fibrosis (7 pts), rib fractures (4 pts), severe pain (11 pts) and lymphedema (2 pts). The increase in biological equivalent dose was highly statistically linked with the occurrence of disabling pain (P = 0.0123). Conclusion. - Parietal re-irradiation achieves good and lasting local control with an acceptable rate of acute complications but with a risk of disabling late sequelae such as severe pain. (author)

  17. The treatment and conditioning of solid radioactive waste (1962); Le traitement et le conditionnement des dechets radioactifs solides (1982)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    Previous studies, the results of which have been confirmed by experiments, have led us to build a semi-industrial plant for the treatment and coating of solid radioactive waste. This report details the means at our disposal in a pilot plant which, apart from being used for tests, was also routine-operated. It is thus possible to give also an appreciation of its operation in this report. (authors) [French] Les etudes anterieures, dont les resultats ont ete confirmes par des essais, nous ont conduits a realiser une installation semi-industrielle de traitement et d'enrobage des dechets radioactifs solides. Le rapport a pour but de preciser les moyens mis a notre disposition dans une unite pilote qui, outre son role de banc d'essai, a pu etre exploitee en routine. C'est donc aussi un bilan de son exploitation qui est presente. (auteurs)

  18. Image processing. A system for the automatic sorting of chromosomes; Traitement d'images - Applications au classement des chromosomes

    Energy Technology Data Exchange (ETDEWEB)

    Najai, Amor

    1977-05-27

    The present paper deals with two aspects of the system: - an automata (specialized hardware) dedicated to image processing. Images are digitized, divided into sub-units and computations are carried out on their main parameters. - A software for the automatic recognition and sorting of chromosomes is implemented on a Multi-20 minicomputer, connected to the automata. (author) [French] Nous decrivons un systeme automatique de classification de chromosomes. Il se compose de: - l'A.S.T.I., Automate Specialise de Traitement d'Images permettant de numeriser celles-ci, d'isoler des sous-images, d'effectuer des calculs sur leurs parametres principaux. - Un programme de reconnaissance et de classification automatique des chromosomes implante sur un mini-ordinateur MULTI-20, couple a l'A.S.T.I. (auteur)

  19. Solvent purification using a current of water vapour. A continuous process applicable to chemical plants treating irradiated fuels; Purification des solvants par entrainement a la vapeur d'eau. Procede continu applicable aux usines chimiques de traitement des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, P R; Sautray, R R; Girard, B R [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1964-07-01

    zirconium-niobium apres traitement est indecelable et il est facile d'obtenir des facteurs de decontamination de 300 sur le ruthenium. La presence d'uranium favorise la decontamination. Pour terminer, le lecteur trouvera des considerations extra-techniques et en particulier l'ordre de grandeur des prix de revient du litre de solvant traite. (auteurs)

  20. Deletion of aprA and nprA genes for alkaline protease A and neutral protease A from bacillus thuringiensis: effect on insecticidal crystal proteins.

    Science.gov (United States)

    Tan, Y; Donovan, W P

    2001-11-17

    The aprA gene encoding alkaline protease A (AprA) was cloned from Bacillus thuringiensis subsp. kurstaki, and the cloned gene was used to construct aprA-deleted (aprA1) strains of B. thuringiensis. An aprA1 strain of B. thuringiensis that contained the wild-type gene for neutral protease A (nprA(+)) displayed levels of extracellular proteolytic activity that were similar to those of an aprA(+)nprA(+) strain. However, when EDTA was included in the protease assay to inhibit NprA activity the aprA1nprA(+) strain displayed only 2% of the extracellular proteolytic activity of the aprA(+)nprA(+) strain. A strain that was deleted for both aprA and nprA (aprA1nprA3 strain) failed to produce detectable levels of proteolytic activity either in the presence or absence of EDTA in the assay. Compared with the aprA(+)nprA(+) strain the aprA1nprA(+) strain yielded 10% more full-length Cry1Bb crystal protein and the aprA1nprA3 strain yielded 25% more full-length Cry1Bb protein. No significant differences were seen in the 50% lethal dose of Cry1Bb protein from aprA(+)nprA(+) and aprA1nprA3 strains against three species of lepidopteran insects. These results suggest that enhanced yield of certain crystal proteins can be obtained by deletion of the genes aprA and nprA which are the major extracellular proteases of B. thuringiensis.

  1. Quantitative Safety Impact of Severe Accident Management Systems for EU-APR during Low Power Shutdown Operation

    International Nuclear Information System (INIS)

    Lee, Keunsung; Hwang, Do Hun; Chang, Hyun-bin

    2016-01-01

    In order to enlarge and to diversify the export market of APR1400, the EU-APR design was developed based on the APR1400 design to comply with the latest version of the European Utility Requirements (EUR) revision D. The EU-APR design has the distinguished and advanced severe accident management systems taken from the APR1400 to obtain a containment integrity for the beyond design basis accident, such as the Passive Ex-vessel retaining and Cooling System (PECS), the Severe Accident Containment Spray System (SACSS) and the Containment Filtered Vent System (CFVS). The risk associated with the nuclear power plant can be identified through the Probabilistic Safety Assessment (PSA). In the EUR chapter 1 and 17 of volume 2, the Criteria for Limited Impact (CLI) should be applied to the Level 2 PSA as a risk metrics. The fraction of exceeding CLI for the EU-APR during LPSD operation was calculated as 4.52% of the CDF under the condition that all severe accident management systems are credited. The PECS, SACSS and CFVS are considered as the severe accident management system which is EU-APR dedicated system. The exemption of each system leads to increase the fraction of exceeding CLI to 54.18%, 89.74% and 21.32% respectively. In case if all these systems are unavailable, the fraction of exceeding CLI is increased to 100%. The most effective system is the SACSS that the system reduces containment pressure and temperature

  2. Quantitative Safety Impact of Severe Accident Management Systems for EU-APR during Low Power Shutdown Operation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Keunsung; Hwang, Do Hun [KHNP CRI, Daejeon (Korea, Republic of); Chang, Hyun-bin [Future and Challenge Technology Co., Yongin (Korea, Republic of)

    2016-10-15

    In order to enlarge and to diversify the export market of APR1400, the EU-APR design was developed based on the APR1400 design to comply with the latest version of the European Utility Requirements (EUR) revision D. The EU-APR design has the distinguished and advanced severe accident management systems taken from the APR1400 to obtain a containment integrity for the beyond design basis accident, such as the Passive Ex-vessel retaining and Cooling System (PECS), the Severe Accident Containment Spray System (SACSS) and the Containment Filtered Vent System (CFVS). The risk associated with the nuclear power plant can be identified through the Probabilistic Safety Assessment (PSA). In the EUR chapter 1 and 17 of volume 2, the Criteria for Limited Impact (CLI) should be applied to the Level 2 PSA as a risk metrics. The fraction of exceeding CLI for the EU-APR during LPSD operation was calculated as 4.52% of the CDF under the condition that all severe accident management systems are credited. The PECS, SACSS and CFVS are considered as the severe accident management system which is EU-APR dedicated system. The exemption of each system leads to increase the fraction of exceeding CLI to 54.18%, 89.74% and 21.32% respectively. In case if all these systems are unavailable, the fraction of exceeding CLI is increased to 100%. The most effective system is the SACSS that the system reduces containment pressure and temperature.

  3. La métaplasie osteoide de l'endomètre après une grossesse à terme

    African Journals Online (AJOL)

    A travers notre cas et à la lumière d'une revue de la littérature nous insistons sur les caractéristiques épidémiologiques, physiopathologiques, cliniques et para cliniques de cette entité rare, dont la connaissance est primordiale pour un diagnostic sûr et par conséquent un traitement adapté permettant souvent de récupérer ...

  4. Pyélonéphrite Emphysémateuse Avec Une Issue Favorable Après ...

    African Journals Online (AJOL)

    28 août 2011 ... 1Service d'Urologie, 2Service de Radio Hôpital militaire Avicenne,. Marrakech, Maroc. RÉSUMÉ. Introduction: La pyélonéphrite emphysémateuse est une infection nécrotique du rein dont la sanction est le plus souvent radicale. Objectif: Notre propos est de montrer que le traitement conservateur pourrait ...

  5. The comparison between layout and design of APR1400 MCR and EPRI requirement

    International Nuclear Information System (INIS)

    Suharyo Widagdo; Darlis; Sigit Santoso; T J Suryono

    2013-01-01

    A good man-machine interface system is needed by a nuclear power reactor because of its complexity and high safety factor. The man-machine interface system is centralized in the main control room (MCR). All of monitoring and controlling activity to keep the installation operation safety can be done from this place. In order to increase its ability in monitoring and controlling a hard effort to raise the interface system to the highest possible level is done not only by using the latest computer technology and instrumentation system but also using Human Engineering, as well. The paper aims to compare the lay out and design the APR1400 MCR and the requirement from EPRI about main control room lay out and design as response of TMI-2 accident. We can see from the discussion that the design of the MCR of APR1400 have been applied the request of EPRI. (author)

  6. Calculation of fuel and moderator temperature coefficients in APR1400 nuclear reactor by MVP code

    International Nuclear Information System (INIS)

    Pham Tuan Nam; Le Thi Thu; Nguyen Huu Tiep; Tran Viet Phu

    2014-01-01

    In this project, these fuel and moderator temperature coefficients were calculated in APR1400 nuclear reactor by MVP code. APR1400 is an advanced water pressurized reactor, that was researched and developed by Korea Experts, its electric power is 1400 MW. The neutronics calculations of full core is very important to analysis and assess a reactor. Results of these calculation is input data for thermal-hydraulics calculations, such as fuel and moderator temperature coefficients. These factors describe the self-safety characteristics of nuclear reactor. After obtaining these reactivity parameters, they were used to re-run the thermal hydraulics calculations in LOCA and RIA accidents. These thermal-hydraulics results were used to analysis effects of reactor physics parameters to thermal hydraulics situation in nuclear reactors. (author)

  7. Improved Design of Crew Operation in Computerized Procedure System of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Seong, No Kyu; Jung, Yeon Sub; Sung, Chan Ho [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    The operators perform the paper-based procedures in analog-based conventional main control room (MCR) depending on only communications between operators except a procedure controller such as a Shift Supervisor (SS), however in digital-based MCR the operators can confirm the procedures simultaneously in own console when the procedure controller of computerized procedure (CP) opens the CP. The synchronization and a synchronization function between procedure controller and other operators has to be considered to support the function of crew operation. This paper suggests the improved design of crew operation in computerized procedure system of APR1400. This paper suggests the improved design of APR1400 CPS. These improvements can help operators perform the crew procedures more efficiently. And they reduce a burden of communication and misunderstanding of computerized procedures. These improvements can be applied to CPS after human factors engineering verification and validation.

  8. Constrained model predictive control for load-following operation of APR reactors

    International Nuclear Information System (INIS)

    Kim, Jae Hwan; Lee, Sim Won; Kim, Ju Hyun; Na, Man Gyun; Yu, Keuk Jong; Kim, Han Gon

    2012-01-01

    The load-following operation of APR+ reactor is needed to control the power effectively using the control rods and to restrain the reactivity control from using the boric acid for flexibility of plant operation. Usually, the reason why the disproportion of axial flux distribution occurs during load-following operation is xenon-induced oscillation. The xenon has a very high absorption cross-section and makes the impact on the reactor delayed by the iodine precursor. The power maneuvering using automatically load-following operation has advantage in terms of safety and economic operation of the reactor, so the controller has to be designed efficiently. Therefore, an advanced control method that meets the conditions such as automatic control, flexibility, safety, and convenience is necessary to load-following operation of APR+ reactor. In this paper, the constrained model predictive control (MPC) method is applied to design APR reactor's automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control. Some controllers use only the current tracking command, but MPC considers future commands in addition to the current tracking command. So, MPC can achieve better tracking performance than others. Furthermore, an MPC is to used in many industrial process control systems. The basic concept of the MPC is to solve an optimization problem for a finite future time interval at present time and to implement the first optimal control input as the current control input. The KISPAC-1D code, which models the APR+ nuclear power plants, is interfaced to the proposed controller to verify the tracking performance of the reactor power level and ASI. It is known that the proposed controller exhibits very fast tracking responses

  9. The effect of nodalization and temperature of reactor upper region: Sensitivity analysis for APR-1400 LBLOCA

    International Nuclear Information System (INIS)

    Kang, Dong Gu

    2017-01-01

    Highlights: • The nodalization of APR-1400 was modified to reflect the characteristic of upper region temperature. • The effect of nodalization and temperature of reactor upper region on LBLOCA consequence was evaluated. • The modification of nodalization is an essential prerequisite in APR-1400 LBLOCA analysis. - Abstract: In best estimate (BE) calculation, the definition of system nodalization is important step influencing the prediction accuracy for specific thermal-hydraulic phenomena. The upper region of reactor is defined as the region of the upper guide structure (UGS) and upper dome. It has been assumed that the temperature of upper region is close to average temperature in most large break loss of coolant accident (LBLOCA) analysis cases. However, it was recently found that the temperature of upper region of APR-1400 reactor might be little lower than or similar to hot leg temperature through the review of detailed design data. In this study, the nodalization of APR-1400 was modified to reflect the characteristic of upper region temperature, and the effect of nodalization and temperature of reactor upper region on LBLOCA consequence was evaluated by sensitivity analysis including best estimate plus uncertainty (BEPU) calculation. In basecase calculation, in case of modified version, the peak cladding temperature (PCT) in blowdown phase became higher and the blowdown quenching (or cooling) was significantly deteriorated as compared to original case, and as a result, the cladding temperature in reflood phase became higher and the final quenching was also delayed. In addition, thermal-hydraulic parameters were compared and analyzed to investigate the effect of change of upper region on cladding temperature. In BEPU analysis, the 95 percentile PCT used in current regulatory practice was increased due to the modification of upper region nodalization, and it occurred in the reflood phase unlike original case.

  10. Structural assessments of plate type support system for APR1400 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Anh Tung; Namgung, Ihn, E-mail: inamgung@kings.ac.kr

    2017-04-01

    Highlights: • This paper investigates plate-type support structure for the reactor vessel of the APR 1400. • The tall column supports of APR1400 reactor challenges in seismic and severe accident events. • A plate-type support of reactor vessel was proposed and evaluated based on ASME code. • The plate-type support was assessed to show its higher rigidity than column-type. - Abstract: This paper investigates an alternative form of support structure for the reactor vessel of the APR 1400. The current reactor vessel adopts a four-column support arrangement locating on the cold legs of the vessel. Although having been successfully designed, the tall column structure challenges in seismic events. In addition, for the mitigation of severe accident consequences, the columns inhibit ex-vessel coolant flow, hence the elimination of the support columns proposes extra safety advantages. A plate-type support was proposed and evaluated for the adequacy of meeting the structural stiffness by Finite Element Analysis (FEA) approach. ASME Boiler and Pressure Vessel Code was used to verify the design. The results, which cover thermal and static structural analysis, show stresses are within allowable limits in accordance with the design code. Even the heat conduction area is increased for the plate-type of support system, the results showed that the thermal stresses are within allowable limits. A comparison of natural frequencies and mode shapes for column support and plate-type support were presented as well which showed higher fundamental frequencies for the plate-type support system resulting in greater rigidity of the support system. From the outcome of this research, the plate-type support is proven to be an alternative to current APR column type support design.

  11. Development of a Test Facility to Simulate the Reactor Flow Distribution of APR+

    International Nuclear Information System (INIS)

    Euh, D. J.; Cho, S.; Youn, Y. J.; Kim, J. T.; Kang, H. S.; Kwon, T. S.

    2011-01-01

    Recently a design of new reactor, APR+, is being developed, as an advanced type of APR1400. In order to analyze the thermal margin and hydraulic characteristics of APR+, quantification tests for flow and pressure distribution with a conservation of flow geometry are necessary. Hetsroni (1967) proposed four principal parameters for a hydraulic model representing a nuclear reactor prototype: geometry, relative roughness, Reynolds number, and Euler number. He concluded that the Euler number should be similar in the prototype and model under the preservation of the aspect ratio on the flow path. The effect of the Reynolds number at its higher values on the Euler number is rather small, since the dependency of the form and frictional loss coefficients on the Reynolds number is seen to be small. ABB-CE has carried out several reactor flow model test programs, mostly for its prototype reactors. A series of tests were conducted using a 3/16 scale reactor model. (see Lee et al., 2001). Lee et al (1991) performed experimental studies using a 1/5.03 scale reactor flow model of Yonggwang nuclear units 3 and 4. They showed that the measured data met the acceptance criteria and were suitable for their intended use in terms of performance and safety analyses. The design of current test facility was based on the conservation of Euler number which is a ratio of pressure drop to dynamic pressure with a sufficiently turbulent region having a high Reynolds number. By referring to the previous study, the APR+ design is linearly reduced to 1/5 ratio with a 1/2 of the velocity scale, which yields a 1/39.7 of Reynolds number scaling ratio. In the present study, the design feature of the facilities, named 'ACOP', in order to investigate flow and pressure distribution are described

  12. Critical heat flux for APR1400 lower head vessel during a severe accident

    International Nuclear Information System (INIS)

    Noh, Sang W.; Suh, Kune Y.

    2013-01-01

    Highlights: ► Studied boiling on downward-facing hemispherical vessel with asymmetric thermal insulator. ► Scaled the APR1400 lower head linearly down by 1/10 including ICI tubes and shear keys. ► Performed thermal analysis using ANSYS V11.0 to determine the internal temperature and heat flux. ► Performed tests to obtain the CHF with saturated demineralized water at atmospheric pressure. ► Measured CHF accounting for 3D random flow effect expected in the APR1400 application. -- Abstract: Corium Ablation Stopper Apparatus (CASA) has a downward-facing hemispherical vessel and geometrically asymmetric thermal insulator of the Advanced Power Reactor 1400 MWe (APR1400) scaled linearly down by 1/10, as well as sixty-one in-core instrumentation (ICI) tubes and four shear keys. The heated vessel plays a pivotal role in CASA depending on the configuration of the oxide pool and metal layer to bring about the focusing effect expected of a molten pool in the lower head during a severe accident. The heated vessel was designed through a trial-and-error method and thermal analysis. Thermal analysis was performed using ANSYS V11.0 to investigate the effect of the internal temperature and heat flux on the integral hemispherical copper vessel. The CASA tests were carried out to obtain the critical heat flux (CHF) with saturated and demineralized water at the atmospheric pressure (0.1 MPa). The CHF in the metal layer through the hemispherical channel was found to be lower than that in the ULPU-2400 configuration V data through the streamlined thermal insulator. The experimental CHF was measured and obtained through the CASA hemispherical heated surface accounting for the three-dimensional random flow effect expected in the APR1400 application

  13. The Gravity Makeup on the LORHR Event during Mid-loop Operation for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol Woo; Lee, Yong Hee; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO, Daejeon (Korea, Republic of)

    2015-05-15

    This paper is to investigate means of the available gravity makeup after the event to prevent or sustain the core uncovery and fuel failure for the typical advanced power reactor nuclear power plants (APR1400). Unlike the OPR1000 (optimized power reactor 1000 nuclear power plants), the refueling water storage tank of APR1400 cannot be used for gravity makeup since it is located on the bottom of the containment with a lower elevation than the reactor vessel. So, the other means of gravity makeup and their effect on the core uncovery are accounted. The use of the water used for the cask loading pit (CLP) during refueling or the safety injection line filling tank (SIFT), which are not designed for gravity makeup during the event, and safety injection tanks (SITs) are considered as the alternative source of makeup feed. The results show that gravity makeup of a SIT provides a sufficient operator action time for the LORHR with the station black out (SBO) during the mid-loop operation for the APR1400. From the LORHR event analysis, the effective means of gravity makeup for APR1400 to cope with this event concurrent loss of all AC power is determined as the gravity feed using SITs. Other means for gravity makeup using CLP or SIFT, which are not designed to mitigate the LORHR event, are evaluated as not effective to the event due to the large flow resistances and the low elevation head to overcome the system pressure increase during the LORHR. The use of one SIT and two SITs for the LORHR provides the core uncovery times as 3 hr 8 min and 4 hr 32 min extending 1 hr 15 min and 2 hr 38 min from the base case, respectively.

  14. Study on Applicability of 10 CFR Part 21 to APR1400 DC Project

    International Nuclear Information System (INIS)

    Shin, He Young; Lee, Do Hwan; Lim, Jae Yong

    2014-01-01

    The tools such as NCR (non conformance report), CAR (corrective action request) and CAP (corrective action program) are widely used for that purpose based upon the rule of 10 CFR Part 50 Appendix B and the ASME Code NQA-1 requirements. These are the tools for a utility, as a purchaser taking over related basic components and services, to ensure strong quality assurance. During the conduct of the project for the acquisition of the standard design certification for APR1400 nuclear power plants from the U. S. NRC (APR1400 DC Project), a new CAP procedure that is appropriate to conduct this unique project was developed. However, it was also recommended to comply with the requirements under 10 CFR Part 21 which enhances nuclear safety quality assurances. Consequently, a new QA procedure is developed in order to deal with the 10 CFR Part 21 issues and this is integrated to the CAP procedure In this paper, the current corrective action program for the APR1400 DC project is introduced and the result of the study on the applicability of 10 CFR Part 21 to the project is indicated. In addition, further improving aspects to be considered are identified. As a frontier project to obtain the standard design certification for APR 1400 model from the U. S. NRC, a modified CAP procedure is developed and enhanced to deal with safety concerning issues in accordance with 10 CFR Part 21. In addition, the newly established QA procedure to directly control the reportability on 10 CFR Part 21 is interfaced into the existing CAP procedure

  15. An Experimental Investigation on APR1400 Penetration Weld Failure by Metallic Melt

    International Nuclear Information System (INIS)

    An, Sang Mo; Ha, Kwang Soon; Kim, Hwan Yeol

    2014-01-01

    The penetrations are considered as the most vulnerable parts with respect to the reactor vessel failure when a core melt severe accident occurs and the corium reaches the lower head. Penetration tube failure modes can be divided into two categories; tube ejection out of the vessel lower head and rupture of the penetration tube outside the vessel. Tube ejection begins with degrading the penetration tube weld strength to zero as the weld is exposed to temperatures as high as the weld melting temperature, which is called weld failure, and then overcoming any binding force in the hole in the vessel wall that results from differential thermal expansion of the tube and vessel wall. Tube rupture assumes that the debris bed has melted the instrument tube inside the reactor and melt migrates down into the tube to a location outside the vessel wall where a pressure rupture can occur, thus breaching the pressure boundary. In the present paper, we have a focus on the tube ejection failure mode, specifically on the APR1400 weld failure by direct contact with a metallic melt. The objective is to investigate experimentally the ablation kinetics of an APR1400 penetration weld during the interactions with a metallic melt and to suggest the modification of the existing weld failure model. This paper involves the interaction experiments of two different metallic melts (metallic corium and stainless steel melts) with a weld specimen, and rough estimation of weld failure time. The interaction experiments between the metallic melts and an APR1400 penetration weld were performed to investigate the ablation kinetics of the penetration weld. Metallic corium and stainless steel melts were generated using an induction heating technique and interacted with a penetration weld specimen. The ablation rate of the weld specimen showed a range from 0.109 to 0..244 mm/s and thus the APR1400 penetration weld was estimated to be failed at hundreds of times after the interaction with the melt

  16. Seismic analysis of the APR1400 nuclear reactor system using a verified beam element model

    International Nuclear Information System (INIS)

    Park, Jong-beom; Park, No-Cheol; Lee, Sang-Jeong; Park, Young-Pil; Choi, Youngin

    2017-01-01

    Highlights: • A simplified beam element model is constructed based on the real dynamic characteristics of the APR1400. • Time history analysis is performed to calculate the seismic responses of the structures. • Large deformations can be observed at the in-phase mode of reactor vessel and core support barrel. - Abstract: Structural integrity is the first priority in the design of nuclear reactor internal structures. In particular, nuclear reactor internals should be designed to endure external forces, such as those due to earthquakes. Many researchers have performed finite element analyses to meet these design requirements. Generally, a seismic analysis model should reflect the dynamic characteristics of the target system. However, seismic analysis based on the finite element method requires long computation times as well as huge storage space. In this research, a beam element model was developed and confirmed based on the real dynamic characteristics of an advanced pressurized water nuclear reactor 1400 (APR1400) system. That verification process enhances the accuracy of the finite element analysis using the beam elements, remarkably. Also, the beam element model reduces seismic analysis costs. Therefore, the beam element model was used to perform the seismic analysis. Then, the safety of the APR1400 was assessed based on a seismic analysis of the time history responses of its structures. Thus, efficient, accurate seismic analysis was demonstrated using the proposed beam element model.

  17. Single-tube condensation experiment in Passive Auxiliary Feedwater System of APR1400+

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Chang Wook; No, Hee Cheon; Yun, Bong Yo; Jeon, Byong Guk [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-05-15

    Conventional Korean nuclear power plants, Advanced Power Reactors (APR), are characterized by an active cooling system. However, Active cooling system may not prevent significant damage without any AC power source available for its operation as vividly illustrated through the recent Fukushima incident. In the APR1400+ to be designed, an independent passive cooling system was added in order to overcome the aforementioned shortcomings. In the Passive Auxiliary Feedwater System (PAFS), gravity force and density difference between steam and water are used. The system comprises of 240 condensation tubes to efficiently remove decay heat. Before applying the PAFS to APR1400+, the system's safety and heat removal performance must be verified. The present study experimentally evaluates the heat removal performance of a single tube in the PAFS. The objectives of SCOP (Single-tube Condensation experiment facility of PAFS) are the evaluation of the heat removal performance in the tube of the PAFS and database construction under various tube designs and test conditions. Reaching these objectives, we developed advanced measurement techniques for the amount of moisture, heat flux, and water film thickness.

  18. The Alberta Pregnancy Outcomes and Nutrition (APrON) cohort study: rationale and methods.

    Science.gov (United States)

    Kaplan, Bonnie J; Giesbrecht, Gerald F; Leung, Brenda M Y; Field, Catherine J; Dewey, Deborah; Bell, Rhonda C; Manca, Donna P; O'Beirne, Maeve; Johnston, David W; Pop, Victor J; Singhal, Nalini; Gagnon, Lisa; Bernier, Francois P; Eliasziw, Misha; McCargar, Linda J; Kooistra, Libbe; Farmer, Anna; Cantell, Marja; Goonewardene, Laki; Casey, Linda M; Letourneau, Nicole; Martin, Jonathan W

    2014-01-01

    The Alberta Pregnancy Outcomes and Nutrition (APrON) study is an ongoing prospective cohort study that recruits pregnant women early in pregnancy and, as of 2012, is following up their infants to 3 years of age. It has currently enrolled approximately 5000 Canadians (2000 pregnant women, their offspring and many of their partners). The primary aims of the APrON study were to determine the relationships between maternal nutrient intake and status, before, during and after gestation, and (1) maternal mood; (2) birth and obstetric outcomes; and (3) infant neurodevelopment. We have collected comprehensive maternal nutrition, anthropometric, biological and mental health data at multiple points in the pregnancy and the post-partum period, as well as obstetrical, birth, health and neurodevelopmental outcomes of these pregnancies. The study continues to follow the infants through to 36 months of age. The current report describes the study design and methods, and findings of some pilot work. The APrON study is a significant resource with opportunities for collaboration. © 2012 John Wiley & Sons Ltd.

  19. Seismic analysis of the APR1400 nuclear reactor system using a verified beam element model

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong-beom [Department of Mechanical Engineering, Yonsei University, 50 Yonsei-ro, Seodaemun-gu, Seoul 03722 (Korea, Republic of); Park, No-Cheol, E-mail: pnch@yonsei.ac.kr [Department of Mechanical Engineering, Yonsei University, 50 Yonsei-ro, Seodaemun-gu, Seoul 03722 (Korea, Republic of); Lee, Sang-Jeong; Park, Young-Pil [Department of Mechanical Engineering, Yonsei University, 50 Yonsei-ro, Seodaemun-gu, Seoul 03722 (Korea, Republic of); Choi, Youngin [Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon 34142 (Korea, Republic of)

    2017-03-15

    Highlights: • A simplified beam element model is constructed based on the real dynamic characteristics of the APR1400. • Time history analysis is performed to calculate the seismic responses of the structures. • Large deformations can be observed at the in-phase mode of reactor vessel and core support barrel. - Abstract: Structural integrity is the first priority in the design of nuclear reactor internal structures. In particular, nuclear reactor internals should be designed to endure external forces, such as those due to earthquakes. Many researchers have performed finite element analyses to meet these design requirements. Generally, a seismic analysis model should reflect the dynamic characteristics of the target system. However, seismic analysis based on the finite element method requires long computation times as well as huge storage space. In this research, a beam element model was developed and confirmed based on the real dynamic characteristics of an advanced pressurized water nuclear reactor 1400 (APR1400) system. That verification process enhances the accuracy of the finite element analysis using the beam elements, remarkably. Also, the beam element model reduces seismic analysis costs. Therefore, the beam element model was used to perform the seismic analysis. Then, the safety of the APR1400 was assessed based on a seismic analysis of the time history responses of its structures. Thus, efficient, accurate seismic analysis was demonstrated using the proposed beam element model.

  20. Containment Performance Analysis with Large Break LOCA for EU-APR1400

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Keun Sung; Kim, Yong Soo

    2013-01-01

    In this paper for containment performance analysis, the containment pressurization analysis is performed and thermo-hydraulic response analysis of containment structure is carried out to provide basic understanding of containment transient states under a severe accident sequence. Especially, in EU-APR1400 design, to reduce containment pressure and temperature, Severe Accident Containment Spray System (SACSS) is designed to be actuated automatically when Core Exit Temperature (CET) reaches 922 K (649 .deg. C). The containment performance analysis was carried on LBLOCA sequence for EU-APR1400 with SACSS through MAAP code. If SACSS is actuated when CET reaches 922 K (649 .deg. C) , the containment pressure and temperature decrease to a sufficient low level. The predicted atmospheric pressure of containment will not exceed the ultimate pressure capacity (UPC) and have a sufficient margin to it even though the UPC of the reference plant (Shin-Kori Units 3 and 4) is used instead because the UPC calculation for EU-APR1400 has not been completed. The largest load on the containment by LBLOCA is estimated at 306.1 kPa. Thus the margin to UPC is estimated to be 330 % in comparison with 1.329 MPa as UPC for the reference plant.

  1. Assistant Personal Robot (APR: Conception and Application of a Tele-Operated Assisted Living Robot

    Directory of Open Access Journals (Sweden)

    Eduard Clotet

    2016-04-01

    Full Text Available This paper presents the technical description, mechanical design, electronic components, software implementation and possible applications of a tele-operated mobile robot designed as an assisted living tool. This robotic concept has been named Assistant Personal Robot (or APR for short and has been designed as a remotely telecontrolled robotic platform built to provide social and assistive services to elderly people and those with impaired mobility. The APR features a fast high-mobility motion system adapted for tele-operation in plain indoor areas, which incorporates a high-priority collision avoidance procedure. This paper presents the mechanical architecture, electrical fundaments and software implementation required in order to develop the main functionalities of an assistive robot. The APR uses a tablet in order to implement the basic peer-to-peer videoconference and tele-operation control combined with a tactile graphic user interface. The paper also presents the development of some applications proposed in the framework of an assisted living robot.

  2. Effect of the design change of the LSSBP on core flow distribution of APR+ Reactor

    International Nuclear Information System (INIS)

    Kim, Kihwan; Euh, Dong-Jin; Choi, Hae-Seob; Kwon, Tae-Soon

    2014-01-01

    The uniform core inlet flow distribution of an Advanced Power Reactor Plus (APR+) is required to prevent the failure rate of the HIPER fuel assembly and improve the core thermal margin. KEPCO-E and C and KAERI proposed a design change of the Lower Support Structure Bottom Plate (LSSBP), since the core flow rates were intense near the outer region of the intact LSSBP in a previous study. In this study, an experiment was carried out to evaluate the effect of the design change of the LSSBP on the core flow distribution using the APR+ Core Flow and Pressure (ACOP) test facility. The results showed great improvement on the core flow distribution under a 4-pump balanced flow condition. Under the 4-pump balanced flow condition, fifteen tests were repeated using the ACOP test facility to verify the effect of the 50% blocked flow area at the outer region of the LSSBP on the core inlet flow distribution. The profiles of the core inlet mass flow rates were analyzed using ensemble averaged values, and compared with that of the intact LSSBP. The results showed great improvement for the overall core region. The change in design of the LSSBP is expected to improve the hydraulic performance of an APR+ reactor

  3. Radiological Impacts Assessment during Normal Decommissioning Operation for EU-APR

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Do Hyun; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of); Lee, ChongHui [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

    2016-10-15

    In this paper, radiological impacts on human beings during normal execution of the decommissioning operations from the current standard design of EU-APR which has been modified and improved from its original design of APR1400 to comply with EUR, are evaluated. Decommissioning is the final phase in the life cycle of a nuclear installation, covering all activities from shutdown and removal of fissile material to environmental restoration of the site. According to article 5.4 specified in chapter 2.20 of European Utility Requirements (EUR), all relevant radiological impacts on human being should be considered during the environmental assessment of decommissioning, including external exposure from direct radiation of plant and other radiation sources, and internal exposure due to inhalation and ingestion. In this paper, radiological impacts on human beings during normal circumstances of the decommissioning operation were evaluated from the current standard design of EU-APR based on the simple transport model and practical generic methodology for assessing the radiological impact provided by IAEA. The results of dose assessment fulfilled the dose limit for all scenarios.

  4. Main steam line break accident simulation of APR1400 using the model of ATLAS facility

    Science.gov (United States)

    Ekariansyah, A. S.; Deswandri; Sunaryo, Geni R.

    2018-02-01

    A main steam line break simulation for APR1400 as an advanced design of PWR has been performed using the RELAP5 code. The simulation was conducted in a model of thermal-hydraulic test facility called as ATLAS, which represents a scaled down facility of the APR1400 design. The main steam line break event is described in a open-access safety report document, in which initial conditions and assumptionsfor the analysis were utilized in performing the simulation and analysis of the selected parameter. The objective of this work was to conduct a benchmark activities by comparing the simulation results of the CESEC-III code as a conservative approach code with the results of RELAP5 as a best-estimate code. Based on the simulation results, a general similarity in the behavior of selected parameters was observed between the two codes. However the degree of accuracy still needs further research an analysis by comparing with the other best-estimate code. Uncertainties arising from the ATLAS model should be minimized by taking into account much more specific data in developing the APR1400 model.

  5. Les filières de traitement et de valorisation des boues d'épuration en France. Rapport d'enquête

    OpenAIRE

    Richard, M.; Pradel, M.

    2014-01-01

    / Irstea, en partenariat avec l'Onema, étudie les impacts environnementaux des filières de traitement et de valorisation/élimination des boues d'épuration présentes dans les stations de traitement des eaux usées (STEU) en France. Dans le cadre de la conception et de la structuration d'un outil ACV simplifié, la connaissance des filières boues mises en place en France est nécessaire. Ainsi, une enquête au niveau national a été menée en 2014. L'objectif de cette enquête est dans un premier t...

  6. LA NOTION DE TORTURE, DE TRAITEMENTS INHUMAINS ET DEGRADANTS DANS LA JURISPRUDENCE DE LA COUR EUROPEENNE DES DROITS DE L’HOMME

    Directory of Open Access Journals (Sweden)

    Jean-Paul Céré

    2017-03-01

    Full Text Available En vertu de l'article 3 de la Convention européenne de sauvegarde des droits de l'homme, les Etats ne peuvent ni pratiquer la torture ni infliger des traitements inhumains ou dégradants. Le particularisme de cette convention par rapport aux autres textes internationaux ou régionaux relatifs aux droits de l’homme réside indéniablement dans le système de protection existant qu’elle a organisé. Un organe juridictionnel, la cour européenne des droits de l’homme, est en charge de sanctionner les Etats qui ne respectent la Convention. Au terme d’une jurisprudence novatrice et évolutive, la cour européenne des droits de l’homme impose de plus en plus efficacement de lutter contre la torture, les traitements inhumains et dégradants.

  7. Evaluation of Ablation rate by the change of Sacrificial Material for PECS in EU-APR

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Do Hyun; Kim, Yong Soo; Lee, Keun Sung [KHNP-CRI, Daejeon (Korea, Republic of)

    2015-05-15

    EU-APR, modified and improved from its original design of APR1400, has been developed to comply with European Utility Requirements (EUR) and nuclear design requirements of the European countries. In EU-APR, Severe Accident Mitigation Systems are dedicated to providing an independent defense line from that of Engineered Safety Feature (ESF) and Diverse Safety Feature (DSF). They consist of Emergency Reactor Depressurization System (ERDS), Passive Ex-vessel corium retaining and Cooling System (PECS), Severe Accident Containment Spray System (SACSS), Hydrogen Mitigation System (HMS) and Containment Filtered Vent System (CFVS). The PECS, so called core catcher, was introduced to prevent the Molten Core Concrete Interaction (MCCI) after Reactor Vessel (RV) failure. The PECS has experienced a lot of changes from its original design. Recently, the most significant change was that as a SM, limestone concrete is installed on PECS's body wall instead of previous sacrificial material rich in Fe{sub 2}O{sub 3}. The main reason of this design change is to overcome the issue that the sacrificial material is ablated rather too fast when reacting with corium that contains a large fraction of Zr metal. Other changes in the geometry of PECS's wall and downcomer design are considered as minor ones. In this paper, the comparison of ablation rates between previous SM and limestone concrete is carried out using MAAP5 code with respective MCCI model according to the material. In this paper, major improvements of MAAP5 model for PECS in EU-APR are presented and the evaluation of ablation rate for the previous SM model and the new LC model is carried out by means of ablation depths with LBLOCA sequence. Two models have respective unique ablation process. The ablation of LC model proceeds at a constant rate regardless of water while the ablation of SM model proceeds at a faster rate before the arrival of cooling water for corium and SM mixture. The change of sacrificial material

  8. Analytical Assessment of Environmental Impact for APR1400DC UHS Cooling Tower

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jaiho [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Hot process water is pumped from the plant process to the cooling towers. Heat is rejected through evaporation of the process water, interacting with ambient air blown upward by fans.. Plumes generated from exit ports of the cooling tower may have adverse effects on the environment, such as deposition of cooling tower drift release, fogging, icing, shadowing, and ground-level temperature and humidity increase. These kinds of environmental impact of the cooling tower are linked closely with the dispersion of the cooling tower plumes. In this respect, predicting the behavior of the plumes has become one of the most important issues in the environmental assessments of the cooling towers. The SACTI (seasonal/annual cooling tower impact) model is an analytical tool to predict the environmental effect of cooling tower, which was developed by Argonne National Laboratory and University of Illinois with support from EPRI (electric power research institute). The initial version of SACTI has been widely used to assess the environmental effect of cooling towers in many industrial fields such as steam power plants and NPPs. Guo et. al. investigated impact of heat rejection and cooling tower height on plume dispersion using the SACTI model, for the purpose of the future construction of inland NPPs. They found that increasing cooling tower height decreases the plume length and height frequencies. Their simulation results showed that the increase in heat rejection increases the plum radius frequency. The APR1400DC is an advanced light water reactor developed for the purpose of NRC-DC (design certification). The cooling towers for APR1400DC UHS consist of two linear mechanical draft cooling towers (LMDCTs). The LMDCT for APR1400DC UHS is conceptually designed because the plant site has not been decided yet. In the present study, the dependency of plume dispersion on the number of cooling towers is investigated using SACTI-2-beta, for predicting annual environmental effect of APR

  9. Evaluation of Ablation rate by the change of Sacrificial Material for PECS in EU-APR

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Kim, Yong Soo; Lee, Keun Sung

    2015-01-01

    EU-APR, modified and improved from its original design of APR1400, has been developed to comply with European Utility Requirements (EUR) and nuclear design requirements of the European countries. In EU-APR, Severe Accident Mitigation Systems are dedicated to providing an independent defense line from that of Engineered Safety Feature (ESF) and Diverse Safety Feature (DSF). They consist of Emergency Reactor Depressurization System (ERDS), Passive Ex-vessel corium retaining and Cooling System (PECS), Severe Accident Containment Spray System (SACSS), Hydrogen Mitigation System (HMS) and Containment Filtered Vent System (CFVS). The PECS, so called core catcher, was introduced to prevent the Molten Core Concrete Interaction (MCCI) after Reactor Vessel (RV) failure. The PECS has experienced a lot of changes from its original design. Recently, the most significant change was that as a SM, limestone concrete is installed on PECS's body wall instead of previous sacrificial material rich in Fe 2 O 3 . The main reason of this design change is to overcome the issue that the sacrificial material is ablated rather too fast when reacting with corium that contains a large fraction of Zr metal. Other changes in the geometry of PECS's wall and downcomer design are considered as minor ones. In this paper, the comparison of ablation rates between previous SM and limestone concrete is carried out using MAAP5 code with respective MCCI model according to the material. In this paper, major improvements of MAAP5 model for PECS in EU-APR are presented and the evaluation of ablation rate for the previous SM model and the new LC model is carried out by means of ablation depths with LBLOCA sequence. Two models have respective unique ablation process. The ablation of LC model proceeds at a constant rate regardless of water while the ablation of SM model proceeds at a faster rate before the arrival of cooling water for corium and SM mixture. The change of sacrificial material also

  10. A Source Term Calculation for the APR1400 NSSS Auxiliary System Components Using the Modified SHIELD Code

    International Nuclear Information System (INIS)

    Park, Hong Sik; Kim, Min; Park, Seong Chan; Seo, Jong Tae; Kim, Eun Kee

    2005-01-01

    The SHIELD code has been used to calculate the source terms of NSSS Auxiliary System (comprising CVCS, SIS, and SCS) components of the OPR1000. Because the code had been developed based upon the SYSTEM80 design and the APR1400 NSSS Auxiliary System design is considerably changed from that of SYSTEM80 or OPR1000, the SHIELD code cannot be used directly for APR1400 radiation design. Thus the hand-calculation is needed for the portion of design changes using the results of the SHIELD code calculation. In this study, the SHIELD code is modified to incorporate the APR1400 design changes and the source term calculation is performed for the APR1400 NSSS Auxiliary System components

  11. Une chaîne de traitement de l'information géographique au service de l'application de la loi Littoral

    Directory of Open Access Journals (Sweden)

    Patrick GUILLOPÉ

    1994-09-01

    Full Text Available L’application de la loi Littoral nécessitait une approche nouvelle de la part de l’État et la mise en œuvre d’outils nouveaux pour une gestion à long terme. L’apport de traitements automatiques de l’information géographique a été ainsi testé au CETE Normandie-Centre sur trois des grands principes posés par cette loi.

  12. Insecticidal activity of the metalloprotease AprA occurs through suppression of host cellular and humoral immunity.

    Science.gov (United States)

    Lee, Seung Ah; Jang, Seong Han; Kim, Byung Hyun; Shibata, Toshio; Yoo, Jinwook; Jung, Yunjin; Kawabata, Shun-Ichiro; Lee, Bok Luel

    2018-04-01

    The biochemical characterization of virulence factors from entomopathogenic bacteria is important to understand entomopathogen-insect molecular interactions. Pseudomonas entomophila is a typical entomopathogenic bacterium that harbors virulence factors against several insects. However, the molecular actions of these factors against host innate immune responses are not clearly elucidated. In this study, we observed that bean bugs (Riptortus pedestris) that were injected with P. entomophila were highly susceptible to this bacterium. To determine how P. entomophila counteracts the host innate immunity to survive within the insect, we purified a highly enriched protein with potential host insect-killing activity from the culture supernatant of P. entomophila. Then, a 45-kDa protein was purified to homogeneity and identified as AprA which is an alkaline zinc metalloprotease of the genus Pseudomonas by liquid chromatography mass spectrometry (LC-MS). Purified AprA showed a pronounced killing effect against host insects and suppressed both host cellular and humoral innate immunity. Furthermore, to show that AprA is an important insecticidal protein of P. entomophila, we used an aprA-deficient P. entomophila mutant strain (ΔaprA). When ΔaprA mutant cells were injected to host insects, this mutant exhibited extremely attenuated virulence. In addition, the cytotoxicity against host hemocytes and the antimicrobial peptide-degrading ability of the ΔaprA mutant were greatly decreased. These findings suggest that AprA functions as an important insecticidal protein of P. entomophila via suppression of host cellular and humoral innate immune responses. Copyright © 2017 Elsevier Ltd. All rights reserved.

  13. Evaluation of the Main Steam Line Break Accident for the APR+ Standard Design using MARS-KS

    Energy Technology Data Exchange (ETDEWEB)

    Park, M. H.; Kim, Y. S.; Hwang, Min Jeong; Sim, S. K. [Environment Energy Technology, Daejeon (Korea, Republic of); Bang, Young Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    As a part of licensing evaluation of the APR+ (Advanced Power Reactor +) standard design, Korea Institute of Nuclear Safety(KINS) performed safety evaluation of the APR+ Standard Safety Analysis Report(SSAR). The results of the safety evaluation of the APR+ Main Steam Line Break(MSLB) accident is presented for the most limiting post-trip return-to-power case with the single failure assumption of the Loss Of Offsite Power(LOOP). MARS-KS regulatory safety analysis code has been used to evaluate safety as well as the system behavior during MSLB accident. The MARS-KS analysis results are compared with the results of the MSLB safety analysis presented in the SSAR of the APR+. Independent safety evaluation has been performed using MARS-KS regulatory safety analysis code for the APR+ MSLB accident inside containment for the limiting case of the full power post-trip return-to-power. The results of MARS-KS analysis were compared with the results of the MSLB safety analysis presented in the APR+ SSAR. Due to higher cooldown of the MARS-KS analysis, the MARS-KS analysis results in a higher positive reactivity insertion into the core by the negative moderator and fuel temperature reactivity coefficients than the APR+ SSAR analysis. Both results show no return-to-power during the limiting case of the MSLB inside containment. However, APR+ SSAR moderator temperature reactivity insertion should be evaluated against the MARS-KS moderator density reactivity insertion for is conservatism. This study also clearly shows asymmetric thermal hydraulic behavior during the MSLB accident at intact and affected sides of the downcomer and the core. These asymmetric phenomena should be further investigated for the effects on the system design.

  14. Decontamination of irradiated fuel processing waste using lead paraperiodate; Decontamination des effluents de traitement des combustibles irradies par le paraperiodate de plomb

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1967-07-01

    The process is designed to eliminate ruthenium. It consists in an oxidation using para-periodic acid whose excess, acting then as a carrying-over agent, is precipitated in the form of a lead salt at a pH of 5 or 6. This process makes it possible to precipitate 80 to 98 per cent of the ruthenium which is not removed by the conventional precipitation techniques which follow it. If the waste is a reducing agent, it is pre-oxidized using ozone or potassium permanganate. The process was developed at Marcoule in 1963 and has since 1965 been applied industrially; its cost price is of the same order of magnitude as conventional processes and its results are satisfactory. (author) [French] Le procede est destine a l'elimination du ruthenium. Il consiste en une oxydation par l'acide par paraperiodique dont l'exces, jouant alors le role d'entraineur, est precipite sous forme de sel de plomb a pH 5 ou 6. Ce traitement permet de precipiter 80 a 98 pour cent du ruthenium rebelle aux traitements de precipitation classique, qui doivent le suivre. Si l'effluent est reducteur il est preoxyde a l'ozone ou au permanganate de potassium. Mis au point a Marcoule en 1963, il est depuis 1965 exploite industriellement, son prix de revient est du meme ordre de grandeur que celui des traitements habituels et les resultats ont donne satisfaction. (auteur)

  15. Study of various decontamination processes for evaporation concentrates; Etude de differents traitements de decontamination sur des concentrats d'evaporation

    Energy Technology Data Exchange (ETDEWEB)

    Lefillatre, G; Cudel, Y; Rodi, L [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1968-07-01

    insolubiliser les radioelements contenus dans les concentrats avant leur enrobage eventuel par le bitume. Dans ce but, la fixation sur des produits mineraux, la precipitation sous forme de sels insolubles ou l'adsorption sur des coprecipites ont ete envisagees. Dans le cas de la fixation des radioelements par des produits mineraux d'origine naturelle ou synthetique a pouvoir absorbant eleve tels que: argiles, diatomees, silicates synthetiques et alumines, 48 produits ont ete experimentes. Leur efficacite selective vis-a-vis du {sup 137}Cs - {sup 90}Sr - {sup 106}Ru-Rh - {sup 144}Ce-Pr - {sup 95}Zr-Nb a ete determinee d'une part sur des concentrats acides, d'autre part sur des concentrate neutralises (precipitation des hydroxydes). Dans le cas de la fixation des radioelements a l'etat de sels insolubles ou de leur adsorption sur des coprecipites, le choix des traitements a porte sur les 2 radioelements les plus dangereux: {sup 137}Cs - {sup 90}Sr. Les traitements classiques ont ete experimentes. Pour le {sup 90}Sr: carbonate de calcium, oxalate de calcium, phosphate de calcium, phosphate de strontium, oxydes de manganese, sulfate de baryum. Pour le {sup 137}Cs: les ferrocyanures de nickel, de cuivre, de zinc, de cobalt, de manganese. La technique a consiste a effectuer les precipitations (hydroxydes, traitements specifiques du {sup 90}Sr et {sup 137}Cs) les unes a la suite des autres sans separer les precipites. (auteurs)

  16. Special equipment for processing can-rupture measurements; Equipement specialise de traitement des mesures de rupture de gaines

    Energy Technology Data Exchange (ETDEWEB)

    Kaiser, J.; Phalippou, J.; Dumont, D.; Viellard, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    installees sur des reacteurs nucleaires utilisent dans la partie du traitement des mesures en totalite ou en partie un calculateur numerique. La fiabilite du systeme est limitee par celle du calculateur, celui-ci representant un point commun pour tout le traitement DRG. Pour satisfaire aux exigences de la securite de fonctionnement il faudrait envisager dans certains cas de doubler le calculateur. L'utilisation d'un calculateur necessite comme interface entre l'equipement de detection et lui-meme des echelles fonctionnant en integrateur pour les impulsions sortant du detecteur. En ajoutant un certain nombre de circuits a ces echelles on est capable d'effectuer le travail demande actuellement au calculateur, en ce qui concerne le calcul. Ce raisonnement nous a conduit a une solution dite ''decentralisee'' en realisant des equipements specialises au niveau du prospecteur meme. Nous croyons que cette solution represente, en dehors de l'aspect de fiabilite, surtout un interet economique. Dans notre solution, le point commun dans le traitement d'information se situe maintenant non plus au niveau d'elaboration du resultat comme dans le cas du calculateur, mais a un niveau plus bas, dans l'impression des resultats. Meme dans le cas d'une defaillance du point commun, les resultats sont elabores, affiches et compares aux seuils d'alarme. Dans le cas d'une panne d'un equipement specialise les resultats de ce prospecteur ne sont plus disponibles, les autres restent en fonction. Il semble que cette solution represente un degre de fiabilite meilleur que la solution utilisant les calculateurs universels. L'utilisation d'une technique a tiroir interchangeable (MULTIBLOC) permet un remplacement rapide de l'equipement specialise en panne. L'emploi systematique des circuits integres (TTL) assure une fiabilite accrue de l'equipement. (auteur)

  17. Les pratiques littéraciées bidisciplinaires lettres-histoire dans le secondaire : vers la construction d'une culture humaniste moins différenciatrice pour les élèves de milieu populaire ?

    Directory of Open Access Journals (Sweden)

    Rossignol Marie-France

    2015-01-01

    Full Text Available Dans le contexte de massification et de multiculturalisme qui caractérise actuellement l'enseignement secondaire français, la nécessité de dispenser une culture commune à donner en partage à tous les élèves se trouve mise sur le devant de la scène scolaire. Les dernières réformes en cours présentent cet objectif comme prioritaire. Ainsi les nouveaux programmes de 2006 réinstitutionnalisent la « culture humaniste », héritière de la culture scolaire originelle, et la confient aux disciplines littéraires, français et histoire, ainsi qu'aux disciplines artistiques. Cette restauration pose la question vive de l'appropriation chez les élèves de milieu populaire d'une telle forme de culture, d'ordre scripturaire, fondée sur la lecture de textes patrimoniaux, en particulier littéraires, mobilisant des ressources cognitives et culturelles de haut niveau. Comment leur donner accès à une littératie humaniste très éloignée de leurs pratiques socioculturelles de référence habituelles sans risquer d'accroître les écarts avec les élèves socialement plus favorisés, davantage familiarisés à cette forme culturelle ? Une recherche exploratoire est menée à partir d'un dispositif bidisciplinaire français-histoire expérimental, mis en œuvre par des praticiens confirmés, dans trois classes d'établissements du secondaire de la banlieue parisienne accueillant des élèves d'origine modeste. L'analyse des productions écrites et orales des élèves montre que la pratique d'une littératie humanisteen contexte bidisciplinaire favorise chez eux l'entrée dans l'apprentissage de la culture humaniste scolaire, et, sur un mode certes très différencié, les conduit à mieux se l'approprier.

  18. The reprocessing of irradiated fuels improvement and extension of the solvent extraction process; Le traitement des combustibles irradies amelioration et extension du procede utilisant les solvants

    Energy Technology Data Exchange (ETDEWEB)

    Faugeras, P; Chesne, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    Improvements made in the conventional tri-butylphosphate process are described, in particular. the concentration and the purification of plutonium by one extraction cycle using tri-butyl-phosphate with reflux; and the use of an apparatus working continuously for precipitating plutonium oxalate, for calcining the oxalate, and for fluorinating the oxide. The modifications proposed for the treatment of irradiated uranium - molybdenum alloys are described, in particular, the dissolution of the fuel, and the concentration of the fission product solutions. The solvent extraction treatment is used also for the plutonium fuels utilized for the fast breeder reactor (Rapsodie) An outline of the process is presented and discussed, as well as the first experimental results and the plans for a pilot plant having a capacity of 1 kg/day. The possible use of tn-lauryl-amine in the plutonium purification cycle is now under consideration for the processing plant at La Hague. The flowsheet for this process and its performance are presented. The possibility of vitrification is considered for the final treatment of the concentrated radioactive wastes from the Marcoule (irradiated uranium) and La Hague (irradiated uranium-molybdenum) Centers. Three possible processes are described and discussed, as well as the results obtained from the operation of the corresponding experimental units using tracers. (authors) [French] On decrit les ameliorations apportees au procede classique utilisant le phosphate tributylique, et notamment la concentration et la purification du plutonium par un cycle d'extraction au tributylphosphate avec reflux, l'utilisation d'un appareillage continu de precipitation d'oxalate de plutonium, de calcination de l'oxalate, et de fluoration de l'oxyde. On presente les modifications envisagees pour le traitement des alliages uranium-molybdene irradies, principalement en ce qui concerne la dissolution du combustible et la concentration des solutions de produits de fission

  19. APR1400 Electrical Power System Conformance to SECY-91-078

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Che-Wung; Kim, Yun-Ho [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, the APR1400 electric power system for NRC-DC was described. In addition, the conformance to SECY 91-078 was evaluated. Enclosure 1 of the SECY provides an overview of the issue and states that the staff concludes that feeding the safety buses from the offsite power sources through non-safety buses or from a common transformer winding with non-safety loads is not the most reliable configuration. Such an arrangement increases the difficulty in properly regulating voltage at the safety buses, subjects the safety loads to transients caused by the non-safety loads, and adds additional failure points between the offsite power sources and safety loads. Therefore, it is the staff’s position that at least one offsite circuit to each redundant safety division should be supplied directly from one of the offsite power sources with no intervening non-safety buses, in such a manner that the offsite source can power the safety buses upon a failure of any non-safety bus. The APR1400 does not have an intervening nonsafety bus in the current offsite to onsite electrical configuration; however, the design does include nonsafety and safety buses coming from the same secondary side 4.16 kV transformer winding. Nevertheless, the APR1400 has designed the electrical interface system between offsite and onsite power with enhanced reliability measures to ensure that the nonsafety system will not impact the safety loads. The design complies with GDC 17 and also conforms to SECY-91-078.

  20. Development of phenomena identification and ranking table for APR1400 main steam line break

    International Nuclear Information System (INIS)

    Song, J. H.; Chung, B. D.; Jeong, J. J.

    2003-01-01

    A Phenomena Identification and Ranking Table (PIRT) was developed for the Main Steam Line Break (MSLB) event of an APR-1400 (Advanced Power Reactor-1400). A team of experts from research institutes, industries, and regulatory bodies participated in the development. The selected event was a double-ended steam line break at full power with the reactor coolant pump running. The panel selected the fuel performance as the primary safety criterion for ranking. The plant design data, the results of APR-1400 safety analysis, and the results of additional best estimate analysis by MARS2.1 were utilized. Three phases of pre-trip, rapid cool-down, and safety injection phase were identified. Then, the ranking of a system, components, phenomenon/process based on the relative importance to the primary evaluation criterion were followed for each time phase. Finally, the knowledge-level for each important process in the component was ranked in terms of the existing knowledge. The highly ranked phenomena identified for APR-1400 MSLB are tube wall heat transfer at the steam generator shell, void distribution at the steam generator shell, liquid entrainment in the separators, mixture level in the separators, boron mixing in the upper down comer, boron transport and thermal mixing in the lower plenum, stored energy release in the upper head, and flow to and/from the upper head. The PIRT will be used as a guide in planning cost effective experimental programs and code development efforts, especially for the quantification of the process and/or phenomena, which have a high importance but low knowledge level

  1. Radioactive Waste Control at the United Kingdom Atomic Energy Research Establishment, Harwell; Traitement des Dechets Radioactifs au Centre de Recherche sur l'Energie Atomique de Harwell; 041a 041e 041d 0422 0420 041e 041b 042c 0417 0410 0423 0414 ; Control de Desechos Radiactivos en el A.E.R.E., Harwell

    Energy Technology Data Exchange (ETDEWEB)

    Burns, R. H. [United Kingdom Atomic Energy Authority (United Kingdom)

    1960-07-01

    The paper outlines the present practices in the control and treatment of radioactive wastes at Harwell. The large-volume, low-level active liquid effluent is treated by phosphate coagulation methods and, eventually, discharged to the River Thames. The medium-level wastes are segregated and undergo a two-stage chemical treatment followed by passage through columns of Vermiculite. The latter process has been found to be effective in removing radoicaesium, which is not dealt with efficiently by the precipitation methods used. Liquid wastes with a high- activity content are stored and a new plant, incorporating chemical treatment, ion exchange and evaporation, is being installed. The chemical sludges formed in the treatment processes are dumped at sea after de-watering by filtration. The contaminated solid waste is either stored or disposed of at sea. It is important to reduce the volume as much as possible and the methods employed include pressure baling, melting and incineration of combustible matter. Small quantities of activity are discharged to the atmosphere through exhaust stacks. The cleaning of this discharge air is commonly achieved by the use of high-efficiency filters or liquid scrubbing systems. Regular stack monitoring is carried out and this is backed up by a comprehensive district sampling programme. (author) [French] L'auteur decrit les methodes de controle et de traitement des dechets radioactifs qui sont appliquees au Centre de Harwell. Le volume considerable des effluents liquides de faible activite est traite par des methodes de coagulation au moyen des phosphates, puis evacue dans la Tamise. Apres separation, les dechets d'activite moyenne sont soumis a un traitement chimique en deux temps, avant de traverser des colonnes de Vermiculite. On a constate que ce dernier processus eliminait le radio- cesium, ce que les methodes de precipitation utilisees ne permettent pas de faire de maniere efficace. Les dechets liquides d'activite intense sont

  2. Chemical treatment proceed of poor uranium content ores; Un procede de traitement chimique des minerais pauvres d'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Mouret, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Pagny, P [Societe Potasse et Engrais Chimiques (France)

    1955-07-01

    The needs in uranium constantly increased inciting to develop new chemical processes for the treatment of uranium ores. we searched processes that permit to get this element from ores poor in uranium, to a reasonable cost price. We used a sulphuric attack and a precipitation of uranium as phosphate uranate or pyrophosphate uranate to separate its from the different impurities. The process permitted to process ores contents of about 0,05% of uranium and to get an end product of sodium carbonate uranate containing 60 to 65% of uranium, with an acceptable cost price and an extraction yield situated between 90 and 95%. (M.B.) [French] Les besoins sans cesse accrus en uranium ont incite de developper de nouveaux procedes chimiques pour le traitement de minerais uranifere. nous avons recherche des procedes qui permettent d'obtenir cet element a partir de minerais pauvres en uranium, a un prix de revient raisonnable. Nous nous sommes orientes vers une attaque sulfurique et une precipitation de l'uranium sous forme de phosphate uraneux ou de pyrophosphate uraneux pour le separer des differentes impuretes. Le procede a permis de descendre a des teneurs en uranium de l'ordre de 0,05 % et d'obtenir un produit final a l'etat d'uranate de soude contenant 60 e 65 % d'uranium, avec un prix de revient acceptable et avec un rendement global d'extraction situe entre 90 et 95 %. (M.B.)

  3. Two cases of physical treatment of uranium ore; Deux cas de traitement physique de minerai d'uranium

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    Until now, all uranium deposits exploited in France are vein type and present a very big variety of mineralization and structure. The process of concentration of these ores requires a study for each of them and, in a lot of cases, only the chemical attack can solve the problem. However, the flotation succeeded to results permitting a very interesting enrichment with lower investments expenses and cost prices. Enrichment by flotation would be foreseeable for poor layers and weak tonnage, permitting to absorb facilities on tonnages three times less important than the acidic treatment, or, to equality of cost price, to treat ores having contents of 2,5 to 4 times weaker. (M.B.) [French] Jusqu'ici, tous les gisements uraniferes exploites en France sont du type filonien et presentent une tres grande variete de mineralisation et de structure. Le procede de concentration de ces minerais necessite une etude pour chacun d'eux et, dans bien des cas, seule l'attaque chimique peut resoudre le probleme. Toutefois, la flottation a abouti a des resultats permettant un enrichissement tres interessant avec les depenses d'investissements et des prix de revient beaucoup plus bas. Un enrichissement par flottation serait envisageable pour des gisements pauvres et de faible tonnage, permettant d'amortir les installations sur des tonnages trois fois moins importants que le traitement acide, ou encore, a egalite de prix de revient, de traiter des minerais ayant des teneurs de 2,5 a 4 fois plus faibles. (M.B.)

  4. Le traitement informatisé de ressources électroniques au Service de l'Information Scientifique du CERN

    CERN Document Server

    Pignard, Nathalie; Jerdelet, Jocelyne

    2001-01-01

    Nous présentons une méthode automatique d'importation de données mise en oeuvre au Service de l'Information Scientifique, SIS, du CERN. Ce programme informatique, baptisé Uploader, permet d'importer dans le catalogue de la bibliothèque du CERN des notices bibliographiques et le texte intégral de documents provenant de diverses sources sur Internet. Ces bases de données concernent la littérature grise en physique et dans les disciplines voisines (par exemple DOE, KEK, Math-Doc, TipTop, etc.). Cette politique d'acquisition, qui met en avant le traitement informatisé des ressources électroniques, soulève quelques réflexions sur l'augmentation du nombre de documents collectés et sur l'élargissement des domaines traités. Le souci constant d'enrichir ces données et d'en faciliter l'accès aux utilisateurs, sur un mode hypertextuel, conduit à une évolution des métiers de la gestion documentaire.

  5. Cloned Bacillus subtilis alkaline protease (aprA) gene showing high level of keratinolytic activity.

    Science.gov (United States)

    Zaghloul, T I

    1998-01-01

    The Bacillus subtilis alkaline protease(aprA) gene was previously cloned on a pUBHO-derivative plasmid. High levels of expression and gene stability were demonstrated when B. subtilis cells were grown on the laboratory medium 2XSG. B. subtilis cells harboring the multicopy aprA gene were grown on basal medium, supplemented with 1 % chicken feather as a source of energy, carbon, and nitrogen. Proteolytic and keratinolytic activities were monitored throughout the cultivation time. A high level of keratinolytic activity was obtained, and this indicates that alkaline protease is acting as a keratinase. Furthermore, considerable amounts of soluble proteins and free amino acids were obtained as a result of the enzymatic hydrolysis of feather. Biodegradation of feather waste using these cells represents an alternative way to improve the nutritional value of feather, since feather waste is currently utilized on a limited basis as a dietary protein supplement for animal feedstuffs. Moreover, the release of free amino acids from feather and the secreted keratinase enzyme would promote industries based on feather waste.

  6. Extended Station Blackout Analyses of an APR1400 with MARS-KS

    International Nuclear Information System (INIS)

    Kim, WoongBae; Jang, HyungWook; Oh, Seungjong; Lee, Sangyong

    2016-01-01

    The Fukushima Dai-ichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electricity required for essential systems during a station blackout is provided from the emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6 and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating of extended station blackout scenarios, the best estimate MARS-KS was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study was performed on reactor coolant pump seal leakage

  7. PLUS 7TM advanced fuel assembly development program for KSNPs and APR1400

    International Nuclear Information System (INIS)

    Kim, Kyutae; Stucker, David L.

    2002-01-01

    KNFC and Westinghouse have recently completed the development of the PLUS 7 TM advanced 16 X 16 fuel assembly for the Korean Standard Nuclear Plants (KSNPs) and the Advanced Power Reactor 1400 (APR 1400). This fuel design utilized the proven advanced design features including mixing vane spacer grids to increase critical heat flux performance, ZIRLO TM advanced materials to enable high-duty, high burnup fuel management and an optimized fuel rod diameter which improves fuel cycle cost while resulting in significant standardization of Korean fuel manufacture. PLUS 7 TM , also includes a patented spacer grid design with conformal fuel rod support designed to provide superior fuel rod wear/fretting resistance while minimizing pressure drop. This paper will present an overview of the PLUS 7 TM fuel assembly development process including a summary of the three-year design and testing program from a mechanical, neutronic, and thermal/hydraulic perspective. The PLUS 7 TM fuel for the KSNPs and the APR1400 reactors results in multi-million dollar per cycle savings in imported enriched uranium product for the Korean nuclear power program with technology specifically developed for Korea by experienced Korean engineers

  8. Analysis of a 12-Finger Rod Drop using RETRAN/MASTER Code System for APR1400

    International Nuclear Information System (INIS)

    Yu, Keuk Jong; You, Sung Chang; Kim, Han Gon

    2009-01-01

    The Optimized Power Reactor 1000 (OPR1000) has 4-finger and 12-finger Control Element Assemblies (CEAs). When the 12-finger CEA is dropped, Core Protection Calculator System (CPCS) shuts down the reactor to prevent fuel damage that could occur from the sudden reactor power peaking. By contrast, the improved CPCS of Advanced Power Reactor 1400 (APR1400), which has systems similar to those of the OPR1000, decreases reactor power rapidly using its Reactor Power Cutback System (RPCS) to avoid unwanted reactor trips caused by the CPCS during a 12- finger CEA drop event. RETRAN is a best-estimate code for transient analysis of Non-LOCA. The RETRAN control logic, which includes the function of reducing reactor power during a 12-Finger CEA drop, has been developed for the APR1400. A MATRAN program has also been developed. MATRAN is the interface program for realtime processing to connect RETRAN with MASTER code which is a nuclear analysis and design code. MATRAN supplies adequate feedback reactivities from the MASTER code to RETRAN code. The purpose of this study is to analyze the behavior of a nuclear reactor core and its primary system using conventional RETRAN analysis procedure and MATRAN program analysis procedure during a 12- finger CEA drop. In addition, the axial power distribution and Axial Shape Index (ASI) are produced by the MATRAN program and they are confirmed as within operation limits

  9. Review of EU-APR Design for Selected Safety Issues of WERNA RHWG 2013

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Soo; Kim, Ji Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Western European Nuclear Regulators' Association (WENRA) was established in 1999 to develop a harmonized approach to nuclear safety and radiation protection and their regulation. In 2013, the Reactor Harmonization Working Group (RHWG) of WENRA sets out the common positions on the seven selected key safety issues. This paper is to introduce the regulatory positions of WENRA RHWG 2013 and to review the compliance of the EU-APR with them. In this paper, we reviewed the compliance of the EUAPR regarding seven safety issues for new NPPs presented by WERNA RHWG in 2013. The EU-APR design fully complies with all WERNA RHWG safety issues since the following measures have been incorporated in it: - Successive five levels of DiD maintaining independence between different levels of DiD - Diverse design against multiple failure events such as ATWS, SBO, Loss of Ultimate Heat Sink, and Loss of Spent Fuel Pool Cooling - SAs dedicated mitigation systems to ensure the containment integrity during the SAs. - Practically eliminates accident sequences with a large or early release of radiological materials by diverse designs for multiple failure events, SAs dedicated mitigation system, and double containment design - Standard site parameters not lead to core melt accidents due to natural or man-made external hazards.

  10. Evaluation of Coolant Injection Procedure in the Severe Accident Management Strategy of APR1400

    International Nuclear Information System (INIS)

    Cho, Yongjin; Lim, Kukhee; Song, Sungchu; Lee, Sukho; Hwang, Taesuk

    2013-01-01

    A coolant injection strategy in the severe accident management guideline (SAMG) of APR1400 relates to immediate coolant injection into RCS (Reactor Coolant System) or injection following the recovery of secondary coolant inventory. This strategy could play important role in accident mitigation and radiological consequences. In this study, appropriateness of the strategy was evaluated using MELCOR1.8.6 and several sensitivity studies of the key parameters were performed. Analysis for APR1400 using MELCOR 1.8.6 was performed to evaluate the effectiveness of accident management strategies and the following conclusions were identified. Sequential operation of secondary and RCS injection may not be the best strategy and the simultaneous injection of secondary and RCS injection could be more preferable. At least, the RCS injection should start before complete drainage of water in the safety injection tank using mobile pumps. In this study, the effectiveness of timing of operator action has been examined and the amount of injection flowrate needs to be studied in the future

  11. Post-test analysis for the APR1400 LBLOCA DVI performance test using MARS

    International Nuclear Information System (INIS)

    Bae, Kyoo Hwan; Lee, Y. J.; Kim, H. C.; Bae, Y. Y.; Park, J. K.; Lee, W.

    2002-03-01

    Post-test analyses using a multi-dimensional best-estimate analysis code, MARS, are performed for the APR1400 LBLOCA DVI (Direct Vessel Injection) performance tests. This report describes the code evaluation results for the test data of various void height tests and direct bypass tests that have been performed at MIDAS test facility. MIDAS is a scaled test facility of APR1400 with the objective of identifying multi-dimensional thermal-hydraulic phenomena in the downcomer during the reflood conditions of a large break LOCA. A modified linear scale ratio was applied in its construction and test conditions. The major thermal-hydraulic parameters such as ECC bypass fraction, steam condensation fraction, and temperature distributions in downcomer are compared and evaluated. The evaluation results of MARS code for the various test cases show that: (a) MARS code has an advanced modeling capability of well predicting major multi-dimensional thermal-hydraulic phenomena occurring in the downcomer, (b) MARS code under-predicts the steam condensation rates, which in turn causes to over-predict the ECC bypass rates. However, the trend of decrease in steam condensation rate and increase in ECC bypass rate in accordance with the increase in steam flow rate, and the calculation results of the ECC bypass rates under the EM analysis conditions generally agree with the test data

  12. Analysis of Total Loss of Feedwater for APR1400 using SPACE

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Seong Min; Park, Seok Jeong; Park, Chan Eok; Choi, Jong Ho; Lee, Gyu Cheon [KEPCO Engineering and Construction, Deajeon (Korea, Republic of)

    2016-10-15

    The Total Loss of FeedWater (TLOFW) event is an accident that main feedwater and auxiliary feedwater of secondary side are not supplied to steam generators. APR1400 uses the Safety Depressurization and Vent System (SDVS) for the F and B operation and SDVS is designed to perform the rapid depressurization function of Reactor Coolant System (RCS) through the remote manual operation when TLOFW is occurred. If RCS pressure falls below a Safety Injection Pump (SIP) working pressure, it can be possible to start the F and B operation which injects SIP flow to RCS and releases the RCS vapor and two-phase flow through Pilot Operated Safety Relief Valves (POSRVs) by opening the POSRVs, and then it can be possible to remove the decay heat. The design requirement of SDVS is that the core water level should be maintained at higher than 2 feet from the top of active core during the F and B operation. The TLOFW analysis was carried out to evaluate the capability of decay heat removal for APR1400 using newly developed SPACE code. The analysis results show that the F and B operation with 2 POSRVs and 2 SIPs and the F and B operation with 4 POSRVs and 4 SIPs meet the SDVS design requirement for the fuel cladding temperature. The comparison with RELAP5 shows good agreement and it validates the applicability of SPACE code for this type of accident analysis.

  13. Extended station blackout analyses of an APR1400 with MARS-KS

    Directory of Open Access Journals (Sweden)

    Kim Woongbae

    2016-01-01

    Full Text Available The Fukushima Daiichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electric energy required for essential systems during a station blackout is provided from emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6, and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating extended station blackout scenarios, the best estimate MARS-KS computer code was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study on reactor coolant pump seal leakage was carried out.

  14. Probability of Neutralization Estimation for APR1400 Physical Protection System Design Effectiveness Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myungsu; Lim, Heoksoon; Na, Janghwan; Chi, Moongoo [Korea Hydro and Nuclear Power Co. Ltd. Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    It is focusing on development of a new designing process which can be compatible to international standards such as IAEA1 and NRC2 suggest. Evaluation for the design effectiveness was found as one of the areas to improve. If a design doesn't meet a certain level of effectiveness, it should be re-designed accordingly. The effectiveness can be calculated with combination of probability of Interruption and probability of neutralization. System Analysis of Vulnerability to Intrusion (SAVI) has been developed by Sandia National Laboratories for that purpose. With SNL's timely detection methodology, SAVI has been used by U.S. nuclear utilities to meet the NRC requirements for PPS design effectiveness evaluation. For the SAVI calculation, probability of neutralization is a vital input element that must be supplied. This paper describes the elements to consider for neutralization, probability estimation methodology, and the estimation for APR1400 PPS design effectiveness evaluation process. Markov chain and Monte Carlo simulation are often used for simple numerical calculation to estimate P{sub N}. The results from both methods are not always identical even for the same situation. P{sub N} values for APR1400 evaluation were calculated based on Markov chain method and modified to be applicable for guards/adversaries ratio based analysis.

  15. The Analysis of Uncontrolled CEA Bank withdrawal from low power Accident for APR1400 Using KNAP

    International Nuclear Information System (INIS)

    Yang, Chang-Keun; Kim, Yo-Han; Ha, Sang-Jun

    2006-01-01

    In Korea, the nuclear industries such as fuel manufacturer, the architect engineer and the utility, have been using the methodologies and codes of vendors, such as Westinghouse(WH), Combustion Engineering(CE), for the safety analyses of nuclear power plants. Consequently the industries have kept up the many organizations to operate the methodologies and to maintain the codes for each vendor. It may cause difficulty to improve the safety analyses efficiency and technology related. So, the necessity another of methodologies and code systems applicable to Non- LOCA, beyond design basis accident and performance analyses for all types of pressurized water reactor (PWR) has been raised. As the first requirement, the best-estimate codes were required for applicable wider application area and realistic behavior prediction of power plants with various and sophisticated functions. After the review on several candidates, RETRAN-3D has been chosen as a system analysis code. The draft version of the methodology was developed based on the references for the general purpose, and modified to apply it to specific plants in Korea. As a part of the feasibility estimation for the methodology and code system, uncontrolled CEA bank withdrawal from low power accident for the Advanced Power Reactor 1400(APR1400) was selected to verify the feasibility using the RETRAN-3D. And the results were compared with the Standard Safety Analysis Reports (SSAR) of APR1400

  16. Extended Station Blackout Analyses of an APR1400 with MARS-KS

    Energy Technology Data Exchange (ETDEWEB)

    Kim, WoongBae; Jang, HyungWook; Oh, Seungjong; Lee, Sangyong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    The Fukushima Dai-ichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electricity required for essential systems during a station blackout is provided from the emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6 and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating of extended station blackout scenarios, the best estimate MARS-KS was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study was performed on reactor coolant pump seal leakage.

  17. Domestic activity for technical development of the APR1400's RCP performance test

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seok; Kim, Seok; Bae, Byung-Uhn; Cho, Yun-Jae; Kim, Yeon-Sik; Jeon, Woo-Jin; Yun, Young-Jung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The thermal hydraulic and electric capability of the RCP test facility (RCPTF) covers up to 18.5 MPa, 343 .deg. C, 11.7 m{sup 3}/s, and 14.0 MW in the design pressure, temperature, flow rate, and the maximum electric power, respectively. In 2013, commissioning test had been performed to verify its designed capability, followed by several modifications in the RCPTF including signal processing and control logic to enhance verification and evaluation capability of the RCP performance. After finishing the commissioning and modification of the RCPTF, type test for the new-type RCP had been performed successfully. In this paper, several technical issues developed in the 2013 and the type test's method and results will be described. In the present paper, the technical activities for the development of the verification test of APR1400's RCP are described. KAERI has completed the full set of technology development, prerequisite for the RCP verification test, and now on the way to perform a test for the sealing capacity of the seal assembly during the Station Block Out (SBO) condition of APR1400.

  18. Study of the dry processing of uranium ores; Etude des traitements de minerais d'uranium par voie seche

    Energy Technology Data Exchange (ETDEWEB)

    Guillet, H

    1959-02-01

    A description is given of direct fluorination of pre-concentrated uranium ores in order to obtain the hexafluoride. After normal sulfuric acid treatment of the ore to eliminate silica, the uranium is precipitated by a load of lime to obtain: either impure calcium uranate of medium grade, or containing around 10% of uranium. This concentrate is dried in an inert atmosphere and then treated with a current of elementary fluorine. The uranium hexafluoride formed is condensed at the outlet of the reaction vessel and may be used either for reduction to tetrafluoride and the subsequent manufacture of uranium metal or as the initial product in a diffusion plant. (author) [French] Il s'agit d'une description de fluoration directe de preconcentres de minerais d'uranium en vue d'obtention d'hexafluorure. Apres attaque sulfurique normale du minerai, afin d' eliminer la silice, l' uranium est precipite par un toit de chaux pour obtenir: ou uranate de chaux impur de titre moyen, ou uranium de la dizaine du pourcentage. Ce concentre seche en atmosphere inerte est soumis a un courant de fluor elementaire. L'hexafluorure d'uranium forme est condense a la sortie du reacteur et peut etre utilise soit apres reduction en tetrafluorure par l'elaboration d'uranium metal, soit comme produit de base dans le cadre d'une usine de diffusion. (auteur)

  19. Study of the dry processing of uranium ores; Etude des traitements de minerais d'uranium par voie seche

    Energy Technology Data Exchange (ETDEWEB)

    Guillet, H

    1959-02-01

    A description is given of direct fluorination of pre-concentrated uranium ores in order to obtain the hexafluoride. After normal sulfuric acid treatment of the ore to eliminate silica, the uranium is precipitated by a load of lime to obtain: either impure calcium uranate of medium grade, or containing around 10% of uranium. This concentrate is dried in an inert atmosphere and then treated with a current of elementary fluorine. The uranium hexafluoride formed is condensed at the outlet of the reaction vessel and may be used either for reduction to tetrafluoride and the subsequent manufacture of uranium metal or as the initial product in a diffusion plant. (author) [French] Il s'agit d'une description de fluoration directe de preconcentres de minerais d'uranium en vue d'obtention d'hexafluorure. Apres attaque sulfurique normale du minerai, afin d' eliminer la silice, l' uranium est precipite par un toit de chaux pour obtenir: ou uranate de chaux impur de titre moyen, ou uranium de la dizaine du pourcentage. Ce concentre seche en atmosphere inerte est soumis a un courant de fluor elementaire. L'hexafluorure d'uranium forme est condense a la sortie du reacteur et peut etre utilise soit apres reduction en tetrafluorure par l'elaboration d'uranium metal, soit comme produit de base dans le cadre d'une usine de diffusion. (auteur)

  20. Uncertainty Evaluation of a Postulated LBLOCA for APR+ using KINS Realistic Evaluation Methodology and MARS-KS

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Min Jeong; Marigomena, Ralph; Yoo, Tae Ho; Kim, Y. S.; Sim, S. K. [Environment and Energy Technology, Inc., Daejeon (Korea, Republic of); Bang, Young Seok [KINS, Daejeon (Korea, Republic of)

    2014-05-15

    As a part of the regulatory safety research, Korea Institute of Nuclear Safety(KINS) also developed a best estimate safety analysis regulatory audit code, MARS-KS, to realistically predict and better understand the physical phenomena of the design basis accidents. KINS improved uncertainty propagation methodology using MARS-KS and applied the improved uncertainty evaluation method for the Shinkori Units 3 and 4 LBLOC. This study is to evaluate the uncertainty propagation of a postulated LBLOCA and quantify the safety margin using KINS-REM and MARS-KS code for the APR+ (Advanced Pressurizer Reactor Plus) Standard Safety Analysis Report(SSAR) which is under regulatory review by the KINS for its design approval. KINS-REM LBLOCA realistic evaluation methodology was used for the regulatory assessment of the APR+ LBLOCA using MARS-KS to evaluate the uncertainty propagation of the uncertainty variables as well as to assess the safety margin during the limiting case of the APR+ double ended guillotine cold leg LBLOCA. Uncertainty evaluation for the APR+ LBLOCA shows that the reflood PCT with upper limit of 95% probability at 95% confidence level is 1363.2 K and is higher than the blowdown PCT95/95 of 1275.3 K. The result shows that the current evaluation of APR+ LBLOCA PCT is within the acceptance criteria of 1477 K ECCS.

  1. Profil épidémiologique, diagnostique, thérapeutique et évolutif du ...

    African Journals Online (AJOL)

    K. Tengue

    Épidémiologie diagnostic;. Traitement; ... soit 6,4 % et le traitement hormonal dans 93,1 % des cas. Le taux de décès .... avaient permis la recherche de localisation secondaire et la classi- .... de plateau technique adéquat dans nos structures.

  2. Apreçando Derivativos de Crédito no Brasil Credit Derivatives Pricing in Brazil

    Directory of Open Access Journals (Sweden)

    Jorge C. Kapotas

    2004-12-01

    Full Text Available Neste artigo apresentamos os principais modelos de apreçamento de instrumentos de crédito onde desenvolvem-se as equações de apreçamento de debêntures. Para tal, utilizam-se os modelos estruturais, de intensidade e, finalmente, de rating. A seguir, definimos o que são derivativos de crédito (CDS e derivamos fórmulas de apreçamento para estes instrumentos. Concluímos este artigo com uma aplicação ao mercado brasileiro. In this paper we present the main models used for pricing defaultable bonds and credit derivatives. The Merton structural model, the intensity framework and a Ratings based model are considered. We apply these techniques to the pricing of credit derivatives on Brazilian US$-indexed treasury bonds.

  3. EFFET DES TRAITEMENTS THERMIQUES SUR LA REACTION ENTRE DES COUCHES MINCES DE TITANE ET DES SUBSTRATS EN ACIER

    Directory of Open Access Journals (Sweden)

    D Slimani

    2015-06-01

    Full Text Available Des couches minces du titane pur ont été déposées avec la méthode de pulvérisation cathodique sur des substrats en acier, type FF80 K-1 contenants ~1% mass. en carbone. La réaction entre les deux parties du système substrat-couche mince est activée avec des traitements thermiques sous vide dans l’intervalle de températures de 400 à900°Cpendant 30 minutes. Les Spectres de diffraction de rayons x confirment l’inter- diffusion des éléments  chimiques du système résultants la formation et la croissance des nouvelles phases en particulier le carbure binaire TiC ayant des caractéristiques thermomécaniques importantes. L’analyse morphologique des échantillons traités  avec le microscope électronique à balayage (MEB montre l’augmentation du flux de diffusion atomique avec la température de recuit, notamment la diffusion du manganèse et du fer vers la surface libre des échantillons aux températures élevées provoquant la dégradation des propriétés mécaniques des revêtements contrairement au premiers stades d’interaction où on a obtenu des bonnes valeurs de la microdureté.

  4. La fibrillation atriale, fréquence, facteurs étiologiques, évolution et traitement dans un service de cardiologie de Dakar, Sénégal

    Directory of Open Access Journals (Sweden)

    Kane Abdoul

    2010-09-01

    Full Text Available INTRODUCTION: La fibrillation atriale est le trouble du rythme cardiaque soutenu le plus fréquent. Les objectifs de ce travail étaient d’étudier la fréquence, les facteurs étiologiques, l’évolution et le traitement de la fibrillation atriale dans un service de cardiologie de Dakar au Sénégal. METHODES: Il s’agit d’une étude rétrospective réalisée sur cinq ans et portant sur l’analyse de 150 dossiers de patients hospitalisés pour une fibrillation atriale. RESULTATS: La fréquence de la fibrillation atriale était de 5,35 % et représentait 66% des troubles du rythme cardiaque avec une prédominance féminine (sex-ratio H/F = 0,45 et un âge moyen de 57,06 ± 18,64 ans. L’origine de la fibrillation était valvulaire dans 36,7% des cas. Les complications thromboemboliques étaient plus fréquentes dans la fibrillation atriale non valvulaire (p=0,006, chez les sujets d’âge > 50 ans (p=0,01 et en cas de dilatation de l’oreillette gauche (p=0,05. Une anticoagulation par anti-vitamine K était instaurée dans 62% des cas et un traitement de contrôle de la fréquence cardiaque dans 87,33%. CONCLUSION: La fibrillation atriale est fréquente en milieu hospitalier africain et concerne des sujets relativement jeunes. L’hypertension artérielle et les valvulopathies rhumatismales sont les principaux facteurs étiologiques. Le traitement reste essentiellement médicamenteux par contrôle de la fréquence cardiaque.

  5. Phylogenetic Diversity of aprA Genes in Subseafloor Sediments on the Northwestern Pacific Margin off Japan.

    Science.gov (United States)

    Aoki, Masataka; Kakiuchi, Ryota; Yamaguchi, Takashi; Takai, Ken; Inagaki, Fumio; Imachi, Hiroyuki

    2015-01-01

    Markedly diverse sequences of the adenosine-5'-phosphosulfate reductase alpha subunit gene (aprA), which encodes a key enzyme in microbial sulfate reduction and sulfur oxidation, were detected in subseafloor sediments on the northwestern Pacific off Japan. The aprA gene sequences were grouped into 135 operational taxonomic units (90% sequence identity), including genes related to putative sulfur-oxidizing bacteria predominantly detected in sulfate-depleted deep sediments. Our results suggest that microbial ecosystems in the subseafloor biosphere have phylogenetically diverse genetic potentials to mediate cryptic sulfur cycles in sediments, even where sulfate is rarely present.

  6. Les pertes après récolte en Afrique : examen analytique et synthèse ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Partout en Afrique, les pertes après récolte le long de la chaîne alimentaire, de la ferme à la table, mettent en péril la sécurité alimentaire des agriculteurs dépourvus de ressources. La réduction des pertes après récolte peut aider à accroître la disponibilité, la qualité nutritionnelle et la salubrité des aliments, et à améliorer ...

  7. Reliability analysis of protection system of advanced pressurized water reactor - APR 1400

    International Nuclear Information System (INIS)

    Varde, P. V.; Choi, J. G.; Lee, D. Y.; Han, J. B.

    2003-04-01

    Reliability analysis was carried out for the protection system of the Korean Advanced Pressurized Water Reactor - APR 1400. The main focus of this study was the reliability analysis of digital protection system, however, towards giving an integrated statement of complete protection reliability an attempt has been made to include the shutdown devices and other related aspects based on the information available to date. The sensitivity analysis has been carried out for the critical components / functions in the system. Other aspects like importance analysis and human error reliability for the critical human actions form part of this work. The framework provided by this study and the results obtained shows that this analysis has potential to be utilized as part of risk informed approach for future design / regulatory applications

  8. Response Time Analysis and Test of Protection System Instrument Channels for APR1400 and OPR1000

    International Nuclear Information System (INIS)

    Lee, Chang Jae; Han, Seung; Yun, Jae Hee; Baek, Seung Min; Lee, Sang Jeong

    2015-01-01

    Safety limits are required to maintain the integrity of physical barriers designed to prevent the uncontrolled release of radioactive materials in nuclear power plants. The safety analysis establishes two critical constraints that include an analytical limit in terms of a measured or calculated variable, and a specific time after the analytical limit is reached to begin protective action. Keeping with the nuclear regulations and industry standards, satisfying these two requirements will ensure that the safety limit will not be exceeded during the design basis event, either an anticipated operational occurrence or a postulated accident. Various studies on the setpoint determination methodology for the safety-related instrumentation have been actively performed to ensure that the requirement of the analytical limit is satisfied. In particular, the protection setpoint methodology for the advanced power reactor 1400 (APP1400) and the optimized power reactor 1000 (OPR1000) has been recently developed to cover both the design basis event and the beyond design basis event. The developed setpoint methodology has also been quantitatively validated using specific computer programs and setpoint calculations. However, the safety of nuclear power plants cannot be fully guaranteed by satisfying the requirement of the analytical limit. In spite of the response time verification requirements of nuclear regulations and industry standards, it is hard to find the studies on the systematically integrated methodology regarding the response time evaluation. In cases of APR1400 and OPR1000, the response time analysis for the plant protection system is partially included in the setpoint calculation and the response time test is separately performed via the specific plant procedure. The test technique has a drawback which is the difficulty to demonstrate completeness of timing test. The analysis technique has also a demerit of resulting in extreme times that not actually possible. Thus

  9. Signoles Aude, Le Hamas au pouvoir et après ?, Toulouse, Editions Milan, 2006.

    Directory of Open Access Journals (Sweden)

    Jean-François Legrain

    2007-11-01

    Full Text Available Dans les étroites limites imposées par la collection (absence totale de notes et de bibliographie, 112 p. en format réduit, le petit livre d’Aude Signoles, Le Hamas au pouvoir et après ?, commence à combler un vide de l’édition française. Le seul livre jusque là disponible en français et entièrement consacré à Hamas remonte à 7 années maintenant ; doté de nombreuses erreurs factuelles et faisant comme si Hamas était apparu avec l’autonomie des années 1990, il ignorait tout de son passé d’Ass...

  10. Response Time Analysis and Test of Protection System Instrument Channels for APR1400 and OPR1000

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Jae; Han, Seung; Yun, Jae Hee; Baek, Seung Min [Department of Instrumentation and Control System Engineering, KEPCO Engineering and Construction, Daejeon (Korea, Republic of); Lee, Sang Jeong [Department of Electronics Engineering, Chungnam National University, Daejeon (Korea, Republic of)

    2015-07-01

    Safety limits are required to maintain the integrity of physical barriers designed to prevent the uncontrolled release of radioactive materials in nuclear power plants. The safety analysis establishes two critical constraints that include an analytical limit in terms of a measured or calculated variable, and a specific time after the analytical limit is reached to begin protective action. Keeping with the nuclear regulations and industry standards, satisfying these two requirements will ensure that the safety limit will not be exceeded during the design basis event, either an anticipated operational occurrence or a postulated accident. Various studies on the setpoint determination methodology for the safety-related instrumentation have been actively performed to ensure that the requirement of the analytical limit is satisfied. In particular, the protection setpoint methodology for the advanced power reactor 1400 (APP1400) and the optimized power reactor 1000 (OPR1000) has been recently developed to cover both the design basis event and the beyond design basis event. The developed setpoint methodology has also been quantitatively validated using specific computer programs and setpoint calculations. However, the safety of nuclear power plants cannot be fully guaranteed by satisfying the requirement of the analytical limit. In spite of the response time verification requirements of nuclear regulations and industry standards, it is hard to find the studies on the systematically integrated methodology regarding the response time evaluation. In cases of APR1400 and OPR1000, the response time analysis for the plant protection system is partially included in the setpoint calculation and the response time test is separately performed via the specific plant procedure. The test technique has a drawback which is the difficulty to demonstrate completeness of timing test. The analysis technique has also a demerit of resulting in extreme times that not actually possible. Thus

  11. A MARS and MIDAS Linked Accident Simulation for Large LOCA in APR1400

    International Nuclear Information System (INIS)

    Choi, Young; Kim, K. R.; Kim, D. H.; Chung, B. D.

    2006-01-01

    A linked calculation utilizing the design-basis code MARS and the severe accident code MIDAS has been accomplished for a station blackout simulation in APR1400. The MARS code was developed by using the RELAP3/MOD3 and COBRA-TF codes, while the MIDAS code is currently under a development process using the MELCOR code. The objectives of this paper are to explain how to identify the MAR-MIDAS linked calculation outlines and the technical problems, including the MARS data transfer method, the MIDAS input generation works and so on. For the performance verification of the MARS-MIDAS linked calculation, the MARS, MIDAS and their linkage system are run independently for the same initiating event, so that their data can be compared with each other after the selection of proper variables

  12. Minimum containment pressure and its effect on ECCS performance of APR-1400

    International Nuclear Information System (INIS)

    Kim, In Goo; Bang, Young S.; Kim, Hho Jung

    2004-01-01

    The containment pressure has a strong effect on the late reheat behavior for a large break LOCA, associated with the DVI issue. The downcomer boiling, which occurs during the post-reflood phase, has a negative effect on core cooling for a LBLOCA. Because the downcomer boiling is enhanced as the containment pressure decreases, how to determine containment pressure is important to the evaluation of ECCS performance. In spite of its importance of containment pressure, there are few studies on the containment pressure and the interaction between RCS and containment thermal hydraulics. To have a better knowledge of the effect of containment pressure on APR-1400 ECCS performance, a parametric study for containment pressure has been carried out. Also, the interaction between RCS and containment behavior has been also investigated

  13. Analysis Of Feedwater Line Break Of APR1400 By MARS Code

    International Nuclear Information System (INIS)

    Nguyen Thi Thanh Thuy; Le Dai Dien, Hoang Minh Giang

    2011-01-01

    This paper will deal with analysis of Feed water Line Break problem (FWLB) of the APR 1400 NPP with initial conditions: operation at 100% of power, double-ended break area of 0.058 m 2 and the break location of the feedwater line between the check valve and the steam generator. The analysis was simulated by MARS code through two step: calculation for steady state and calculation for transient state with initial condition mentioned. Some output result were presented with explanation: sequence of events corresponding to the time of the accident, the system behavior as temperature, pressure, steam generator water levels as well as DNBR, etc. before and after the accident. (author)

  14. Analysis Of Control Rod Ejection Of APR1400 By RELAP5

    International Nuclear Information System (INIS)

    Le Thi Thu; Hoang Minh Giang; Vo Thi Huong; Le Dai Dien

    2011-01-01

    This paper presents the analysis of Reactivity Induced Accident caused by ejection of a Control Element Assembly (CEA) from APR 1400 reactor vessel within 0.05 second. The initial condition were assumed as following: power level at 102%, delayed neutron fraction β = 412 pcm and CEA worth = 110 pcm. The analysis was simulated by RELAP5 code through two step: calculation of steady state and calculation of transient with initial condition mentioned as above. Some output results were presented with explanation: sequence of events corresponding to the time of the accident, the system behavior as power, reactivity feedback from fuel temperature changes (Doppler) as well as temperature, pressure, DNBR within 6 second of the accident. (author)

  15. Construire un jeu éducatif en ligne, Asthme : 1, 2, 3 … Respirez!, pour sensibiliser les jeunes du secondaire aux problèmes de l'asthme

    Directory of Open Access Journals (Sweden)

    Louise Sauvé

    2011-05-01

    Full Text Available Dans le cadre d’une étude financée par le Conseil de recherche en sciences sociales et humaines (CRSH, 2008-2011, nous examinons l’efficacité d’un jeu éducatif en ligne sur l’apprentissage cognitif (structuration des connaissances et affectif (changement d'attitudes. Construit à partir des règles du jeu de société Parchési auxquelles plusieurs adaptations ont été apportées, le jeu Asthme : 1, 2, 3… Respirez! a été conçu pour s'inscrire dans le programme d’éducation à la santé pour les élèves du secondaire IV et V, âgés entre 15 et 17 ans. Dans cet article, nous présenterons brièvement les problèmes associés à l’asthme au Québec et au Canada. Ensuite, nous expliciterons l'apport des jeux éducatifs sur la structuration des connaissances et le changement d’attitudes ainsi que les paramètres d'apprentissage utilisés pour construire le jeu. Enfin, nous décrirons comment le jeu a été construit et la mise à l'essai réalisée avec 40 élèves pour évaluer son design, sa lisibilité pédagogique et sa convivialité.

  16. Appraisal of the Psychiatric Diagnostic Screening Questionnaire in a perinatal cohort: The APrON study.

    Science.gov (United States)

    Leung, Brenda; Letourneau, Nicole; Bright, Katherine; Giesbrecht, Gerald F; Ntanda, Henry; Gagnon, Lisa

    2017-08-01

    Depression and anxiety are routinely screened as part of perinatal care. However, other Axis 1 disorders and specific anxiety disorders are less likely to be screened or assessed as part of obstetric care. The objective of this study was to determine whether the Psychiatric Diagnostic Screening Questionnaire (PDSQ) is a potentially useful tool to screen for psychiatric conditions in pregnant and postpartum women in a community setting. We compared the prevalence of DSM Axis I disorders obtained on the PDSQ with: (1) the prevalence of these disorders reported in previous studies of pregnant and postpartum women, and (2) scores obtained on the Edinburgh Postpartum Depression Scale (EPDS) and the Symptom Checklist-90-Revised (SCL-90R) anxiety scale. Data were obtained from the Alberta Pregnancy Outcomes and Nutrition (APrON) study. The PDSQ was completed by 1575 women prenatally and 1481 postnatally. The three most prevalent PDSQ conditions were social phobia, somatic disorder, and obsessive-compulsive disorder (OCD). The prevalence of social phobia, alcohol disorder, OCD and psychosis were higher in the APrON cohort compared with statistics in the literature. The proportion of women meeting depression and anxiety cut-offs on the PDSQ were lower than for the EPDS and the SCL-90R. The Cohens Kappa index ( k) indicated poor to fair agreement between the measures in classifying pregnant women as depressed or anxious. The PDSQ subscales may not be appropriate for the pregnant population. Research into instruments more specific to pregnant and postpartum women are needed to determine the prevalence of psychiatric disorders in this population.

  17. Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Song, Sung Chu; Lee, Jung Jae; Cho, Yong Jin; Hwang, Taesuk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion.

  18. Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

    International Nuclear Information System (INIS)

    Song, Sung Chu; Lee, Jung Jae; Cho, Yong Jin; Hwang, Taesuk

    2013-01-01

    The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion

  19. Use case driven approach to develop simulation model for PCS of APR1400 simulator

    International Nuclear Information System (INIS)

    Dong Wook, Kim; Hong Soo, Kim; Hyeon Tae, Kang; Byung Hwan, Bae

    2006-01-01

    The full-scope simulator is being developed to evaluate specific design feature and to support the iterative design and validation in the Man-Machine Interface System (MMIS) design of Advanced Power Reactor (APR) 1400. The simulator consists of process model, control logic model, and MMI for the APR1400 as well as the Power Control System (PCS). In this paper, a use case driven approach is proposed to develop a simulation model for PCS. In this approach, a system is considered from the point of view of its users. User's view of the system is based on interactions with the system and the resultant responses. In use case driven approach, we initially consider the system as a black box and look at its interactions with the users. From these interactions, use cases of the system are identified. Then the system is modeled using these use cases as functions. Lower levels expand the functionalities of each of these use cases. Hence, starting from the topmost level view of the system, we proceeded down to the lowest level (the internal view of the system). The model of the system thus developed is use case driven. This paper will introduce the functionality of the PCS simulation model, including a requirement analysis based on use case and the validation result of development of PCS model. The PCS simulation model using use case will be first used during the full-scope simulator development for nuclear power plant and will be supplied to Shin-Kori 3 and 4 plant. The use case based simulation model development can be useful for the design and implementation of simulation models. (authors)

  20. Analysis for the Effects of Grid Voltage Degradation on APR1400 Operation, Case Study for Egypt

    International Nuclear Information System (INIS)

    Hassan, Mostafa Ahmed Fouad; Koo, Chang Choong

    2015-01-01

    Egypt is one of the countries planning to introduce a NPP into its electrical power system. Although the Egyptian power system has sufficient capacity to integrate any commercially available nuclear unit as the total installed capacity of the power system is more than 32GWe, which is more than 10 times capacity of any nuclear unit in the range of 1000 to 1700MWe, the system is vulnerable to extreme voltage variations, especially voltage degradation during peak load conditions. These conditions can lead to voltage collapse if a counter measure, usually load shedding, is not taken in a proper time. Hence, it is necessary to analyze the effect of such conditions on the safe and economic operation of the NPP. In this paper we analyzed the effects of grid voltage degradation on the safe and economic operation of the Advanced Power Reactor (APR1400) to determine any adverse effects on the plant auxiliary loads while operating in the Egyptian power system. In this paper the effects of grid voltage degradation on the safe and economic operation of APR1400 were investigated taking into account, generator operating limits, plant safety requirements, operation modes and loading categories in order to determine any adverse effect on the plant auxiliary loads while operating in the Egyptian power system. The results of the load flow and motor starting analysis demonstrated that during normal operation the automatic voltage regulator and transformers OLTCs can mitigate the effect of grid voltage degradation without any detrimental effect on the plant auxiliary loads. During the highly unlikely LOCA condition if the grid voltage degraded below 95%, the degraded voltage relays at Class 1E 4.16 kV buses will trip the supply and load breakers and reconnect the required safety loads to the EDG after 4 minutes time delay. During this period the safety loads required for LOCA can be started and accelerated to their rated speed safely even in the worst case of expected degraded voltage

  1. New tools for NTD vaccines: A case study of quality control assays for product development of the human hookworm vaccine Na-APR-1M74.

    Science.gov (United States)

    Pearson, Mark S; Jariwala, Amar R; Abbenante, Giovanni; Plieskatt, Jordan; Wilson, David; Bottazzi, Maria Elena; Hotez, Peter J; Keegan, Brian; Bethony, Jeffrey M; Loukas, Alex

    2015-01-01

    Na-APR-1(M74) is an aspartic protease that is rendered enzymatically inactive by site-directed mutagenesis and is a candidate antigen component in the Human Hookworm Vaccine. The mutant protease exerts vaccine efficacy by inducing antibodies that neutralize the enzymatic activity of wild type enzyme (Na-APR-1wt) in the gut of the hookworm, thereby depriving the worm of its ability to digest its blood meal. Previously, canines immunized with Na-APR-1(M74) and challenged with Ancylostoma caninum were partially protected against hookworm challenge infection, especially from the loss in hemoglobin observed in control canines and canine immunoglobulin (Ig) G raised against Na-APR-1 was shown to inhibit the enzymatic activity of Na-APR-1 wt in vitro, thereby providing proof of concept of Na-APR-1(M74) as a vaccine antigen. The mutated version, Na-APR-1(M74), was then expressed at the cGMP level using a Nicotiana benthamiana expression system (Fraunhofer, CMB, Delaware, MD), formulated with Alhydrogel®, and used to immunize mice in a dose-ranging study to explore the enzyme-neutralizing capacity of the resulting anti- Na-APR-1(M74) IgG. As little as 0.99 μg of recombinant Na-APR-1(M74) could induce anti Na-APR-1(M74) IgG in mice that were capable of inhibiting Na-APR-1w t-mediated digestion of a peptide substrate by 89%. In the absence of enzymatic activity of Na-APR-1(M74) as a surrogate marker of protein functionality, we developed an assay based on the binding of a quenched fluorescence-labeled inhibitor of aspartic proteases, BODIPY-FL pepstatin A (BDP). Binding of BDP in the active site of Na-APR-1 wt was demonstrated by inhibition of enzymatic activity, and competitive binding with unlabelled pepstatin A. BDP also bound to Na-APR-1(M74) which was assessed by fluorescence polarization, but with an ∼ 50-fold reduction in the dissociation constant. Taken together, these assays comprise a "toolbox" that could be useful for the analyses of Na-APR-1(M74) as it

  2. Quantification de la Charge Virale et tests de résistance du VIH-1 aux ARV à partir d’échantillons DBS (Dried Blood Spots chez des patients Guinéens sous traitement antirétroviral

    Directory of Open Access Journals (Sweden)

    Nestor Bangoura

    2015-06-01

    Full Text Available Problématique: Comme dans plusieurs pays du Sud, le suivi virologique des patients sous traitement antirétroviral (TARV en Guinée est timide voire inexistant dans certaines localités. Le but de cette étude était d’évaluer la faisabilité technique et logistique de l’utilisation des DBS dans les tests de charge virale (CV et de génotypage. Méthode: De septembre à octobre 2010, les DBS ont été préparés à partir de prélèvements sanguins de patients adultes sous TARV. Le délai d’envoi des échantillons au laboratoire de référence était de 30 jours maximum après le prélèvement et se faisait à température ambiante. La CV a été quantifiée et les échantillons de patients en échec virologique (CV ≥ 3 log10 copies/mL ont été génotypés selon le protocole de l’ANRS. L’algorithme de Stanford version 6.0.8 a été utilisé pour l’analyse et l’interprétation des mutations de résistance. Résultats: Parmi les 136 patients inclus, 129 et 7 étaient respectivement sous première et deuxième ligne de traitement avec une médiane de suivi de 35 mois [IQR: 6-108]. L’échec virologique a été noté chez 33 patients. Parmi eux, 84.8% (n = 28/33 ont bénéficié d’ungénotypage. Le taux de résistance global était de 14% (n = 19/136. Le CRF02_AG était le sous type viral le plus prévalent (82%; n = 23. Conclusion: En plus de montrer la faisabilité technique et logistique des tests de CV et de génotypage à partir des DBS, ces résultats montrent l’intérêt de leurs utilisations dans le suivi virologique des patients sous TARV. Cette étude a permis également de documenter l’échec virologique, la résistance aux ARV et la diversité génétique du VIH-1 en Guinée. Mots clés: VIH-1, Résistance aux ARV, DBS (Dried Blood Spots, Guinée Conakry, Génotypage,Charge Virale.   Quantification of Viral load and resistance tests of HIV-1 to ARVs from dried blood spotssamples in Guinean patients undergoing

  3. Processing of wastewaters of column bases of the C.E.B. uranium-thorianite plant; Traitement des eaux residuaires des pieds de colonne de l'usine d'urano-thorianite du C.E.B.

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P.; Wormser, G.

    1959-08-12

    The authors report, on the one hand, results of tests aimed at determining an optimal chemical treatment for the purification of wastewaters from the column of extraction by solvents of the CEB uranium-thorianite plant, and on the other hand, the measurement problems faced due to the chemical composition of the studied solutions. In a first set of tests, the authors studied the carryover efficiency of barium sulphate and barium carbonate, but due to difficulties created by the presence of barium when recovering radium, other possibilities have been studied which take this possibility of barium recovery without barium into account. The obtained results show the benefit of an intermediate filtration of lead sulphate, followed by an additional purification. The decontamination rate is then multiplied by ten, and radium is recovered in a precipitate free of hydroxides. An operational mode is proposed. In the first part, the authors describe measurement methods used to determine total alpha and radium in highly salted solutions [French] Dans ce rapport sont exposes: - d'une part les resultats des essais de laboratoire en vue de determiner un traitement chimique optimum pour l'epuration des eaux residuaires en provenance de la colonne d'extraction par solvants de l'usine d'urano-thorianite du C.E.B.; - d'autre part les problemes de mesure qui se sont poses du fait de la composition chimique des solutions etudiees. Dans une premiere serie d'essais nous avons etudie l'efficacite de l'entrainement par le sulfate de baryum et le carbonate de baryum. Toutefois, avertis des difficultes posees par la presence de baryum lors d'une eventuelle recuperation du radium, nous avons ete amenes a etudier les deux cas suivants qui tiennent compte de la necessite de recuperer le radium sans baryum: - soit faire une seule filtration d'un precipite de sulfate de plomb + hydroxydes, - soit proceder a une filtration intermediaire du sulfate de plomb. Apres divers essais, il est apparu que la

  4. The Experience of Staging Nijinsky's "L'Apres-Midi d'un Faune" in a Higher Education Dance Program

    Science.gov (United States)

    Curran, Tina

    2010-01-01

    This study documented the experiences of staging Vaslav Nijinsky's "L'Apres-midi d'un Faune" in a higher education dance program. The ballet was staged from Labanotation. Research questions focused on teaching and learning pedagogy, characterization of the process over time, experiences of the participants and teaching approaches. The project…

  5. 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)

  6. Collection and processing of information in biological kinetics studies with radioactive tracers; Collecte et traitement de l'information dans les etudes de cinetique biologique avec traceurs radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Remy, J; Lafuma, J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The authors present an automatic method for the collection and treatment of information in biological kinetics experiments using radioactive tracers. The recording are made without any time constant on magnetic tape. The information recorded is sampled by a 400 channel multi-scale analyzer and transferred to punched cards. The digital analysis is done by an I.B.M. computer. The method is illustrated by an example: the hepatic fixation of colloidal gold in the pig. Its advantages and requirements are discussed. In the appendix are given the FORTRAN texts for two programmes used in treating the example presented. (authors) [French] Les auteurs presentent une methode automatique de collecte et de traitement de l'information dans les experiences de cinetique biologique utilisant les traceurs radioactifs. Les enregistrements sont realises sans constante de temps sur bande magnetique. L'information enregistree fait l'objet d'un echantillonnage a l'aide d'un analyseur a 400 canaux en mode multi-echelle puis est transferee sur cartes perforees. L'exploitation digitale est confiee a un ordinateur I.B.M.. La methode est illustree par un exemple d'etude de la fixation hepatique de l'or colloidal chez le porc. Ses avantages et ses exigences sont discutes. En annexe figurent les textes en FORTRAN de deux programmes utilises pour le traitement de l'exemple cite. (auteurs)

  7. Homology modeling of dissimilatory APS reductases (AprBA of sulfur-oxidizing and sulfate-reducing prokaryotes.

    Directory of Open Access Journals (Sweden)

    Birte Meyer

    Full Text Available BACKGROUND: The dissimilatory adenosine-5'-phosphosulfate (APS reductase (cofactors flavin adenine dinucleotide, FAD, and two [4Fe-4S] centers catalyzes the transformation of APS to sulfite and AMP in sulfate-reducing prokaryotes (SRP; in sulfur-oxidizing bacteria (SOB it has been suggested to operate in the reverse direction. Recently, the three-dimensional structure of the Archaeoglobus fulgidus enzyme has been determined in different catalytically relevant states providing insights into its reaction cycle. METHODOLOGY/PRINCIPAL FINDINGS: Full-length AprBA sequences from 20 phylogenetically distinct SRP and SOB species were used for homology modeling. In general, the average accuracy of the calculated models was sufficiently good to allow a structural and functional comparison between the beta- and alpha-subunit structures (78.8-99.3% and 89.5-96.8% of the AprB and AprA main chain atoms, respectively, had root mean square deviations below 1 A with respect to the template structures. Besides their overall conformity, the SRP- and SOB-derived models revealed the existence of individual adaptations at the electron-transferring AprB protein surface presumably resulting from docking to different electron donor/acceptor proteins. These structural alterations correlated with the protein phylogeny (three major phylogenetic lineages: (1 SRP including LGT-affected Archaeoglobi and SOB of Apr lineage II, (2 crenarchaeal SRP Caldivirga and Pyrobaculum, and (3 SOB of the distinct Apr lineage I and the presence of potential APS reductase-interacting redox complexes. The almost identical protein matrices surrounding both [4Fe-4S] clusters, the FAD cofactor, the active site channel and center within the AprB/A models of SRP and SOB point to a highly similar catalytic process of APS reduction/sulfite oxidation independent of the metabolism type the APS reductase is involved in and the species it has been originated from. CONCLUSIONS: Based on the comparative

  8. Implementasi Automatic Packet Reporting System (APRS Untuk Paket Data Pemantauan dan PengukuranUntuk Paket Data Pemantauan dan Pengukuran

    Directory of Open Access Journals (Sweden)

    Arief Goeritno

    2016-03-01

    Full Text Available Telah dilakukan implementasi Automatic Packet Reporting System (APRS untuk paket data pemantauan dan pengukuran melalui tujuan penelitian, berupa: a penyetelan program aplikasi pada jaringan APRS dan b pengukuran terhadap penerimaan data berdasarkan kinerja sensor-sensor. Penyetelan program aplikasi APRS merupakan konfigurasi perangkat lunak untuk APRS yang akan digunakan pada stasiun penerimaan data APRS dengan program aplikasi yang biasa digunakan, yaitu hyperterminal dan UI-View 32. Pengukuran penerimaan data berdasarkan kinerja sensor yang dilakukan melalui proses perekaman pada stasiun penerimaan data APRS. Kinerja sensor-sensor akan diamati pada stasiun pengiriman dan data hasil pengamatan akan dapat diterima pada stasiun penerimaan secara real time. Program aplikasi berbasis hyperterminal dan UI View 32 telah berhasil melakukan proses handshaking antara Terminal Node Controller (TNC dan komputer, sehingga data telemetri dari stasiun pengiriman paket data dapat diterima di stasiun penerimaan. Data telemetri dapat diamati pada stasiun penerimaan dan dapat diperoleh secara real time dengan format: YB0LRB-11>BEACON,WIDE2-1 [05/18/2014 04:03:49]: : T#010,008,093,004,122,075. Notifikasi YB0LRB-11 merupakan stasiun pengiriman paket data telemetri, kemudian data tersebut akan diterima pada stasiun penerima YD1PRY dengan format: YD1PRY-2>APLPN,ARISS [05/18/2014 04:03:07]: : !06.30.37S/106.48.26E#. Notifikasi tersebut merupakan pengiriman informasi data posisi oleh stasiun YD1PRY untuk inisialisasi pada jaringan APRS. Stasiun YB0LRB-11 ketika mengirim paket data telemetri dengan format: YB0LRB-11>BEACON,WIDE2-1 [05/18/2014 04:00:49]: : T#001,004,035,005,122,075. Paket data dari stasiun YB0LRB yang dipancar ulang atau digipeater dengan format: YB0LRB-11>BEACON,YD1PRY-2,WIDE2* [05/18/2014 04:00:50]: : T#001,004,035,005,122,075. Sensor pengukuran berkinerja relatif stabil, walaupun terdapat nilai simpangan pengukuran sebesar 1 cm atau

  9. Treatment of uranium ores by natural leaching in Portugal; Traitement par lixiviation naturelle des minerais uraniferes portugais

    Energy Technology Data Exchange (ETDEWEB)

    Lacerda, J de [Junta de Energia Nuclear, Lisbonne (Portugal)

    1967-06-15

    The technique described for treating uranium ores by natural leaching has been developed as a result of research carried out in Portugal with a view to determining and eliminating the causes of uranium migration in ores stored in the open. With the natural leaching method, which has been successfully applied to primary uranium ores, the ore is piled up on a waterproof surface and sprayed intermittently with mine water. Pyrite and ferrous sulphate are used as solid reagents and are mixed with the ore in amounts averaging 0.4% and 0.2% respectively. Over 70 000 tons of ore with a U{sub 3}O{sub 8} content of between 0.076 and 0.150% have been treated at five natural leaching plants. The average recovery in these operations was between 57.7 and 85.9%. The average cost was US $3.31/lb U{sub 3}O{sub 8}. (author) [French] Le traitement des minerais uraniferes par lixiviation naturelle est le fruit des recherches effectuees au Portugal dans le but de determiner et d'eliminer les causes de la migration de l'uranium contenu dans les minerais emmagasines a ciel ouvert. La methode de lixiviation naturelle, appliquee avec succes aux mineraux primaires d'uranium, consiste essentiellement en l'arrosage intermittent, avec l'eau des mines, du minerai entasse sur des aires impermeabilisees. On utilise comme reactifs solides la pyrite et le sulfate ferreux melanges avec le minerai a raison de 0,4% et 0,2% respectivement en moyenne. Plus de 70 000 t de minerai, dont les teneurs en U{sub 3}O{sub 8} etaient comprises entre 0,076% et 0,150%, ont ete traitees dans cinq installations de lixiviation naturelle ou on a obtenu des recuperations moyennes oscillant entre 57,7% et 85,9%, pour le prix de revient moyen de 3,31 dollars par livre de U{sub 3}O{sub 8}. (author)

  10. Progress of Design Improvements for APR1400 Computerized Procedure System from HFE V and V results and Design Experience

    International Nuclear Information System (INIS)

    Lee, Sungjin; Seong, Nokyu

    2015-01-01

    This study shows major already improved design features from the above three processes and a design proposal for to-be-improving items. APR1400 CPS has been verified and validated by the HFE process, internal design review and site acceptance tests. APR1400 Computerized Procedure System (CPS) has been applied to Shin-Kori Nuclear Power Plant (SKN) 3 and 4 units, Shin-Hanul Nuclear Power Plant (SHN) 1 and 2 units and Baraka Nuclear Power Plant (BNPP) 1, 2, 3 and 4 units. Since APR1400 CPS is a first-of-a-kind (FOAK) human machine interface (HMI) for executing a computerized procedure in the nuclear power plant's main control room in South Korea, it has been continuously improved through a) the human factor engineering (HFE) verification and validation (V and V), b) the internal design review and c) prototype tests. Human engineering discrepancies (HEDs) can be identified by the HFE V and V activity. Some HEDs of APR1400 CPS for SKN 3 and 4 and SHN 1 and 2 have been adopted as a role of design improvement in the CPS system while others were regarded as an operator training requirement or part of task contents. Various requests for improving the CPS have been collected from those results. A HMI system should be improved continuously for removing potential defects. Some of introduced design features in this paper has been adopted for APR1400 nuclear power plants. Some of them are under the review in the CPS design team of KHNP

  11. Analysis of steam condensation in APR1400 IRWST for loss of coolant accident

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Young Suk

    2006-02-15

    The In-Containment Refueling Water Storage Tank (IRWST) of APR1400 is installed at the bottom of containment building to promote the plant safety functions during an accident. This design feature brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised when an accident occurs. The hot steam which is released from RCS break enters the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, in which water is colder than incoming steam. The purpose of this study is to investigate the influence of IRWST and pressure relief damper on back pressure and temperature in APR1400 containment codes such as CONTEMPT-LT and GOTHIC. The comparison of codes showed that GOTHIC code be more appropriate for the prediction of containment pressure and temperature under the condition of steam condensation occurring in confined water pool. Especially, the GOTHIC has superior capability to treat multi-compartmentalized geometry This study developed one-compartment (single) model, two-compartment (separated) model, and three-dimension (3-D) model, respectively. Two compartment model separates the IRWST from the other containment compartments. In 3-D model, only the IRWST is nodalized with Cartesian modeling. The single model is developed for comparison with two-compartment model which can analyze PRD's influence. The separated model for predicting PRD's influence divides the space between containment and IRWST. 3-D model for IRWST was generated because it is not symmetric considering location of sparger, pump, and suction sump. Therefore, IRWST is simulated with not only detailed three-dimensional behavior but also independent flow paths for four PRDs. Many experimental studies for the direct-contact heat transfer in stratified steam water flows, cocurrent or countercurrent, have been performed (Segev et al., 1981; Lim et al., 1981

  12. Analysis of Hydrogen Concentration Distribution during an SBO Accident for Shin-Ulchin APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jongtae; Hong, Seong Wan [Korea Atomic energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    To prohibit the accumulation of hydrogen, the containment volume is considered to reduce the hydrogen concentration, or hydrogen mitigation devices such as PARs or igniters are installed in the containment. In the case of the Fukushima NPPs, the applied strategy for the hydrogen safety is the use of a containment venting system (CVS). In this way, the hydrogen accumulated in the containment vessel is vented into the environment. One of the causes of the hydrogen explosions occurring in the containment buildings of the Fukushima NPPs is expected to be the failure of the venting system. The hydrogen was therefore easily accumulated in the containment building. It is uncertain what the ignition source for the hydrogen combustion was during the accident. However, it is not too conservative to assume that an ignition source exists at any time and any place in a containment during a core-melt accident. Shin-Ulchin 1 and 2, which are construction plants of an APR 1400, are two of the newest NPPs in Korea. They have many features to enhance the safety margin during a design-based and beyond-design-based accident. One of them is the in-containment refueling water storage tank (IRWST) located inside the containment. It is used as a sink/source for feed-bleed operation. When the core is damaged along an accident progression, the hydrogen generated in the RPV can be released into the IRWST of the APR1400 with steam and water. From a previous study, it was found that a highly concentrated hydrogen/air mixture can be developed if the hydrogen is released into the IRWST. In the case of Shin-Ulchin 1 and 2, the hydrogen mitigation strategy during a high-pressure accident such as a station blackout (SBO) is changed by installing a 3-way valve. When a severe accident management (SAM) for the plant is initiated, the flow path from a pressurizer to the IRWST is changed into a steam-generator (S/G) compartment by turning the 3-wat valve actively (pilot operated). By doing so, it is

  13. Comparison of serpent and triton generated FEW group constants for APR1400 nuclear reactor core

    International Nuclear Information System (INIS)

    Elsawi, Mohamed A.; Alnoamani, Zainab

    2015-01-01

    The accuracy of full-core reactor power calculations using diffusion codes is strongly dependent on the quality of the homogenized cross sections and other few-group constants generated by lattice codes. For many years, deterministic lattice codes have been used to generate these constants using different techniques: the discrete ordinates, collision probability or the method of characteristics, just to name a few. These codes, however, show some limitations, for example, on complex geometries or near heavy absorbers as in modern pressurized water reactor (PWR) designs like the Korean Advanced Power Reactor 1400 (APR1400) core. The use of continuous-energy Monte Carlo (MC) codes to produce nuclear constants can be seen as an attractive option when dealing with fuel or reactor types that lie beyond the capabilities of conventional deterministic lattice transport codes. In this paper, the few-group constants generated by two of the state-of-the-art reactor physics codes, SERPENT and SCALE/TRITON, will be critically studied and their reliability for being used in subsequent diffusion calculations will be evaluated. SERPENT is a 3D, continuous-energy, Monte Carlo reactor physics code which has a built-in burn-up calculation capability. It has been developed at the Technical Research Center of Finland (VTT) since 2004. SCALE/TRITON, on the other hand, is a control module developed within the framework of SCALE package that enables performing deterministic 2-D transport calculations on nuclear reactor core lattices. The approach followed in this paper is as follows. First, the few-group nuclear constants for the APR1400 reactor core were generated using SERPENT (version 2.1.22) and NEWT (in SCALE version 6.1.2) codes. For both codes, the critical spectrum, calculated using the B1 method, was used as a weighting function. Second, 2-D diffusion calculations were performed using the US NRC core simulator PARCS employing the two few-group constant sets generated in the first

  14. Analysis of steam condensation in APR1400 IRWST for loss of coolant accident

    International Nuclear Information System (INIS)

    Oh, Young Suk

    2006-02-01

    The In-Containment Refueling Water Storage Tank (IRWST) of APR1400 is installed at the bottom of containment building to promote the plant safety functions during an accident. This design feature brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised when an accident occurs. The hot steam which is released from RCS break enters the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, in which water is colder than incoming steam. The purpose of this study is to investigate the influence of IRWST and pressure relief damper on back pressure and temperature in APR1400 containment codes such as CONTEMPT-LT and GOTHIC. The comparison of codes showed that GOTHIC code be more appropriate for the prediction of containment pressure and temperature under the condition of steam condensation occurring in confined water pool. Especially, the GOTHIC has superior capability to treat multi-compartmentalized geometry This study developed one-compartment (single) model, two-compartment (separated) model, and three-dimension (3-D) model, respectively. Two compartment model separates the IRWST from the other containment compartments. In 3-D model, only the IRWST is nodalized with Cartesian modeling. The single model is developed for comparison with two-compartment model which can analyze PRD's influence. The separated model for predicting PRD's influence divides the space between containment and IRWST. 3-D model for IRWST was generated because it is not symmetric considering location of sparger, pump, and suction sump. Therefore, IRWST is simulated with not only detailed three-dimensional behavior but also independent flow paths for four PRDs. Many experimental studies for the direct-contact heat transfer in stratified steam water flows, cocurrent or countercurrent, have been performed (Segev et al., 1981; Lim et al., 1981; Kim and

  15. Best-estimated multi-dimensional calculation during LB LOCA for APR1400

    International Nuclear Information System (INIS)

    Oh, D. Y.; Bang, Y. S.; Cheong, A. J.; Woong, S.; Korea, W.

    2010-01-01

    Best-estimated (BE) calculation with uncertainty quantification for the emergency core cooling system (ECCS) performance analysis during Loss of Coolant Accident (LOCA) is more broadly used in nuclear industries and regulations. In Korea, demand on regulatory audit calculation is continuously increasing to support the safety review for life extension, power up-rating and advanced nuclear reactor design. The thermal-hydraulic system code, MARS (Multi-dimensional Analysis of Reactor Safety), with multi-dimensional capability is used for audit calculation. It achieves to describe the complicated phenomena in reactor coolant system by very effectively consolidating the one dimensional RELAP5/MOD3 with the multidimensional COBRA-TF codes. The advanced power reactors (APR1400) to be evaluated has four separated hydraulic trains of the high pressure injection system (HPSI) with direct vessel injection (DVI) which is different from the existing commercial PWRs. Also, the therma-hydraulic behavior of DVI plant would be considerably different from that of a cold-leg safety injection since the low pressure safety injection system are eliminated and the high pressure safety flow are injected into the specific elevation of reactor vessel downcomer. The ECCS bypass induced by the downcomer boiling due to hot wall heating of reactor vessel during reflooding phase is one of the important phenomena which should be considered in DVI plants. Therefore, in this study, BE calculation with one-dimensional (1-D) and multi-dimensional (multi-D) MARS models during LBLOCA are performed for APR1400 plant. In the multi-D evaluation, the reactor vessel is modeled by multi-D components and the specific treatment of flow path inside reactor vessel, e.g., upper guide structure, is essential. The concept of hot zone is adopted to simulate the limiting thermal-hydraulic conditions surrounding hot rod, which is similar to hot channel in 1-D. Also, alternative treatment of the hot rods in multi-D is

  16. Measurement techniques of local parameters in the downcomer boiling experiment of APR1400

    International Nuclear Information System (INIS)

    Lee, Eu Hwak

    2004-02-01

    In order to investigate boiling phenomena experimentally in the downcomer during LBLOCA with Direct Vessel Injection (DVI), which is a new Safety Injection System (SIS) of Advanced Power Reactor 1400 MW (APR1400), several parameters should be measured through the verification of their applicability. In this study, measurement techniques of the parameters are developed for the downcomer boiling experiment; local phase velocities, local void fraction and heat flux from the heated wall. The experiment has been performed with the heated wall, which has a thickness of 8.2 cm and a height of 32.5 cm and made of the same material as the prototype (APR1400) with chrome coating against rusting. The newly developed pitot tube is applied to the measurement of local liquid velocity and its calibration curve is obtained experimentally with the consideration of the effect according to water temperature and hole size changes. The developed pitot tube measures the local liquid velocity with 0.69 % deviation and it is confirmed that the water temperature and geometrical change does not affect the calibration curve. The high-speed camera and commercial software are used to measure the local vapor velocity with the accuracy of 0.06 m/sec per pixel and the procedure is confirmed in the present study. It turns out that the vapor velocity is insensitive to void size. High-speed camera and image processing are used to measure the local void fraction with the determined intensity criterion for distinguishing each phase and the results are compared with the bulk void fraction by differential pressure transmitters. In the actual experiment, the developed method is applied successfully and the results show that the criterion of intensity has little effect on local void fraction. And, it is observed that the tendency between the measured local and bulk void faction is maintained with time. In order to measure heat flux from the heated wall, two heat flux measurement techniques are developed

  17. Apreçamento de opções de IDI usando o modelo CIR

    Directory of Open Access Journals (Sweden)

    José Santiago Fajardo Barbachan

    2003-06-01

    Full Text Available A opção de IDI da BM&F possui características peculiares que torna o seu apreçamento diferente das opções de taxa de juros mais comuns, como as de títulos de renda fixa. Este artigo desenvolve uma fórmula para apreçamento dessas opções de IDI, utilizando a precificação livre de arbitragem. O modelo utilizado considera apenas um fator estocástico: a taxa de juros livre de risco de curto prazo. A equação diferencial usada para modelar o comportamento da taxa de juros é a do modelo CIR (COX INGERSOLL & ROSS, 1985, que possui reversão à média e não permite a existência de taxas de juros nominais negativas. Também é feita uma estimação dos parâmetros do modelo proposto baseando-se em dados históricos, para então comparar o preço teórico da opção baseado nestes parâmetros com os preços de mercado e com o preço teórico considerando a modelagem de Vasicek (1977.The IDI option from the BM&F (Commodities and Futures Exchange has unusual characteristics, that make its pricing different from common interest rate options. This paper develops a closed form formula for the pricing of these IDI options, using an arbitrage-free pricing approach. The model used considers only one stochastic factor: the short-term risk-free interest rate. The differential equation used to model the behavior of the interest rate comes from the CIR (COX INGERSOLL & ROSS, 1985 model, which has mean reversion property and does not allow negative nominal interest rates. It is also done a parameter estimation of the proposed model based on historic data, and then compares the theoretical price of the option based on these parameters with the market price and with the theoretical price considering the Vasicek (1977 model.

  18. Développement de la mémoire de travail et traitement des phrases complexes : Quelle relation ?

    Directory of Open Access Journals (Sweden)

    Frauenfelder Ulrich

    2012-07-01

    Full Text Available La complexité syntaxique d’une phrase en langage oral peut se caractériser par le nombre et la nature des opérations syntaxiques nécessaires à son élaboration, et notamment par la profondeur de son enchâssement. Cette complexité influence l’âge d’acquisition des différentes structures syntaxiques, les énoncés les plus complexes étant maîtrisés plus tardivement par l’enfant. Certains auteurs attribuent cette acquisition de la syntaxe complexe à des contraintes développementales externes au système linguistique lui-même et notamment à des limitations dans les capacités de mémoire de travail (Jakubowicz, 2007. Ainsi, le traitement d’une phrase complexe engendrerait un coût cognitif important et constituerait une surcharge pour des capacités de mémoire de travail davantage limitées chez le jeune enfant. La maturation normale de ce système mnémonique permettrait ensuite à l’enfant de comprendre et de produire des énoncés de plus en plus complexes. La présente recherche a pour objectif d’éclaircir les liens entre le développement de la mémoire de travail et le traitement des phrases complexes chez l’enfant tout-venant âgé de 5 à 12 ans. Suivant le modèle de la mémoire de travail de Baddeley & Hitch (1986 et les travaux de Barrouillet & Camos (2001, 2007, nous avons appréhendé les compétences de la boucle phonologique via des épreuves d’empans simples (empan direct de chiffres, répétition de mots et de pseudo-mots et la mémoire de travail verbale via des tâches d’empans complexes (empan indirect de chiffres, counting span et running span. Les habiletés syntaxiques des enfants ont été évaluées en compréhension et en répétition d’énoncés complexes. Une analyse d’échantillons de langage spontané a enfin permis de récolter les données liées à l’utilisation de la syntaxe complexe en contexte écologique (LME, taux de subordination et taux d’enchâssement profond. Les

  19. Numerical Analysis of Molten Corium Dispersion during Hypothetical High-Pressure Accidents in APR1400 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Ha, Kwang Soon; Kim, Sang Baik; Kim, Hee Dong; Jeong, Jae Sik

    2010-01-01

    During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by the following jet of a high pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet with very high velocity and is released into the upper compartment of the NPP by an overpressure in the cavity. The heat-carrying fragments of the corium transfer the thermal energy to the ambient air in the containment and react chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. New generation NPPs such as APR1400 and EPR have been designed in consideration of reducing the possibility of the containment failure from the DCH. In order for that, APR1400 has a convolute-type corium chamber connected to the reactor cavity. In the case of EPR, severe-accident dedicated depressurization valves are installed to preclude a high pressure melt ejection (HPME). DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical reaction. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. The corium dispersion rates for many types of the NPP containments had been obtained by experiments in 90s. And some correlations from the experimental data were developed. As mentioned above, APR1400 has a corium chamber to reduce the corium dispersion rate. But there is no experimental data for the dispersion rate specific to the APR1400 cavity geometry. So its performance for capturing of the dispersed corium

  20. Barriers to Systemic, Effective, and Sustainable Technology Use in High School Classrooms / Obstacles à l’utilisation systémique, efficace et durable de la technologie dans les salles de classe des écoles secondaires

    Directory of Open Access Journals (Sweden)

    Jason Scott Daniels

    2014-01-01

    Full Text Available The purpose of the Technology and High School Success (THSS initiative was to encourage innovative strategies focused on improving provincial high school completion rates, using technology and student-centered learning to engage student interest. The primary purpose of this paper is to report on barriers that impede systemic, effective and sustainable technology integration within schools. Even with teacher and administrative support and commitment for THSS, evaluative research indicated minimal change in system capacity as a result of the initiative. Three primary barriers to program sustainability were: 1 schools and school districts did not leverage the opportunity to revisit their existing vision(s, 2 schools and school districts did not use data to make changes, and 3 limited access to technology. Le but de l’initiative « Technology and High School Success (THSS » était d'encourager des stratégies novatrices visant à améliorer le taux d’achèvement des études secondaires dans la province de l’Alberta en utilisant la technologie et un apprentissage centré sur l'élève afin de susciter l'intérêt des élèves. L'objectif principal de cet article est de rendre compte des obstacles entravant l'intégration systémique, efficace et durable de la technologie dans les écoles. La recherche évaluative a révélé des changements minimes dans la capacité systémique à la suite de l'initiative, et ce, malgré l’appui et l’engagement des enseignants et des administrateurs envers le THSS. Les trois obstacles principaux à la viabilité du programme sont les suivants: 1 les écoles et les districts scolaires n'ont pas profité de l’occasion pour revoir leur(s vision(s, 2 les écoles et les districts scolaires n'ont pas utilisé les données pour effectuer des changements, et 3 l'accès limité à la technologie.

  1. Application of the risk-informed methodology for APR1400 P-T limits curve

    Energy Technology Data Exchange (ETDEWEB)

    Kim, K.; Namgung, I. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-07-01

    A reactor pressure vessel (RPV) in a nuclear power plant has operational limits of pressure and temperature to prevent a potential drastic propagation of cracks due to brittle fracture. We call it a pressure-temperature limits curve (P-T limits curve). Appendix G of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, provides deterministic procedures to develop the P-T limits curve for the reactor pressure vessel. Recently, an alternative risk-informed methodology has been added in the ASME Code. Risk-informed means that we can consider insights from a probabilistic risk assessment by using this methodology. This alternative methodology provides a simple procedure to develop risk-informed P-T limits for heat up, cool down, and hydrostatic test events. The risk-informed P-T limits curve is known to provide more operational flexibility, particularly for reactor pressure vessels with relatively high irradiation levels and radiation sensitive materials. In this paper, we developed both the deterministic and a risk-informed P-T limits curve for an APR1400 reactor using Appendix G of the ASME Code, Section XI and compare the results in terms of additional operational margin. (author)

  2. Modeling of melt retention in EU-APR1400 ex-vessel core catcher

    Energy Technology Data Exchange (ETDEWEB)

    Granovsky, V. S.; Sulatsky, A. A.; Khabensky, V. B.; Sulatskaya, M. B. [Alexandrov Research Inst. of Technology NITI, Sosnovy Bor (Russian Federation); Gusarov, V. V.; Almyashev, V. I.; Komlev, A. A. [Saint Petersburg State Technological Univ. SPbSTU, St.Petersburg (Russian Federation); Bechta, S. [KTH, Stockholm (Sweden); Kim, Y. S. [KHNP, 1312 Gil 70, Yuseongdaero, Yuseong-gu, Daejeon (Korea, Republic of); Park, R. J.; Kim, H. Y.; Song, J. H. [KAERI, 989 Gil 111, Daedeokdaero, Yuseong-gu, Daejeon (Korea, Republic of)

    2012-07-01

    A core catcher is adopted in the EU-APR1400 reactor design for management and mitigation of severe accidents with reactor core melting. The core catcher concept incorporates a number of engineering solutions used in the catcher designs of European EPR and Russian WER-1000 reactors, such as thin-layer corium spreading for better cooling, retention of the melt in a water-cooled steel vessel, and use of sacrificial material (SM) to control the melt properties. SM is one of the key elements of the catcher design and its performance is critical for melt retention efficiency. This SM consists of oxide components, but the core catcher also includes sacrificial steel which reacts with the metal melt of the molten corium to reduce its temperature. The paper describes the required properties of SM. The melt retention capability of the core catcher can be confirmed by modeling the heat fluxes to the catcher vessel to show that it will not fail. The fulfillment of this requirement is demonstrated on the example of LBLOCA severe accident. Thermal and physicochemical interactions between the oxide and metal melts, interactions of the melts with SM, sacrificial steel and vessel, core catcher external cooling by water and release of non-condensable gases are modeled. (authors)

  3. Development of a Desktop Simulator for APR1400 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lee, J. B.

    2016-01-01

    It is essential for utilities to possess a full-scope simulator for operator training and operation test for operators. But it is very expensive and sometimes lack of fidelity if processes of developing the simulator and designing the plant are in parallel. It is due to the situation that simulator development stage sometimes precedes the plant design stage and modifications may occur to the design of the plant in construction stage. In an attempt to build a low cost and efficient simulator, a desktop simulator has been developed. This model is described herein. Using desktop simulators for training operators is an efficient method for familiarizing operators with their plant’s operation. A low cost and efficient desktop simulator for APR1400 has been developed, and brief features are introduced here. It is configured to mimic a full-scale simulator, and can be used for operators to be familiarized to their plant’s operation. Since the size of the simulator is small enough to be fit in a desk, it can be used in a classroom or in an office at any time. It can also be used to evaluate design changes or modifications of the plant before implementing them to the plant

  4. Consolidation and Decomposition of APR1400 NRC Design Certification Processes for Collaborative and Accelerated Processing

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young Chul [FNC Technology Co., Yongin (Korea, Republic of); Kang, Deog Ji [KNHP, Daejeon (Korea, Republic of)

    2016-05-15

    KEPCO and KHNP are conducting APR1400 Design Certification from NRC. For the proper management of processes and information, a system called RIS (Regulatory Information management System) has been implemented by FNC from 2014, and it is on the final stage. In retaining the certification from NRC, RIS will be a very essential role by providing platform for collaborative and accelerated processing of responses to RAI (Request of Additional Information). Preparation of responses to RAI with this kind of systematic approach may be the first in the world. Westinghouse is doing manually and using MS Excel to collect the processing status. Where as, RIS will enable each member can do his own job and collect the status automatically. In this paper, how collaborative and accelerated processing of responses to RAI can be enabled will be described, and further enhancements will also be discussed. It handles MS Word directory with the help of VSTO. And with the help of Aspose.Total for .NET, the prepared response to RAI meets NRC's requirements. Through some further work and direct integration with requirement management solution, RIS can be expanded to cover a prior impact notice in case of DCD being altered.

  5. Evaluation on thermal-hydraulic characteristics for passive safety device of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Seong Yeon; Lee, S. H.; Son, M. K. [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Jee, M. S.; Chung, M. H. [Chungnam National Univ., Taejon (Korea, Republic of)

    2001-07-15

    To establish evaluation and verification guideline for the APR1400, thermal-hydraulic characteristics for fuel rod bundle, reactor vessel and fluidic device is analyzed using FLUENT. Scope and major results of research are as follows : Thermal-hydraulic characteristics for nuclear fuel rod bundle: design data for nuclear fuel rod bundle and structure are surveyed, and 3 x 3 sub-channel model is adopted to investigate the fluid flow and heat transfer characteristics in fuel rod bundle. Computational results are compared with the heat transfer data measured by naphthalene sublimation method, and numerical analysis and evaluation are performed at various design conditions and flow conditions. Thermal-hydraulic characteristics for reactor vessel: reactor vessel design data are surveyed to develop numerical model. Porous media model is applied for fuel rod bundle, and full-scale, three dimensional simulation is performed at actual operating conditions. Distributions of velocity, pressure and temperature are discussed. Flow characteristics for fluidic device: three dimensional numerical model for fluidic device is developed, and numerical results are compared with experimental data obtained at KAERI in order to verify numerical simulation. In addition, variation of flow rate is investigated at various elapsed times after valve operating, and flow characteristics is analyzed at low and high flow rate conditions, respectively.

  6. Conceptual design of passive containment cooling system with air holdup tanks of improved APR+

    International Nuclear Information System (INIS)

    Jeon, Byong Guk; Cheon No, Hee

    2014-01-01

    In Korea, after the successful validation of passive auxiliary feedwater system (PAFS), a passive containment cooling system (PCCS) gets attention for future development. We suggested PCCS design based on APR+, an advanced PWR developed in Korea, and performed scoping analysis. On the extension of the simple scoping analysis, MARS simulation is performed to incorporate the behavior of water pool outside the containment as well as steam-air mixture inside the containment. Through the simulation we demonstrated the effectiveness of the air holdup tank (AHT). Also we investigated the effect of the models of heat transfer coefficients between steam-air mixture side and water side, and flow instability inside HX tubes. The presence of AHT enables us to reduce the number of required HX tubes more than half through an increase in the heat transfer coefficients due to the reduction of air fraction in the containment. Finally flow instability was observed and mitigated by putting orifice plates at the inlet of tubes, increasing height of return nozzle, and increasing a tube angle. (authors)

  7. Improved Design of PECS to reduce Flow Instability for EU-APR1400

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Keunsung

    2014-01-01

    For EU-APR1400, PECS (Passive Ex-vessel corium retaining and Cooling System), so-called core catcher, was adopted to keep the integrity of basemat in containment by preventing MCCI (Molten Core Concrete Interaction) through retaining core debris and cooling corium outside the reactor vessel. In this paper, the improved design of PECS is presented to increase coolability by reducing flow instability in the region of cooling channel. In this paper, flow instability analysis was carried out using CFD code to find out the most improved design of PECS, which is to increase coolability by reducing bubble entrainment in the region of cooling channel. The reduction of bubble entrainment in the downcomer facilitates higher mass flow rates in the downcomer. Among presented four designed for the downcomer of PECS, the superstep design shows the highest mass flow rate and the lowest gas holdup in the downcomer as well as in the cooling channel. Compared with the existing design, the elimination of the horizontal part and the addition of an extra space above the vertical entrance to the downcomer seem to help the separation of the vapor

  8. Development of Alarm System link Drawing for Operation Support for APR1400 Digital Main Control Room

    International Nuclear Information System (INIS)

    Kim, Ki-Hwan

    2016-01-01

    Digitalized MMI(Man-Machine Interface) including Digital Main Control Room(MCR) and digital I and C system was being applied for SKN 3 and 4 Nuclear Power Plant(NPP) and subsequent APR1400 NPP type. But, operators can not easily find instrument for alarm immediately. Therefore, Alarm system is required to easily find instrument for Alarm. For this implementation, we will plan system design considering design feature without affecting network load and CPU load. We have developed Alarm system link drawing for digital MCR. Operators of the digitalized MCR navigates from their consoles to the drawings related to the plant alarms and their instruments or the operation status. Such method gives cognitive load to the operators having to travel to different locations in finding the related information. Screen Sharing System, which is the fundamental technique for Drawing Interconnection Alarm System is close to completion, and it should be functionally tested and verified by the human factor engineering. For the actual application to the operating plants, the drawings to be interconnected to the alarms and the opinions from the operators/maintenance departments for designating alarm number should be surveyed, Also, another function that allows the access to the alarm related drawings not only from the MCR but also from the other offices

  9. Development of Alarm System link Drawing for Operation Support for APR1400 Digital Main Control Room

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki-Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Digitalized MMI(Man-Machine Interface) including Digital Main Control Room(MCR) and digital I and C system was being applied for SKN 3 and 4 Nuclear Power Plant(NPP) and subsequent APR1400 NPP type. But, operators can not easily find instrument for alarm immediately. Therefore, Alarm system is required to easily find instrument for Alarm. For this implementation, we will plan system design considering design feature without affecting network load and CPU load. We have developed Alarm system link drawing for digital MCR. Operators of the digitalized MCR navigates from their consoles to the drawings related to the plant alarms and their instruments or the operation status. Such method gives cognitive load to the operators having to travel to different locations in finding the related information. Screen Sharing System, which is the fundamental technique for Drawing Interconnection Alarm System is close to completion, and it should be functionally tested and verified by the human factor engineering. For the actual application to the operating plants, the drawings to be interconnected to the alarms and the opinions from the operators/maintenance departments for designating alarm number should be surveyed, Also, another function that allows the access to the alarm related drawings not only from the MCR but also from the other offices.

  10. The Development and Evaluation of Inherent RPCS for the APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jae D.; Ryu, Seok H.; Jung, Dong C.; Kim, Joon S.; Baek, Byung C.; Sung, Song K.; You, Guk J. [KNF, Daejeon (Korea, Republic of); Kim, Han G. [KHNP, Daejeon (Korea, Republic of); Chi, Sung G. [KOPEC, Daejeon (Korea, Republic of)

    2008-10-15

    The APR1400 RPCS (Reactor Power Cutback System) is designed to rapidly reduce the core power to eliminate the need for a reactor trip following a large load rejection or a loss of two main feedwater pumps at high power. GDC (General Design Criteria) 25 says 'Protection system requirements for reactivity control malfunctions. The protection system shall be designed to assure that SAFDL (Specified Acceptable Fuel Design Limits) are not exceeded for any single malfunction of the reactivity control systems, such as accidental withdrawal (not ejection or dropout) of control rods.' In order to comply GDC 25, CPCS (Core Protection Calculator System) will apply a big power penalty({approx} 1.3) to determine the minimum DNBR (Departure from Nucleate Boiling Ratio), the maximum LPD(Local Power Density) and reactor may immediately trip by CPCS low DNBR and high LPD during high power operation for 12-finger CEA drop. The purpose of this study is to develop the inherent RPCS to avoid unwanted reactor trips due to a 12-finger CEA drop. In order to accomplish this purpose, the CPCS should be modified to send RPCS actuation signal and not to apply power penalty due to 12-finger CEA drop for a shot period. During this period which is determined by assessment of safety, the SAFDL will not be violated without any CPCS trip function. The system and CPCS performance is evaluated to verify that CPCS trip does not occurred during 12-finger CEA drop event.

  11. Development of a Desktop Simulator for APR1400 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. B. [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    It is essential for utilities to possess a full-scope simulator for operator training and operation test for operators. But it is very expensive and sometimes lack of fidelity if processes of developing the simulator and designing the plant are in parallel. It is due to the situation that simulator development stage sometimes precedes the plant design stage and modifications may occur to the design of the plant in construction stage. In an attempt to build a low cost and efficient simulator, a desktop simulator has been developed. This model is described herein. Using desktop simulators for training operators is an efficient method for familiarizing operators with their plant’s operation. A low cost and efficient desktop simulator for APR1400 has been developed, and brief features are introduced here. It is configured to mimic a full-scale simulator, and can be used for operators to be familiarized to their plant’s operation. Since the size of the simulator is small enough to be fit in a desk, it can be used in a classroom or in an office at any time. It can also be used to evaluate design changes or modifications of the plant before implementing them to the plant.

  12. Preliminary COM3D Analysis for H{sub 2} Combustion in the APR1400 Containment

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Hyung Seok; Kim, Jongtae; Kim, Sang-Baik; Hong, Seong-Wan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In order to assure the containment integrity of APR1400, it is necessary to evaluate an overpressure buildup resulting from a propagation of hydrogen flame along the structure and wall in the containment during a severe accident using the COM3D. Korea Atomic Energy Research Institute (KAERI) established a numerical analysis system for evaluating an overpressure buildup owing to a hydrogen combustion in the containment of a nuclear power plant by importing COM3D from KIT in Germany. The COM3D has been currently used in the simulations of the combustions and explosions, together with the system of industrial risk mitigation of hydrogen and burnable gases in nuclear containment and auxiliary buildings. KAERI performed the hydrogen combustion analysis using the COM3D code with the initial hydrogen distribution calculated by the GASFLOW under assumption of 85% metal-water reaction in the reactor vessel. From the COM3D results, we can know that the pressure buildup was about 100 kPa because the flame speed was not increased above 1000 m/s and the pressure wave passed through the open spaces in the large containment.

  13. Arthrose médiale du genou : évaluations et recommandations cliniques pour les traitements par infiltration, orthèses plantaires et/ou orthèse du genou à l'aide d'analyses quantifiées de la marche

    OpenAIRE

    Dessery, Yoann

    2014-01-01

    L’arthrose du genou (gonarthrose) est une des sources d’incapacité physique les plus fréquentes dans le monde. Plusieurs traitements sont disponibles pour réduire la douleur et ralentir l’évolution de la maladie. Cependant, certains de ces traitements manquent encore de documentation ou d’ajustement par rapport aux patients. L’objectif général de cette thèse est d’évaluer l’impact de différents traitements de la gonarthrose médiale sur la vie quotidienne et le patron de marche afin d’aider le...

  14. Traitement des diagraphies acoustiques. Deuxième partie : séparation des ondes en diagraphie acoustique Full-Waveform Acoustic Data Processing. Second Part: Wave Separation in Acoustic Well Logging

    Directory of Open Access Journals (Sweden)

    Gavin P.

    2006-11-01

    Full Text Available L'utilisation d'outils acoustiques à émetteurs-récepteurs multiples et enregistrement numérique permet de faire une microsismique de puits en utilisant des techniques de traitement dérivées du traitement sismique. Comme les enregistrements acoustiques sont composés de différents types d'ondes (ondes de volume réfractées ou réfléchies et ondes d'interface, une étape importante du traitement acoustique est la séparation des ondes. Cet article montre que la séparation des ondes peut être optimisée en fonction du choix du type de collection des enregistrements acoustiques et de la performance des algorithmes utilisés, dépendante du nombre de traces par collection. Les différents types de collection sont la collection émetteur ou récepteur commun et la collection à déport constant. Trois exemples de traitement de diagraphie acoustique sont présentés. Le premier exemple montre que les interférences des ondes qui conduisent à des anomalies sur l'estimation des logs acoustiques tels que le log de lenteur (Delta t sont réduites après une bonne séparation des ondes. Le deuxième exemple est un exemple d'imagerie en puits vertical. Le traitement par filtrage de Wiener sur une section à déport constant permet de différencier les modes réfractés et d'interface des diffractions profondes (environ 4 m créées par la présence d'intercalations dolomitiques en milieu argileux. Le troisième exemple est un exemple d'imagerie en puits horizontal. Le traitement est réalisé sur une collection point de tir commun. La combinaison de filtrage en vitesse apparente pour extraire les différents types d'ondes et de filtrage matriciel pour améliorer le rapport signal sur bruit a permis d'extraire un jeu de réflexions. La connaissance a priori de la zone réservoir a permis d'identifier les événements réfléchis en-dessous et en-dessus du drain. Cet exemple montre la nécessité d'utiliser des techniques spécifiques pour lever l

  15. Single port-assisted fully laparoscopic abdominoperineal resection (APR) with immediate V-RAM flap reconstruction of the perineal defect.

    LENUS (Irish Health Repository)

    Ali, Sayid

    2012-09-01

    Abdominoperineal resection (APR) of anorectal cancers after neoadjuvant chemoradiotherapy may incur significant perineal morbidity. While vertical rectus abdominis muscle (V-RAM) flaps can fill the pelvic resection space with health tissue, their use has previously been described predominantly in association with laparotomy. Here, we describe a means of combination laparoscopic APR with V-RAM flap reconstruction that allows structural preservation of the entire abdominal wall throughout the oncological resection and of the deep parietal layers after V-RAM donation. Furthermore, a single port access device used at the end colostomy site allows a second senior surgeon assist with an additional two working instruments for the purpose of improved pelvic tissue retraction, especially useful in obese patients.

  16. Treatment and Processing of Radioactive Wastes; Traitement des Dechets Radioactifs; 041e 0411 0420 0414 ; Tratamiento de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Rodger, Walton A. [Chemical Engineering Division, Argonne National Laboratory, Lemont, IL (United States)

    1960-07-01

    Various methods which have been considered for processing and treating radioactive wastes of both low and high level are discussed. Low-Level Wastes-Gases are diluted and discharged to the atmosphere through stacks or are filtered through highly retentive filters. Typical installations are described. Incineration of combustible wastes has been examined and descriptions and operating data are given. Baling is often a useful adjunct to a solids collection system. A variety of processes for liquid wastes have been studied. Typical systems are described and operating data given. High-Level Wastes-Gases are sometimes vented directly through stacks but more often some treatment is required. The treatment takes the form of chemical scrubbing, removal of iodine on silver reactors, rare-gas removal and filtration. Highly contaminated solids may require decontamination in place before they can be removed. High-level liquid wastes represent the largest single waste-disposal problem facing the industry at the present time. This problem includes reduction in the volume of the waste originally produced by process changes or changing the process; concentration of the produced waste or reduction to solids by one of several methods including concentration, use of Portland cement, adsorption on clays or other natural materials, and calcination. The technical and economic problems associated with temporary storage are considered. It may become necessary to do waste processing at only a few carefully selected sites. Estimates are made of the amounts that might be involved in transport and of the equipment needed. The attendant hazards and costs are considered. (author) [French] L'auteur etudie les diverses methodes qui ont ete envisagees pour le traitement des dechets de faible et de haute radioactivite. Dechets, de faible radioactivite - Les gaz sont, soit dilues et evacues dans l'atmosphere par de hautes cheminees, soit filtres au moyen d'appareils a grande puissance de filtrage. L

  17. Réduction des pertes de mangues après la récolte en Asie du Sud ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    29 avr. 2016 ... Près de 70 % de la production mondiale de mangues provient de l'Inde, mais les pertes après récolte en raison d'une manutention, d'un transport et d'une transformation inadéquats peuvent atteindre 35 %. De plus, les prix obtenus par les producteurs sont souvent peu élevés à cause de la saturation du ...

  18. Migration d'une broche dans le canal médullaire cervical après une ...

    African Journals Online (AJOL)

    Migration d'une broche dans le canal médullaire cervical après une ostéosynthèse de l'articulation acromio-claviculaire. Bah Aliou, El Alaoui Adil. Abstract. We report the case of a 49 year-old right-handed chef with left shoulder trauma occurred during a football game. The diagnosis was fracture of the distal quarter of ...

  19. Evaluation Methodology for Void Swelling Susceptibility of APR1400 Reactor Vessel Internals for U.S. NRC Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kweon, Hyeong Do; Lee, Do Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The APR1400 RVI (Reactor Vessel Internals) operates in harsh conditions, such as long term exposure to neutron irradiation, high temperatures, reactor coolant environment, and other operating loads. Therefore, even though the RVI components are mainly made of austenitic stainless steel which is well known to have good mechanical and corrosion-resistive properties, these operating conditions. The aging is characterized by a chromium depletion along grain boundaries of austenitic stainless steel, a decrease in ductility and fracture toughness of the steel, an increase in yield and ultimate strength of the steel, and a potential volume change due to void formation in the steel. For these reasons, under certain conditions of stress, temperature, and level of irradiation, the void swelling which is one of the challenging degradation mechanisms affecting the integrity of the RVI may appear at specific locations of the RVI, especially due to high neutron fluence and high temperature under localized gamma heating and low velocity of coolant flow. To assess the effects of operating neutron fluences, temperatures and stresses on the material properties changes and the susceptibility to the void swelling, the evaluation methodology of the APR1400 RVI components for U.S. NRC Design Certification was suggested in this paper. The approach to the evaluation is summarized as follows: 1. RVI component list of the APR1400 is collected. 2. Initial screening to determine the evaluation scope is completed using the design values of fluences. 3. Functionality assessments (radiation transport analysis, CFD analysis, structural analysis) are sequentially performed. 4. Susceptibility to the void swelling is identified through ANSYS/USERMAT module. KHNP believes that the proposed methodology which is based on the EPRI works for operating reactors is the best way to evaluate the void swelling for new reactors such as the APR1400.

  20. L'eau et les liquides de dialyse dans le traitement de l'insuffisance rénale chronique terminale

    OpenAIRE

    Kunegel , Edouard

    2013-01-01

    Non disponible / Not available; Seules trois méthodes de traitement, aujourd'hui, s'offrent au patient insuffisant rénal chronique (IRC) en phase terminale : la dialyse péritonéale, l'hémodialyse, et la transplantation rénale. L'esquisse de ces techniques sera dessinée au fil de ce travail, avec un focus particulier sur l'hémodialyse, méthode à ce jour encore la plus utilisée. À ses débuts, les résultats proposés par cette procédure, assortis d'une lourde mortalité, étaient peu concluants.Jus...

  1. Dosage of fission products in irradiated fuel treatment effluents (radio-chemical method); Dosage des produits de fission dans les effluents du traitement des combustibles irradies (methode radiochimique)

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-07-01

    The dosage methods presented here are applicable to relatively long-lived fission products present in the effluents resulting from irradiated fuel treatment processes (Sr - Cs - Ce - Zr - Nb - Ru - I). The methods are based on the same principle: - addition of a carrying-over agent - chemical separation over several purification stages, - determination of the chemical yield by calorimetry - counting of an aliquot liquid portion. (author) [French] Les methodes de dosage presentees concernent les produits de fission a vie relativement longue presents dans les effluents de traitement des combustibles irradies (Sr - Cs - Ce - Zr - Nb - Ru - I). Elles sont toutes basees sur le meme principe: - addition d'entraineur, - separation chimique en plusieurs stades de purification, - determination du rendement chimique par calorimetrie, - comptage d'une aliquote liquide. (auteur)

  2. Etude pilote par PET/CT de la réponse à l'ipilimumab dans le traitement du mélanome métastatique.

    OpenAIRE

    Rochat, N.

    2012-01-01

    0 Abstract L'incidence du mélanome est en nette augmentation en Europe et aux Etats-Unis. La Chirurgie peut être curative au stade précoce de la maladie,la radiothérapie se pratique À visée palliative, les chimiothérapies n'ont montré que peu d'effet. Les progress actuels se font via l'immunothérapie. Des traitements par l'interleukine-2 et l'interféron-α se sont montrés efficaces chez certains patients, mais leur utilisation est limitée par leur forte toxicité. Depuis 201...

  3. Pharmacokinetic and pharmaco-technological approaches of actinides decorporation by an in vivo sequestering agent. Application to the development of new treatments; Approches pharmacocinetique et pharmacotechnique de la decorporation d'actinides par un agent complexant in vivo. Application a la mise au point de nouveaux traitements

    Energy Technology Data Exchange (ETDEWEB)

    Phan, G.

    2005-05-24

    modulate the pharmacokinetic parameters by prolonging their circulation time. Stealth liposomes of diameters reduced to around 100 nm (SL-100 nm) displayed a more convenient distribution which may improve the pharmacological effect of DTPA. Indeed, the administration of a single dose of approximately 3 {mu}mol.kg{sup -1} of DTPA encapsulated in SL-100 nm induced an excretion of more than 90% of the Pu injected activity after 16 days while one free DTPA dose of 30 {mu}mol.kg{sup -1} induced only less than 50% of excretion of Pu under the same conditions. Moreover, one weekly administration of the SL-100 nm makes it possible to reduce significantly the retention of plutonium in the liver to less than 2% of Pu injected activity and that in the skeleton to less than 0.2%, only 30 days after Pu contamination. All these improvements may be attributed to the increase in the aria under the curve of the DTPA concentrations (AUC) and to an increased distribution of DTPA to the liver and the skeleton by the SL-100 nm. Contrary to the injection of free DTPA, SL-100 nm liposomes seem to be able to interact with the macrophages and the hepatocytes in the liver, then to intercept plutonium and to prevent the deposition of the actinide in the skeleton in the rats. Liposomal formulations of DTPA and their pharmacokinetic studies thus make it possible to optimize the treatment of decorporation of Pu. (author) [French] Apres contamination interne par les actinides transuraniens, l'acide diethylene-triamine-pentaacetique (DTPA) est le seul traitement disponible pour accelerer la decorporation c'est-a-dire l'excretion hors de l'organisme de ces radiocontaminants par les voies naturelles (urinaire et fecale). Cependant, l'efficacite du DTPA est variable et semble limitee pour mobiliser les toxiques a partir de leurs sites de dEpot et de retention qui sont principalement le foie et le squelette. La molecule presente en effet une pharmacocinetique defavorable (faible

  4. Diversity of sulfur-cycle prokaryotes in freshwater lake sediments investigated using aprA as the functional marker gene.

    Science.gov (United States)

    Watanabe, Tomohiro; Kojima, Hisaya; Takano, Yoshinori; Fukui, Manabu

    2013-09-01

    The diversity of sulfate-reducing prokaryotes (SRPs) and sulfur-oxidizing prokaryotes (SOPs) in freshwater lake ecosystems was investigated by cloning and sequencing of the aprA gene, which encodes for a key enzyme in dissimilatory sulfate reduction and sulfur oxidation. To understand their diversity better, the spatial distribution of aprA genes was investigated in sediments collected from six geographically distant lakes in Antarctica and Japan, including a hypersaline lake for comparison. The microbial community compositions of freshwater sediments and a hypersaline sediment showed notable differences. The clones affiliated with Desulfobacteraceae and Desulfobulbaceae were frequently detected in all freshwater lake sediments. The SOP community was mainly composed of four major phylogenetic groups. One of them formed a monophyletic cluster with a sulfur-oxidizing betaproteobacterium, Sulfuricella denitrificans, but the others were not assigned to specific genera. In addition, the AprA sequences, which were not clearly affiliated to either SRP or SOP lineages, dominated the libraries from four freshwater lake sediments. The results showed the wide distribution of some sulfur-cycle prokaryotes across geographical distances and supported the idea that metabolic flexibility is an important feature for SRP survival in low-sulfate environments. Copyright © 2013 Elsevier GmbH. All rights reserved.

  5. Developing Optimal Procedure of Emergency Outside Cooling Water Injection for APR1400 Extended SBO Scenario Using MARS Code

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Jong Rok; Oh, Seung Jong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    In this study, we examined optimum operator actions to mitigate extended SBO using MARS code. Particularly, this paper focuses on analyzing outside core cooling water injection scenario, and aimed to develop optimal extended SBO procedure. Supplying outside emergency cooling water is the key feature of flexible strategy in extended SBO situation. An optimum strategy to maintain core cooling is developed for typical extended SBO. MARS APR1400 best estimate model was used to find optimal procedure. Also RCP seal leakage effect was considered importantly. Recent Fukushima accident shows the importance of mitigation capability against extended SBO scenarios. In Korea, all nuclear power plants incorporated various measures against Fukushima-like events. For APR1400 NPP, outside connectors are installed to inject cooling water using fire trucks or portable pumps. Using these connectors, outside cooling water can be provided to reactor, steam generators (SG), containment spray system, and spent fuel pool. In U. S., similar approach is chosen to provide a diverse and flexible means to prevent fuel damage (core and SFP) in external event conditions resulting in extended loss of AC power and loss of ultimate heat sink. Hence, hardware necessary to cope with extended SBO is already available for APR1400. However, considering the complex and stressful condition encountered by operators during extended SBO, it is important to develop guidelines/procedures to best cope with the event.

  6. A Study on the Embedment Effect in the Soil-Structure Interaction Analysis of the APR1400

    International Nuclear Information System (INIS)

    Young-Sun Jang; Kwang-Ho Joo; Chong-Hak Kim

    2002-01-01

    The SSI (Soil-Structure Interaction) analyses are being performed for the APR1400 (Advanced Power Reactor 1400 MWe, Old name - KNGR; Korean Next Generation Reactor) design, because the APR1400 is developed as a Standard Nuclear Power Plant concept enveloping suitable soil conditions. For the SSI analyses, SASSI program which adopts the Flexible Volume Method is used. In the SSI analyses, there can be uncertainties by Bond and De-bond problem between the structure and lateral soil elements. According to ASCE Standard 4, one method to address this concern is to assume no connectivity between structure and lateral soil over the upper half of the embedment of 20 ft (6 m), whichever is less. This study is performed as a part of the parametric analyses for the APR1400 seismic analyses to address the concern of the potential embedment effect on the in-structure response spectra due to connectivity between structure and lateral soil. In this study, 4 model cases are analyzed to check the potential embedment effect - Full connection, 20 ft no connectivity which is defined as a minimum De-bond depth of the soil in ASCE Standard 4 and 26.5 ft no connectivity between structure and lateral soil over the upper half of the embedment. Last one is full no connection for only reference. The in-structure response spectra are compared with the response spectra without considering the embedment effect. (authors)

  7. Outcomes of patients with abdominoperineal resection (APR) and low anterior resection (LAR) who had very low rectal cancer.

    Science.gov (United States)

    Yeom, Seung-Seop; Park, In Ja; Jung, Sung Woo; Oh, Se Heon; Lee, Jong Lyul; Yoon, Yong Sik; Kim, Chan Wook; Lim, Seok-Byung; Kim, Nayoung; Yu, Chang Sik; Kim, Jin Cheon

    2017-10-01

    We compared the oncological outcomes of sphincter-saving resection (SSR) and abdominoperineal resection (APR) in 409 consecutive patients with very low rectal cancer (i.e., tumors within 3 cm from the anal verge); 335 (81.9%) patients underwent APR and 74 (18.1%) underwent SSR. The APR group comprised higher proportions of men (67.5% vs 55.4%, P = .049) and advanced-stage patients (P cancer stages. RFS was associated with ypT and ypN stages in patients who received PCRT, while pN stage, lymphovascular invasion (LVI), and circumferential resection margin (CRM) involvement were risk factors for RFS in those who did not receive PCRT. Notably, SSR was not found to be a risk factor for RFS in either subgroup. Patients who were stratified according to cancer stage and PCRT also showed no differences in RFS according to the mode of surgery. Our results demonstrate that, regardless of PCRT administration, SSR is an effective treatment for very low rectal cancer, while CRM is an important prognostic factor for patients who did not receive PCRT.

  8. Investigation of the Condensation Effect at IRWST Pool Surface on Containment Back Pressure in APR1400 Containment

    International Nuclear Information System (INIS)

    Lee, Eui Jong; Lee, Jin Yong; Lee, Byung Chul

    2006-01-01

    The APR1400 has several new design concepts in order to improve the plant safety functions during a postulated accident. The In-Containment Refueling Water Storage Tank (IRWST) is one of the new design concepts of APR1400 and installed at the bottom of containment building to promote the plant safety functions by simplifying emergency core cooling water source and preventing release of the fission product during an accidents. This design feature, however, brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised under accident conditions. The hot steam which is released from RCS break enters into the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, colder than incoming steam. The purpose of this study is to examine closely the influence of the condensation effect at IRWST on containment back pressure in APR1400 containment building using the GOTHIC code which can predict the steam condensation on IRWST pool surface

  9. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    International Nuclear Information System (INIS)

    Lee, Eo Hwak

    2010-02-01

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  10. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eo Hwak

    2010-02-15

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  11. Review on the NEI Methodology of Debris Transport Analysis in Sump Blockage Issue for APR1400

    International Nuclear Information System (INIS)

    Kim, Jong Uk; Lee, Jeong Ik; Hong, Soon Joon; Lee, Byung Chul; Bang, Young Seok

    2007-01-01

    Since USNRC (United State Nuclear Regulatory Committee) initially addressed post-accident sump performance under Unresolved Safety Issue USI A-43, sump blockage issue has gone through GSI-191, Regulation Guide 1.82, Rev. 3 (RG. 1.82 Rev.3), and generic Letter 2004-02 for PWRs (Pressurized Water Reactors). As a response of these USNRC's activities, NEI 04-07 was issued in order to evaluate the post-accident performance of a plant's recirculation sump. The baseline methodology of NEI 04-07 is composed of break selection, debris generation, latent debris, debris transport, and head loss. In analytical refinement of NEI 04-07, computational fluid dynamic (CFD) is suggested for the evaluation of debris transport in emergency core cooling (ECC) recirculation mode as guided by RG. 1.82 Rev.3. In Korea nuclear industry also keeps step with international activities of this safety issue, with Kori 1 plant as a pioneering edge. Korean nuclear industry has been also pursuing development of an advanced PWR of APR1400, which incorporates several improved safety features. One of the key features, considering sump blockage issue, is the adoption of IRWST (In-containment Refueling Water Storage Tank). This device, as the acronym implies, changes the emergency core cooling water injection pattern. This fact makes us to review the applicability of NEI 04-07's methodology. In this paper we discuss the applicability of NEI 04- 07's methodology, and more over, new methodology is proposed. And finally the preliminary debris transport is analyzed

  12. Feasibility Study of Core Design with a Monte Carlo Code for APR1400 Initial core

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jinsun; Chang, Do Ik; Seong, Kibong [KEPCO NF, Daejeon (Korea, Republic of)

    2014-10-15

    The Monte Carlo calculation becomes more popular and useful nowadays due to the rapid progress in computing power and parallel calculation techniques. There have been many attempts to analyze a commercial core by Monte Carlo transport code using the enhanced computer capability, recently. In this paper, Monte Carlo calculation of APR1400 initial core has been performed and the results are compared with the calculation results of conventional deterministic code to find out the feasibility of core design using Monte Carlo code. SERPENT, a 3D continuous-energy Monte Carlo reactor physics burnup calculation code is used for this purpose and the KARMA-ASTRA code system, which is used for a deterministic code of comparison. The preliminary investigation for the feasibility of commercial core design with Monte Carlo code was performed in this study. Simplified core geometry modeling was performed for the reactor core surroundings and reactor coolant model is based on two region model. The reactivity difference at HZP ARO condition between Monte Carlo code and the deterministic code is consistent with each other and the reactivity difference during the depletion could be reduced by adopting the realistic moderator temperature. The reactivity difference calculated at HFP, BOC, ARO equilibrium condition was 180 ±9 pcm, with axial moderator temperature of a deterministic code. The computing time will be a significant burden at this time for the application of Monte Carlo code to the commercial core design even with the application of parallel computing because numerous core simulations are required for actual loading pattern search. One of the remedy will be a combination of Monte Carlo code and the deterministic code to generate the physics data. The comparison of physics parameters with sophisticated moderator temperature modeling and depletion will be performed for a further study.

  13. Onset of liquid droplet entrainment on a direct vessel injection system for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Han-sol; Lee, Jae-Young [Handong Global University, Pohang (Korea, Republic of); Kim, Jong-Rok; Euh, Dong-Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this research, a series of visualization works was conducted to understand droplet entrainment of the flow pattern generated in direct vessel injection system(DVI) of Korea nuclear power plant, APR 1400. In the emergency situation of a nuclear power plant, reliability of DVI cooling can be an important issue. It is known that, the amount and the rate of entrainment during the DVI cooling process can significantly affect the total heat removal. To visualize the film Reynolds number closely related with onset of droplet entrainment induced by falling film flow and lateral air flow in a small gap, confocal chromatic sensing method for measuring accurately film thickness and depth averaging particle image velocimetry for film velocity were used. The results have been post processed 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. To visualize the droplet entrainment induced by falling film flow and lateral air flow in a small gap, shadowgraph method with CCD camera (2200fps, 1280 pixel X 800 pixel, ) on coated plate with super water-repellent agent was used. The results have been post processed using 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. By adopting both super hydrophobic coating method and shadowgraph method, entrainment in a narrow gap was successfully visualized that has rarely performed before and meaningful results for DVI system research fields have been made.

  14. Onset of liquid droplet entrainment on a direct vessel injection system for APR1400

    International Nuclear Information System (INIS)

    Kim, Han-sol; Lee, Jae-Young; Kim, Jong-Rok; Euh, Dong-Jin

    2016-01-01

    In this research, a series of visualization works was conducted to understand droplet entrainment of the flow pattern generated in direct vessel injection system(DVI) of Korea nuclear power plant, APR 1400. In the emergency situation of a nuclear power plant, reliability of DVI cooling can be an important issue. It is known that, the amount and the rate of entrainment during the DVI cooling process can significantly affect the total heat removal. To visualize the film Reynolds number closely related with onset of droplet entrainment induced by falling film flow and lateral air flow in a small gap, confocal chromatic sensing method for measuring accurately film thickness and depth averaging particle image velocimetry for film velocity were used. The results have been post processed 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. To visualize the droplet entrainment induced by falling film flow and lateral air flow in a small gap, shadowgraph method with CCD camera (2200fps, 1280 pixel X 800 pixel, ) on coated plate with super water-repellent agent was used. The results have been post processed using 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. By adopting both super hydrophobic coating method and shadowgraph method, entrainment in a narrow gap was successfully visualized that has rarely performed before and meaningful results for DVI system research fields have been made

  15. Steady state flow evaluations for passive auxiliary feedwater system of APR

    International Nuclear Information System (INIS)

    Park, Jongha; Kim, Jaeyul; Seong, Hoje; Kang, Kyoungho

    2012-01-01

    This paper briefly introduces a methodology to evaluate steady state flow of APR+ Passive Auxiliary Feedwater System (PAFS). The PAFS is being developed as a safety grade passive system to completely replace the existing active Auxiliary Feedwater System (AFWS). Natural circulation cooling can be generally classified into the single-phase, two-phase, and boiling-condensation modes. The PAF is designed to be operated in a boiling-condensation natural circulation mode. The steady-state flow rate should be equal to the steady-state boiling/condensation rate determined by the steady-state energy and momentum balances in the PAFS. The determined steady-state flow rate can be used in the design optimization for the natural circulation loop of the PAFS through the steady-state momentum balance. Since the retarding force, which is to be balanced by the driving force in the natural circulation system design depends on the reliable evaluation of the success of a natural circulation system design depends on the reliable evaluation of the pressure loss coefficients. In PAFS, the core decay heat is released by natural circulation flow between the S G secondary side and the Passive Condensation Heat Exchanger (PCHX) that is immersed in the Passive Condensation Cooling Tank (PCCT). The PCCT is located on the top of Auxiliary building The driving force is determined by the difference between the S/G (heat Source) secondary water level and condensation liquid (heat sink) level. It will overcome retarding force at flowrate in the system, which is determined by vaporization and condensation of the steam which is generated at the S/G by the latent heat in system. In this study, the theoretical method to estimate the steady state flow rate in boiling-condensation natural circulation system is developed and compared with test results

  16. Analysis of a molten pool natural convection in the APR1400 RPV at a severe accident

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Park, Rae Joon; Kim, Sang Baik

    2005-01-01

    During a hypothetical severe accident, reactor fuel rods and structures supporting them are melted and relocated in the lower head of the reactor vessel. These relocated molten materials could be separated by their density difference and construct metal/oxide stratified pools in the lower head. A decay heat generated from the fuel material is transferred to the vessel wall and upper structures remaining in the reactor vessel by natural convection. As shown in Fig. 1 two-layered stratified molten pool is developed in the reactor lower vessel. The oxidic pool usually constructed by the mixture of uranium oxide and zirconium oxide. The melting temperature of the oxidic material is very high compared to the steel vessel and metallic layer. And highly turbulent natural convection generated by the decay heat enhances heat transfer to the boundary of the oxidic pool. By this thermal mechanism, oxide curst is developed around the oxidic layer as shown in Fig. 1. The oxidic pool is bounded thermally and fluid-dynamically by the developed crust. By this boundedness, the heat transfer structure in the stratified oxidic/metallic pool can be solved separately. The thermal boundary condition of the oxidic pool is isothermal with constant melting temperature of the oxidic material. The decay heat is transfer to side wall and upper interface between oxidic and metallic layer. Turbulent natural convection is dominant heat transfer mechanism in the oxidic pool. The heat transferred from the bottom oxidic layer is imposed to the upper metallic layer. This transferred heat in the metallic pool is removed through side and upper surface, which is augmented also by natural convection developed in the pool. In this study, a molten pool natural convection in the APR1400 RPV during a severe accident is simulated using the Lilac code and the calculated heat flux distribution on the reactor vessel wall is compared with a lumped-parameter (LP) prediction

  17. Microbiological Studies on the Influence of Combined Processes of Heat and Irradiation on the Survival of Saccharomyces Cerevisiae Var. Ellipsoideus; Etudes Microbiologiques sur l'Influence d'un Traitement Mixte par Chauffage et Irradiation sur la Survie de Saccharomyces Cerevisiae Var. Ellipsoideus; Mikrobiologicheskie issledovaniya vliyaniya sovmestnykh protsessov nagreva i oblucheniya na vyzhivanie saccharomyces Cerevisiae Var. Ellipsoideus; Estudios Microbiologicos de la Influencia del Calentamiento e Irradiacion Combinados Sobre la Supervivencia del Saccharomyces Cerevisiae Var. Ellipsoideus

    Energy Technology Data Exchange (ETDEWEB)

    Stehlik, G.; Kaindl, K. [Institute for Biology and Agriculture, Reaktorzentrum, Seibersdorf (Austria)

    1966-11-15

    this treatment are under investigation on apple and grape juice. (author) [French] L'un des principaux sujets de recherche inscrits au programme international sur la conservation des fruits et jus de fruits par irradiation, execute a Seibersdorf, est le probleme de la radiosensibilisation des micro-organismes. En vue d'etudier l'effet d'un traitement par la chaleur et l'irradiation sur la survie des cellules de levures (formation de colonies), une souche a forte radioresistance - Saccharomyces cerevisiae var. ellipsoideus - cultivee sur un milieu nutritif semi-synthetique, a ete soumise des le debut de sa phase logarithmique a un traitement combine par chauffage et irradiation gamma (source au cobalt-60). Le traitement thermique a ete applique, soit immediatement avant l'irradiation, soit pendant ou immediatement apres celle-ci. On a fait varier la temperature entre 20 et 52,5 Degree-Sign C. Pour l'irradiation, effectuee dans Bullet un tube en verre bien aere, on a utilise des doses allant jusqu'a 0, 3 x 10{sup 6} rad. L'effet d'inhibition de ce traitement mixte depend de l'ordre de succession du chauffage et de l'irradiation; les resultats obtenus sont les suivants: la combinaison la plus efficace est un traitement simultane par chauffage et irradiation; la combinaison qui consiste a faire suivre le chauffage d'une irradiation a la temperature ambiante est moins efficace; le moindre effet a ete obtenu par chauffage apres irradiation a la temperature ambiante. Le traitement mixte chaleur/irradiation donne des courbes de survie (fractions d'organismes survivants) qui sont des lignes droites ayant pour coordonnees la dose d'irradiation a une echelle semi-logarithimique, et la temperature dans l'intervalle compris entre la temperature ambiante et 45 Degree-Sign C. Au-dessus de 45 Degree-Sign C, les courbes indiquent, a des doses inferieures a 30 krad, un accroissement du nombre des survivants par rapport a l'echantillon non irradie. En comparant les pentes des courbes de

  18. Solvent purification using a current of water vapour. A continuous process applicable to chemical plants treating irradiated fuels; Purification des solvants par entrainement a la vapeur d'eau. Procede continu applicable aux usines chimiques de traitement des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, P.R.; Sautray, R.R.; Girard, B.R. [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1964-07-01

    sur la decontamination. L'activite en zirconium-niobium apres traitement est indecelable et il est facile d'obtenir des facteurs de decontamination de 300 sur le ruthenium. La presence d'uranium favorise la decontamination. Pour terminer, le lecteur trouvera des considerations extra-techniques et en particulier l'ordre de grandeur des prix de revient du litre de solvant traite. (auteurs)

  19. Cold-Leg Small Break LOCA Analysis of APR1400 Plant Using a SPACE/sEM Code

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Sang Gyu; Lee, Suk Ho; Yu, Keuk Jong; Kim, Han Gon; Lee, Jae Yong [Central Research Institute, KHNP, Ltd., Daejeon (Korea, Republic of)

    2013-10-15

    The Small Break Loss-of-Coolant Accident (SBLOCA) evaluation methodology (EM) for APR1400, called sEM, is now being developed using SPACE code. SPACE/sEM is to set up a conservative evaluation methodology in accordance with appendix K of 10 CFR 50. Major required and acceptable features of the evaluation models are described as below. - Fission product decay : 1.2 times of ANS97 decay curve - Critical flow model : Henry-Fauske Moody two phase critical flow model - Metal-Water reaction model : Baker-Just equation - Critical Heat Flux (CHF) : B and W, Barnett and Modified Barnett correlation - Post-CHF : Groeneveld 5.7 film boiling correlation A series of test matrix is established to validate SPACE/sEM code in terms of major SBLOCA phenomena, e.g. core level swelling and boiling, core heat transfer, critical flow, loop seal clearance and their integrated effects. The separated effect tests (SETs) and integrated effect tests (IETs) are successfully performed and these results shows that SPACE/sEM code has a conservatism comparing with experimental data. Finally, plant calculations of SBLOCA for APR1400 are conducted as described below. - Break location sensitivity : DVI line, hot-leg, cold-leg, pump suction leg. - Break size spectrum : 0.4ft{sup 2}∼0.02ft{sup 2}(DVI) 0.5ft{sup 2}∼0.02ft{sup 2}(hot-leg, cold-leg, pump suction leg) This paper deals with break size spectrum analysis of cold-leg break accidents. Based on the calculation results, emergency core cooling system (ECCS) performances of APR1400 and typical SBLOCA phenomena can be evaluated. Cold-leg SBLOCA analysis for APR1400 is performed using SPACE/sEM code under harsh environment condition. SPACE/sEM code shows the typical SBLOCA behaviors and it is reasonably predicted. Although SPACE/sEM code has conservative models and correlations based on appendix K of 10 CFR 50, PCT does not exceed the requirement (1477 K). It is concluded that ECCS in APR1400 has a sufficient performance in cold-leg SBLOCA.

  20. Cold-Leg Small Break LOCA Analysis of APR1400 Plant Using a SPACE/sEM Code

    International Nuclear Information System (INIS)

    Lim, Sang Gyu; Lee, Suk Ho; Yu, Keuk Jong; Kim, Han Gon; Lee, Jae Yong

    2013-01-01

    The Small Break Loss-of-Coolant Accident (SBLOCA) evaluation methodology (EM) for APR1400, called sEM, is now being developed using SPACE code. SPACE/sEM is to set up a conservative evaluation methodology in accordance with appendix K of 10 CFR 50. Major required and acceptable features of the evaluation models are described as below. - Fission product decay : 1.2 times of ANS97 decay curve - Critical flow model : Henry-Fauske Moody two phase critical flow model - Metal-Water reaction model : Baker-Just equation - Critical Heat Flux (CHF) : B and W, Barnett and Modified Barnett correlation - Post-CHF : Groeneveld 5.7 film boiling correlation A series of test matrix is established to validate SPACE/sEM code in terms of major SBLOCA phenomena, e.g. core level swelling and boiling, core heat transfer, critical flow, loop seal clearance and their integrated effects. The separated effect tests (SETs) and integrated effect tests (IETs) are successfully performed and these results shows that SPACE/sEM code has a conservatism comparing with experimental data. Finally, plant calculations of SBLOCA for APR1400 are conducted as described below. - Break location sensitivity : DVI line, hot-leg, cold-leg, pump suction leg. - Break size spectrum : 0.4ft 2 ∼0.02ft 2 (DVI) 0.5ft 2 ∼0.02ft 2 (hot-leg, cold-leg, pump suction leg) This paper deals with break size spectrum analysis of cold-leg break accidents. Based on the calculation results, emergency core cooling system (ECCS) performances of APR1400 and typical SBLOCA phenomena can be evaluated. Cold-leg SBLOCA analysis for APR1400 is performed using SPACE/sEM code under harsh environment condition. SPACE/sEM code shows the typical SBLOCA behaviors and it is reasonably predicted. Although SPACE/sEM code has conservative models and correlations based on appendix K of 10 CFR 50, PCT does not exceed the requirement (1477 K). It is concluded that ECCS in APR1400 has a sufficient performance in cold-leg SBLOCA

  1. A Model of Secondary Hydrocarbon Migration As a Buoyancy-Driven Separate Phase Flow Un modèle de migration secondaire des hydrocarbures considéré comme un écoulement en phases séparées régi par la poussée d'Archimède

    Directory of Open Access Journals (Sweden)

    Lehner F. K.

    2006-11-01

    Full Text Available A mathematical model of secondary migration is described which permits the prediction of hydrocarbon migration and accumulation patterns in a sedimentary basin, if source rock expulsion rates and geometrical and hydraulic properties of major carrier systems are known through geological time. In this model, secondary migration is treated as buoyancy-driven, segregated flow of hydrocarbons in hydrostatic aquifers. Lateral, updip migration is conceived as a Boussinesq-type, free-surface flow, with source and sink terms representing supply from source rocks and leakage through cap rocks and faults. This permits a two-dimensional, map-view mathematical description of a three-dimensional, time-dependent secondary migration system. A nine-point finite difference approximation has been developed to minimize numerical dispersion, and upstream-weighting is used to obtain stable solutions. Example computations for simple, single carrier bed structures are presented. L'article décrit un modèle mathématique de migration secondaire prédisant la migration des hydrocarbures et leur accumulation dans un bassin sédimentaire, lorsque les taux d'expulsion des roches mères et les propriétés géométriques et hydrauliques des principaux systèmes de drainage sont connus à l'échelle du temps géologique. Dans ce modèle, la migration secondaire est traitée comme un écoulement des hydrocarbures en phase séparée, contrôlé par la poussée d'Archimède, dans des aquifères hydrostatiques. La migration latérale est considérée comme un écoulement de type Boussinesq, à surface libre, avec des termes sources et puits représentant les apports venant des roches mères et les fuites à travers les couvertures et les failles. Ceci permet une description mathématique bidimensionnelle cartographiable d'un système de migration secondaire tridimensionnel et dépendant du temps. On utilise une approximation type différences finies à neuf points pour minimiser

  2. Predictors of exclusive breastfeeding: observations from the Alberta pregnancy outcomes and nutrition (APrON) study

    Science.gov (United States)

    2013-01-01

    Background Despite growing evidence that supports the importance of 6-month exclusive breastfeeding, few Canadian mothers adhere to this, and early weaning onto solids is a common practice. This study assessed infant feeding transitions during the first 6 months postpartum and factors that predicted exclusive breastfeeding to 3 and 6 months. Methods This prospective cohort study was part of the Alberta Pregnancy Outcomes and Nutrition study (APrON). From an initial sample of 600 pregnant women recruited from Edmonton and Calgary, 402 mothers provided complete details at 3 months postpartum; 300 stayed on to provide information at 6 months postpartum. During pregnancy and at 3 and 6 months postpartum, data on maternal and infant socio-demographic, behavior, and feeding were collected. Results Even though there was a high rate of “ever having breastfed” (98.6%), exclusive breastfeeding rates for 3 and 6 months were 54.0% and 15.3%, respectively. After controlling for potential confounders, the study showed that mothers who held post-graduate university degrees were 3.76 times more likely to breastfeed exclusively for 6 months than those without a university degree (95% CI: 1.30-10.92; p = 0.015). In addition, mother of previous children were more likely to breastfeed exclusively for 6 months (OR: 2.21, 95% CI: 1.08-4.52; p = 0.031). Mothers who were in the highest quartile of the Iowa Infant Feeding Attitude Score were 4.29 and 5.40 times more likely to breastfeed exclusively for 3 months (95% CI: 1.31-14.08; p-trend breastfeeding rate in Alberta is considerably below national and international breastfeeding recommendations. Professional advice that focuses on prenatal maternal knowledge, attitudes, and misperceptions may promote adherence to World Health Organization breastfeeding guidelines. Knowing that exclusive breastfeeding is less likely to take place among lower-educated, primiparous women may help health practitioners focus their

  3. Development of an amphibious robot for visual inspection of APR1400 Npp IRWST strainer

    International Nuclear Information System (INIS)

    Jang, You Hyun; Kim, Jong Seog

    2014-01-01

    An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of installing sole

  4. Development of an amphibious robot for visual inspection of APR1400 Npp IRWST strainer

    Energy Technology Data Exchange (ETDEWEB)

    Jang, You Hyun; Kim, Jong Seog [Korea Hydro Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)

    2014-06-15

    An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of installing sole

  5. Predictors of exclusive breastfeeding: observations from the Alberta pregnancy outcomes and nutrition (APrON) study.

    Science.gov (United States)

    Jessri, Mahsa; Farmer, Anna P; Maximova, Katerina; Willows, Noreen D; Bell, Rhonda C

    2013-05-16

    Despite growing evidence that supports the importance of 6-month exclusive breastfeeding, few Canadian mothers adhere to this, and early weaning onto solids is a common practice. This study assessed infant feeding transitions during the first 6 months postpartum and factors that predicted exclusive breastfeeding to 3 and 6 months. This prospective cohort study was part of the Alberta Pregnancy Outcomes and Nutrition study (APrON). From an initial sample of 600 pregnant women recruited from Edmonton and Calgary, 402 mothers provided complete details at 3 months postpartum; 300 stayed on to provide information at 6 months postpartum. During pregnancy and at 3 and 6 months postpartum, data on maternal and infant socio-demographic, behavior, and feeding were collected. Even though there was a high rate of "ever having breastfed" (98.6%), exclusive breastfeeding rates for 3 and 6 months were 54.0% and 15.3%, respectively. After controlling for potential confounders, the study showed that mothers who held post-graduate university degrees were 3.76 times more likely to breastfeed exclusively for 6 months than those without a university degree (95% CI: 1.30-10.92; p = 0.015). In addition, mother of previous children were more likely to breastfeed exclusively for 6 months (OR: 2.21, 95% CI: 1.08-4.52; p = 0.031). Mothers who were in the highest quartile of the Iowa Infant Feeding Attitude Score were 4.29 and 5.40 times more likely to breastfeed exclusively for 3 months (95% CI: 1.31-14.08; p-trend < 0.001) and 6 months (95% CI: 2.75-10.60; P-trend < 0.001), respectively. The 6-month exclusive breastfeeding rate in Alberta is considerably below national and international breastfeeding recommendations. Professional advice that focuses on prenatal maternal knowledge, attitudes, and misperceptions may promote adherence to World Health Organization breastfeeding guidelines. Knowing that exclusive breastfeeding is less likely to take place among lower

  6. DEVELOPMENT OF AN AMPHIBIOUS ROBOT FOR VISUAL INSPECTION OF APR1400 NPP IRWST STRAINER ASSEMBLY

    Directory of Open Access Journals (Sweden)

    YOU HYUN JANG

    2014-06-01

    Full Text Available An amphibious inspection robot system (hereafter AIROS is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of

  7. 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)

  8. Caractérisation et tests de traitement des déchets ménagers et boues de vidange par voie anaérobie et compostage pour la ville de Kinshas

    OpenAIRE

    Mindele Ukondalemba, Léonard

    2016-01-01

    Dans les pays en développement (PED) en général et en République Démocratique du Congo en particulier, la problématique de l’assainissement (eaux usées et des déchets solides) constitue un enjeu majeur pour les spécialistes et les autorités locales. Cette thèse a comme objectif général de faire une évaluation de l’état des lieux et de dégager des pistes possibles de traitements des déchets solides et liquides en vue de protéger les populations et de s’orienter vers des traitements qui res...

  9. Émissions azotées au champ et performances des machines lors de l'épandage de boues issues du traitement des eaux usées

    OpenAIRE

    Pradel, M.; Pacaud, T.; Cariolle, M.

    2011-01-01

    / Ce document est un rapport de synthèse des travaux réalisés dans le cadre du projet Ecodefi sur l'estimation des émissions azotées lors de l'épandage de boues issues du traitement des eaux usées en lien avec les performances technologiques des machines utilisées à cet effet.

  10. Analysis of MSGTR events for APR1400 by means of best estimate thermal-hydraulic system code

    International Nuclear Information System (INIS)

    Jeong, Ji Hwan; Kim, Sang Jae; Chang, Keun Sun; Lee, Jae Hun

    2001-01-01

    A multiple steam generator tube rupture (MSGTR) event has never occurred in the history of commercial nuclear reactor operation while single steam generator tube rupture (SGTR) event is reported to occur every two years. As there is no history of MSGTR event, the understandings of transients and consequences of this event are not so much. In this study, a postulated MSGTR event in advanced power reactor 1400 (APR1400) is analyzed using thermal-hydraulic system code. The APR 1400 is a two-loop, 1000 MWe, PWR supposed to be built in 2009. MARS1.4 is used in this study. The present study aims to understand the effects of rupture location in heat transfer tubes and selection of affected steam generator following a MSGTR event. The effects of five tube rupture locations are compared with each other. The comparison shows that the response of APR1400 is to allow shortest time for operator action following a tubes rupture in the vicinity of hot-leg side tube sheet and to allow longest time following a tube ruptures at the tube top. The MSSV lift time for rupture at tube-top is evaluated as 24.5% larger than that for rupture at hot-leg side tube sheet. Also, the MSSV lift time for four cases are compared in order to examine how long operator response time is allowed depending on which steam generator is affected. The comparison shows that the cases for both of two steam generators are affected allow longer time for operator action compared with the cases that a single steam generator is affected. Further more, the tube ruptures in the steam generator where a pressurizer is linked leads to the shortest operator response time

  11. CFD Analysis of Random Turbulent Flow Load in Steam Generator of APR1400 Under Normal Operation Condition

    International Nuclear Information System (INIS)

    Lim, Sang Gyu; You, Sung Chang; Kim, Han Gon

    2011-01-01

    Regulatory guide 1.20 revision 3 of the Nuclear Regulatory Committee (NRC) modifies guidance for vibration assessments of reactor internals and steam generator internals. The new guidance requires applicants to provide a preliminary analysis and evaluation of the design and performance of a facility, including the safety margins of during normal operation and transient conditions anticipated during the life of the facility. Especially, revision 3 require rigorous assessments of adverse flow effects in the steam dryer cased by flow-excited acoustic and structural resonances such as the abnormality from power-uprated BWR cases. For two nearly identical nuclear power plants, the steam system of one BWR plant experienced failure of steam dryers and the main steam system components when steam flow was increased by 16 percent for extended power uprate (EPU). The mechanisms of those failures have revealed that a small adverse flow changing from the prototype condition induced severe flow-excited acoustic and structural resonances, leading to structural failures. In accordance with the historical background, therefore, potential adverse flow effects should be evaluated rigorously for steam generator internals in both BWR and Pressurized Water Reactor (PWR). The Advanced Power Reactor 1400 (APR1400), an evolutionary light water reactor, increased the power by 7.7 percent from the design of the 'Valid Prototype', System80+. Thus, reliable evaluations of potential adverse flow effects on the steam generator of APR1400 are necessary according to the regulatory guide. This paper is part of the computational fluid dynamics (CFD) analysis results for evaluation of the adverse flow effect for the steam generator internals of APR1400, including a series of sensitivity analyses to enhance the reliability of CFD analysis and an estimation the effect of flow loads on the internals of the steam generator under normal operation conditions

  12. Réduction des pertes de mangues après la récolte en Asie du Sud ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    29 avr. 2016 ... On a également conçu des boîtes spéciales contenant de la fibre de banane imprégnée d'hexanal, dont l'utilisation pour le transport de la mangue permet de conserver le fruit beaucoup plus longtemps. Réduction des pertes de mangues après la récolte en Asie du Sud​ (PDF, 506 Ko). Il s'agit de l'une ...

  13. Contrôle hormonal des caractéristiques des fibres musculaires après la naissance

    OpenAIRE

    Cassar-Malek, Isabelle; Listrat, Anne; Picard, Brigitte

    1998-01-01

    Après la naissance, la croissance et les propriétés contractiles et métaboliques des fibres musculaires sont soumises à une régulation endocrinienne complexe. A l’exception des glucocorticoïdes, la plupart des hormones présente une action anabolique sur le tissu musculaire. Leur influence sur les caractéristiques des fibres est cependant très différente. Ainsi, les hormones somatotropes affectent peu la composition en fibres des muscles. La GH, comme l’IGF-1, régulerait cependant l’expression...

  14. Development of a Human Performance Evaluation Support System for Human Factors Validation of MCR MMI Design in APR-1400

    International Nuclear Information System (INIS)

    Ha, Jun Su; Seong, Poong Hyun

    2005-01-01

    As CRT-based display and advanced information technology were applied to advanced reactors such as APR-1400 (Advanced Power Reactor-1400), human operators' tasks became more cognitive works. As a results, Human Factors Engineering (HFE) became more important in designing the MCR (Main Control Room) MMI (Man-Machine Interface) of an advanced reactor. According to the Human Factors Engineering Program Review Model, human factors validation of MCR MMI design should be performed through performance-based tests to determine whether it acceptably supports safe operation of the plant. In order to support the evaluation of the performance, a HUman Performance Evaluation Support System (HUPESS) is in development

  15. Evolution of glycaemia in the rat after gamma irradiation; Evolution de la glycemie chez le rat apres irradiation gamma

    Energy Technology Data Exchange (ETDEWEB)

    Marble, G; Frossard, H; Breuil, L; Engler, R [Commissariat a l' Energie Atomique, Fontenay aux Roses (France). Centre d' Etudes Nucleaires

    1965-07-01

    The study of glycaemia variations in the rat after irradiation has made it possible to observe not only a premature hyperglycemia but also a belated hypoglycemia whose importance and subsequent evolution seem to depend on the dose given to the animal. (authors) [French] L'etude des variations de la glycemie du rat apres irradiation a permis de noter une hyperglycemie precoce mais egalement une hypoglycemie retardee dont l'amplitude et l'evolution seraient fonction de la dose delivree a l'animal. (auteurs)

  16. Multi-analytical characterisation of D’Aprés Cormon by José Veloso Salgado

    Energy Technology Data Exchange (ETDEWEB)

    Cardeira, A.M. [Faculdade de Belas-Artes da Universidade de Lisboa, Largo da Academia Nacional de Belas-Artes, 1249-058 Lisboa (Portugal); Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Longelin, S. [Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Costa, S.; Candeias, A. [Laboratório José de Figueiredo, Direcção Geral do Património Cultural, Rua das Janelas Verdes 37, 1249-018 Lisboa (Portugal); Laboratório HERCULES e Centro de Química de Évora, Universidade de Évora, Largo Marquês de Marialva 8, 7000 Évora (Portugal); Carvalho, M.L. [Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Manso, M., E-mail: marta974@cii.fc.ul.pt [Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal)

    2014-07-15

    This case study reveals the analytical characterisation carried out on ‘D’Aprés Cormon’ (1891) by Veloso Salgado, a copy of ‘Caïn’ (1880) by Fernando Cormon, belonging nowadays to Musée d’Orsay. Infrared Reflectography made in situ revealed underdrawing grid that was used to transpose the original painting to a smaller scale, pictorial style, execution method and retouched/restored areas. In situ EDXRF analysis together with Raman microscopy allowed the identification of gypsum, lead white, titanium white, yellow ochre, vermilion, ultramarine and lamp black. These results provide valuable information about the Salgado’s palette and his production technique.

  17. Preliminary design of S-CO{sub 2} Brayton cycle for APR-1400 with power generation and desalination process

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Seong Jun; Lee, Won Woong; Jeong, Yong Hoon; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [KUSTAR, Abu Dhabi (United Arab Emirates)

    2015-10-15

    This study was conducted to explore the capabilities of the S-CO{sub 2} Brayton cycle for a cogeneration system for APR-1400 application. Three concepts of the S-CO{sub 2} simple recuperated co-generation cycle were designed. A supercritical CO{sub 2} (S-CO{sub 2}) Brayton cycle is recently receiving significant attention as a promising power conversion system in wide range of energy applications due to its high efficiency and compact footprint. The main reason why the S-CO{sub 2} Brayton cycle has these advantages is that the compressor operates near the critical point of CO{sub 2} (30.98 .deg. C, 7.38MPa) to reduce the compression work significantly compared to the other Brayton cycles. In this study, the concept of replacing the entire steam cycle of APR-1400 with the S-CO{sub 2} Brayton cycle is evaluated. The power generation purpose S-CO{sub 2} Brayton cycles are redesigned to generate power and provide heat to the desalination system at the same time. The performance of these newly suggested cycles are evaluated in this paper. The target was to deliver 147MW heat to the desalination process. The thermal efficiencies of the three concepts are not significantly different, but the 3{sup rd} concept is relatively simpler than other cycles because only an additional heat exchanger is required. Although the 2{sup nd} concept is relatively complicated in comparison to other concepts, the temperatures at the inlet and outlet of the DHX are higher than that of the others. As shown in the results, the S-CO{sub 2} Brayton cycles are not easy to outperform the steam cycle with very simple layout and general design points under APR-1400 operating condition. However, this study shows that the S-CO{sub 2} Brayton cycles can be designed as a co-generation cycle while producing the target desalination heat with a simple configuration. In addition, it was also found that the S-CO{sub 2} Brayton cycle can achieve higher cycle thermal efficiency than the steam power cycle under

  18. Expression, purification, and characterization of the Necator americanus aspartic protease-1 (Na-APR-1 (M74)) antigen, a component of the bivalent human hookworm vaccine.

    Science.gov (United States)

    Seid, Christopher A; Curti, Elena; Jones, R Mark; Hudspeth, Elissa; Rezende, Wanderson; Pollet, Jeroen; Center, Lori; Versteeg, Leroy; Pritchard, Sonya; Musiychuk, Konstantin; Yusibov, Vidadi; Hotez, Peter J; Bottazzi, Maria Elena

    2015-01-01

    Over 400 million people living in the world's poorest developing nations are infected with hookworms, mostly of the genus Necator americanus. A bivalent human hookworm vaccine composed of the Necator americanus Glutathione S-Transferase-1 (Na-GST-1) and the Necator americanus Aspartic Protease-1 (Na-APR-1 (M74)) is currently under development by the Sabin Vaccine Institute Product Development Partnership (Sabin PDP). Both monovalent vaccines are currently in Phase 1 trials. Both Na-GST-1 and Na-APR-1 antigens are expressed as recombinant proteins. While Na-GST-1 was found to express with high yields in Pichia pastoris, the level of expression of Na-APR-1 in this host was too low to be suitable for a manufacturing process. When the tobacco plant Nicotiana benthamiana was evaluated as an expression system, acceptable levels of solubility, yield, and stability were attained. Observed expression levels of Na-APR-1 (M74) using this system are ∼300 mg/kg. Here we describe the achievements and obstacles encountered during process development as well as characterization and stability of the purified Na-APR-1 (M74) protein and formulated vaccine. The expression, purification and analysis of purified Na-APR-1 (M74) protein obtained from representative 5 kg reproducibility runs performed to qualify the Na-APR-1 (M74) production process is also presented. This process has been successfully transferred to a pilot plant and a 50 kg scale manufacturing campaign under current Good Manufacturing Practice (cGMP) has been performed. The 50 kg run has provided a sufficient amount of protein to support the ongoing hookworm vaccine development program of the Sabin PDP.

  19. Monitoring the impact of an aspartic protease (MpAPr1) on grape proteins and wine properties.

    Science.gov (United States)

    Theron, Louwrens Wiid; Bely, Marina; Divol, Benoit

    2018-04-23

    The perception of haze in wine is brought about when pathogenesis-related proteins become unstable and aggregate, subsequently resulting in crosslinking until it develops into light-dispersing particles. Elimination of these proteins is usually achieved via bentonite fining, which, although effective, suffers from several drawbacks. The utilization of proteases has been proposed as an ideal alternative. In a previous study, an aspartic protease (MpAPr1) from the yeast Metschnikowia pulcherrima was purified and shown to be partially active against grape proteins in synthetic medium. In this study, the effects of pure MpAPr1 supplemented to Sauvignon Blanc juice on subsequent fermentation were investigated. The juice was incubated for 48 h and thereafter inoculated with Saccharomyces cerevisiae. Results revealed that the enzyme had no observable effects on fermentation performance and retained activity throughout. Protein degradation could be detected and resulted in a significant modification of the wine composition and an increase in the presence of certain volatile compounds, especially those linked to amino acid metabolism.

  20. Unit Risk Quotient (RQ) and Relative Significance of Radionuclide on Flora and Fauna to the EU-APR Optimization

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Keunsung [KHNP-CRI, Daejeon (Korea, Republic of); Kim, Sukhoon [FNC Technology Co., Ltd., Yongin (Korea, Republic of); Lee, Chonghui [KEPCO E and C, Yongin (Korea, Republic of)

    2015-05-15

    As part of the project for acquiring the certification from EUR organization, in accordance with Articles 4.8 and 5.5 specified in Section 2.20 of EUR Volume 2, the effects of ionizing radiation from the standard design of EU-APR on biota and ecosystems during operation and decommissioning phases shall be assessed. This assessment must be carried out according to the ERICA (i.e. Environmental Risk from Ionizing Contaminants: Assessment and management) integrated approach. This paper describes the evaluation results for unit risk quotient and relative significance by radionuclide derived from performing Tier 1 assessment on flora and fauna for the EU-APR design using ERICA Tool. As specified previously, Pa-231 and Th-228 are the most significant for the terrestrial and for the marine/freshwater ecosystems, respectively. And, in terms of environmental risk, those radionuclides having the most impact on flora and fauna are relatively more significant than isotope having the least impact by about 7 to 10 orders of magnitude.

  1. Unit Risk Quotient (RQ) and Relative Significance of Radionuclide on Flora and Fauna to the EU-APR Optimization

    International Nuclear Information System (INIS)

    Lee, Keunsung; Kim, Sukhoon; Lee, Chonghui

    2015-01-01

    As part of the project for acquiring the certification from EUR organization, in accordance with Articles 4.8 and 5.5 specified in Section 2.20 of EUR Volume 2, the effects of ionizing radiation from the standard design of EU-APR on biota and ecosystems during operation and decommissioning phases shall be assessed. This assessment must be carried out according to the ERICA (i.e. Environmental Risk from Ionizing Contaminants: Assessment and management) integrated approach. This paper describes the evaluation results for unit risk quotient and relative significance by radionuclide derived from performing Tier 1 assessment on flora and fauna for the EU-APR design using ERICA Tool. As specified previously, Pa-231 and Th-228 are the most significant for the terrestrial and for the marine/freshwater ecosystems, respectively. And, in terms of environmental risk, those radionuclides having the most impact on flora and fauna are relatively more significant than isotope having the least impact by about 7 to 10 orders of magnitude

  2. Performance Assessment of Turbulence Models for the Prediction of the Reactor Internal Flow in the Scale-down APR+

    International Nuclear Information System (INIS)

    Lee, Gonghee; Bang, Youngseok; Woo, Swengwoong; Kim, Dohyeong; Kang, Minku

    2013-01-01

    The types of errors in CFD simulation can be divided into the two main categories: numerical errors and model errors. Turbulence model is one of the important sources for model errors. In this study, in order to assess the prediction performance of Reynolds-averaged Navier-Stokes (RANS)-based two equations turbulence models for the analysis of flow distribution inside a 1/5 scale-down APR+, the simulation was conducted with the commercial CFD software, ANSYS CFX V. 14. In this study, in order to assess the prediction performance of turbulence models for the analysis of flow distribution inside a 1/5 scale-down APR+, the simulation was conducted with the commercial CFD software, ANSYS CFX V. 14. Both standard k-ε model and SST model predicted the similar flow pattern inside reactor. Therefore it was concluded that the prediction performance of both turbulence models was nearly same. Complex thermal-hydraulic characteristics exist inside reactor because the reactor internals consist of fuel assembly, control rod assembly, and the internal structures. Either flow distribution test for the scale-down reactor model or computational fluid dynamics (CFD) simulation have been conducted to understand these complex thermal-hydraulic features inside reactor

  3. Cost of transporting irradiated fuels and maintenance costs of a chemical treatment plant for irradiated fuels; Cout de transport des combustibles irradies et cout d'entretien d'une usine de traitement chimique des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    other plants, an attempt has been made to express the maintenance costs as a percentage of the investments corresponding to each of the sections considered. The unequal aspect of maintenance in a plant of this type is demonstrated, this being due particularly to the inaccessibility of most of the equipment during operation. Finally some conclusions are drawn on what the maintenance costs could be and the means of reducing them in future plants. (author) [French] Le cout du cycle des combustibles a fait l'objet de nombreuses etudes mais beaucoup d'entre elles sont basees sur des etudes a priori et sont donc plus ou moins sujettes a caution. C'est ainsi que dans la partie ayant trait au traitement des combustibles irradies, des elements importants du cout n'ont que rarement ete precises a la suite d'experiences pratiques: le cout du transport des combustibles eux-memes et le cout d'entretien de l'usine. Les etudes relatives au cout du transport sont generalement basees sur des calculs faits a partir de donnees un peu arbitraires. Les etudes qui ont ete faites en France pour le transport d'uranium irradie entre les reacteurs EdF de Chinon et l'usine de retraitement de La Hague et l'uranium irradie des reacteurs de recherches jusqu'aux usines de retraitement etrangeres sont exposees et montrent qu'il a ete possible d'arriver a des types de chateaux de transport et des modalites d'expedition qui permettent de diminuer les couts dans des proportions tres importantes. Ceci a pu etre obtenu soit en combinant les transports par rail et par route soit par l'augmentation des capacites unitaires des chateaux de transport: on cite le cas d'un chateau de transport pour element des piles piscines qui est capable de transporter un coeur complet d'une pile a la fois entrainant une reduction substantielle du cout. Les etudes concernant les couts d'entretien d'usines de retraitement sont encore plus rares, or, dans les usines a entretien direct, ces couts sont une fraction non negligeable

  4. MDEP Design-Specific Common Position CP-APR1400WG-01. Common position addressing Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2016-05-01

    The MDEP APR1400 Working Group (APR1400WG) members consist of members from Republic of Korea, United Arab Emirates, and the United States. A main objectives of MDEP is to encourage convergence of code, standard and safety goals with exploring the opportunities for harmonization of regulatory practice and cooperation on safety review of APR-1400 specific designs. This common position addressing is aimed at sharing knowledge, information and experience on safety improvement related to lessons learned from the Fukushima Daiichi NPP Accident or Fukushima Daiichi NPP Accident-related issues amongst APR-1400 WG member states to achieve the MEDP goal. Because not all of these Regulators have completed the regulatory review of their APR1400 applications yet, this paper identifies common preliminary approaches to address potential safety improvements for APR1400 plants, as well as common general expectations for new nuclear power plants, as related to lessons learned from the Fukushima Daiichi NPP Accident or Fukushima Daiichi NPP Accident-related issues. While some asymmetry exists among those of three Regulators in terms of design, regulatory practice and licensing milestone sharing information and common understanding on post-Fukushima Daiichi NPP Accident enhancement would be promote resilient design for countering beyond design extreme external event like Fukushima Daiichi NPP nuclear disaster. This common position paper aims at identifying characteristics of post-Fukushima Daiichi NPP Accident enhancements putting in place by each country and setting common position to achieve balanced and harmonized APR-1400 design. After the safety reviews of the APR1400 design applications that are currently in review are completed, the regulators will update this paper to reflect their safety conclusions regarding the APR1400 design and how the design could be enhanced to address Fukushima Daiichi NPP Accident-related issues. The common preliminary approaches are organised into

  5. Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Oger, C; Vaumas, P de [Saint-Gobain Nucleaire, 92 - Courbevoie (France)

    1964-07-01

    processing plants are shown, different from those in part two. The indirect effect of these reprocessing programmes on the availability of plutonium, and therefore on the possibility.of undertaking plutonium burning reactor programmes, must be taken into account. (authors) [French] L'objet de cette communication est d'apporter une contribution a la solution du probleme du choix des tailles et des localisations optimales des usines de traitement des combustibles nucleaires irradies, associees a des programmes de puissance electrique installee. Dans une premiere partie, on etudie la structure des couts d'investissements et d'exploitation des usines de traitement de l'uranium naturel irradie, l'influence de la taille des usines sur ces couts et ces structures de couts. Au cout de traitement de l'uranium naturel irradie s'ajoute d'autre part le cout du transport des combustibles irradies des lieux de production aux sites des usines de traitement. La recherche du cout minimum pour la production d'un pays ou d'un ensemble de pays fait donc intervenir a la fois la taille et la localisation des usines. On indique les couts de transport previsibles pour l'uranium naturel irradie et la structure de ces couts (transport, assurance, couts et amortissement des containers). Dans une deuxieme partie, et pour differents echeanciers de combustibles irradies a traiter chaque annee, on determine les tailles et les localisations optimales des usines de traitement et la sensibilite de ces resultats, aux hypotheses de base concernant le cout du traitement, le cout du transport, l'annee de demarrage du programme d'usines, l'horizon choisi. - le probleme de nature combinatoire, assez complexe, est resolu par l'application des methodes de la programmation dynamique. - on montre que les methodes sont egalement applicables au probleme du choix des tailles et des localisations optimales des usines de traitement des elements du type MTR, associees aux programmes de reacteurs de recherche ainsi qu

  6. aprABC: A Mycobacterium tuberculosis complex-specific locus that modulates pH-driven adaptation to the macrophage phagosome

    Science.gov (United States)

    Abramovitch, Robert B.; Rohde, Kyle H.; Hsu, Fong-Fu; Russell, David G.

    2011-01-01

    Summary Following phagocytosis by macrophages, Mycobacterium tuberculosis (Mtb) senses the intracellular environment and remodels its gene expression for growth in the phagosome. We have identified an Acid and Phagosome Regulated (aprABC) locus that is unique to the Mtb complex and whose gene expression is induced during growth in acidic environments in vitro and in macrophages. Using the aprA promoter, we generated a strain that exhibits high levels of inducible fluorescence in response to growth in acidic medium in vitro and in macrophages. aprABC expression is dependent on the two-component regulator phoPR, linking phoPR signaling to pH sensing. Deletion of the aprABC locus causes defects in gene expression that impact aggregation, intracellular growth, and the relative levels of storage and cell wall lipids. We propose a model where phoPR senses the acidic pH of the phagosome and induces aprABC expression to fine-tune processes unique for intracellular adaptation of Mtb complex bacteria. PMID:21401735

  7. Characterisation of the thermostable protease AprX in strains of Pseudomonas fluorescens and impact on the shelf-life of dairy products: preliminary results

    Directory of Open Access Journals (Sweden)

    Nadia Andrea Andreani

    2016-12-01

    Full Text Available Bacterial proteases are involved in food spoilage and shelf-life reduction. Among the bacterial proteases, a predominant role in spoilage of dairy products seems to be played by the thermostable metallo-protease AprX, which is produced by various strains of Pseudomonas fluorescens. Differences in AprX enzyme activity among different strains were highlighted, but the most proteolytic strains were not identified. In this study, the presence of the aprX gene was evaluated in 69 strains isolated from food matrices and 18 reference strains belonging to the P. fluorescens group, which had been previously typed by the multi locus sequence typing method. Subsequently, a subset of reference strains was inoculated in ultra-high temperature milk, and the expression of the aprX gene was evaluated at 22 and 6°C. On the same milk samples, the proteolytic activity was then evaluated through Azocasein and trinitrobenzenesulfonic acid solution assays. Finally, to assess the applicability of the former assay directly on dairy products the proteolityc activity was tested on industrial ricotta samples using the Azocasein assay. These results demonstrate the spread of aprX gene in most strains tested and the applicability of Azocasein assay to monitor the proteolytic activity in dairy products.

  8. Fission product determination in irradiated fuel processing waste (electrophoresis); Dosage des produits de fission dans les effluents de traitement des combustibles irradies (electrophorese)

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M; Tret, J [Commissariat a l' Energie Atomique, Centre de Marcoule, 30 - Bagnols-sur-Ceze (France). Centre de Production de Plutonium de Marcoule. Services d' Extraction du Plutonium

    1966-07-01

    This dosage method concerns fission products present in the waste produced from the processing of cooled irradiated fuels. - Sr, Cs, Ce, Y, Ru by quantitative analysis; - Zr, Nb by qualitative analysis. It includes electrophoresis on paper strips one meter long which is then analysed between two window-less Geiger counters. For an activity of 10{sup -2} {mu}Ci of any cation in a 10 {mu}l spot, the standard error {sigma} if 3 to 4 per cent. complete analysis lasts about 5 hours. (authors) [French] Cette methode de dosage concerne les produits de fission presents dans les effluents de traitement des combustibles irradies refroidis: - Sr, Cs, Ce, Y, Ru en analyse quantitative; - Zr, Nb en analyse qualitative. Elle comporte une electrophorese sur bande de papier de un metre de longueur suivie d'un depouillement entre deux compteurs Geiger sans fenetre. Pour une activite de 10{sup -2} {mu}Ci d'un cation quelconque dans une tache de 10 {mu}l l'erreur standard {sigma} est de 3 a 4 pour cent. L'analyse complete demande environ 5 heures. (auteurs)

  9. Forecast evaluation of the impact of the concomitant chemoradiotherapy after conservative breast treatment on the esthetic satisfaction: difference between physician and patient assessment; Evaluation prospective de l'impact de la chimioradiotherapie concomitante apres traitement conservateur du cancer du sein sur la satisfaction esthetique: difference entre l'appreciation du medecin et celle des patientes

    Energy Technology Data Exchange (ETDEWEB)

    Toledano, A. [Hopital Tenon, APHP, 75 - Paris (France); Garaud, P.; Le Floch, O.; Calais, G. [Henry Kaplan, CHU, 37 - Tours (France); Bollet, M.; Fourquet, A. [Institut Curie, 75 Paris (France); Serin, D. [Institut Sainte-Catherine, 84 - Avignon (France); Miny-Buffete, J. [CHU Minjoz, 25 - Besancon (France); Favre, A. [CHR La Source, 45 - Orleans (France); Azria, D. [CRLC Val-d' Aurelle, 34 - Montpellier (France)

    2006-11-15

    After conservative surgery of mammary glands, the concomitant chemoradiotherapy leads a significant increase of delayed effects ( stage over or equal to 2). The esthetic result is also subjective. The patients satisfaction is superior to the physician's ones after conservative treatment of mammary glands and is not only determined by delayed toxicity. Several methods of evaluation allow to find an esthetic result more harmful after concomitant chemoradiotherapy. (N.C.)

  10. Is it always possible to respect dose constraints for target volumes and organs at risk within the frame of breast radiotherapy after conservative treatment?; Le respect des contraintes de dose aux volumes cibles et aux organes a risque est-il toujours possible dans le cadre d'une radiotherapie du sein apres traitement conservateur?

    Energy Technology Data Exchange (ETDEWEB)

    Renoult, F.; Faivre, J.C.; Charra Brunaud, C.; Tournier-Rangeard, L.; Lostette, J.; Huger, S.; Marchesi, V.; Peiffert, D.; Marchal, C. [Centre Alexis-Vautrin, 54 - Nancy (France); Xemard, S. [Centre hospitalier Jean-Monnet, 88 - Epinal (France)

    2010-10-15

    The use of three-dimensional breast radiotherapy after a conservative treatment allowed cardiotoxicity as well as the dose delivered to lungs to be significantly reduced. However several bibliographic references give different dose constraints. Based on the constraints given by the Oncological radiotherapy French Society (SFRO), the authors analysed whether these recommendations could be actually respected within a daily practice. Based on a sample of 91 patients, the authors collected the following data: mammary gland volumes receiving respectively 95 and 107% of the dose before the boost calculation, heart and pulmonary volumes receiving different dose levels. Coverage constraints are indicated. It appears that the present technique does not allow the constraints to be respected in a majority of cases. Short communication

  11. Reported case of a grade 3 toxicity after treatment of an hepatic metastasis by CyberKnife{sup R}; Cas rapporte d'une toxicite de grade 3 apres traitement d'une metastase hepatique par CyberKnife{sup R}

    Energy Technology Data Exchange (ETDEWEB)

    Baumann, A.S.; Taste-George, H.; Marchesi, V.; Buccheit, I.; Beckendorf, V.; Peiffert, D. [Centre Alexis-Vautrin, Vandceuvre -les-Nancy (France)

    2011-10-15

    The authors briefly describe the treatment plan dosimetry for a patient irradiated several times with CyberKnife in the liver and suffering from a grade 3 toxicity of gastric-antrum-ulcer type. They conclude that dose constraints for organs at risk must be scrupulously respected within the frame of hypo-fractionated treatments because side effects can be severe and difficult to treat. Short communication

  12. Hypothyroidism following cervical irradiation in the management of carcinoma of the nasopharynx and of the breast: a prospective study on eighty-four cases; Hypothyroidie apres irradiation cervicale dans le traitement des cancers du nasopharynx et du sein: etude prospective a propos de 84 patients

    Energy Technology Data Exchange (ETDEWEB)

    Daoud, J.; Siala, W. [Centre Hospitalier Universitaire-Habib Bourguiba, Service de Radiotherapie Carcinologique (Tunisia); Guermazi, F. [Service de Medicine Nucleaire de Sfax (Tunisia); Besbes, M. [Institut Salah-Azaiez de Tunis, Service de Radiotherapie Carcinologique (Tunisia); Frikha, M. [Service de Carcinologie Medicale de Sfax (Tunisia); Ghorbel, M.; Drira, M. [Service ORL de Sfax (Tunisia); Abid, M. [Centre Hospitalier Universitaire Hedi-CHAKER, Service d' endocrinologie du Sfax (Tunisia)

    2005-05-15

    Purpose. - 1/ To evaluate the incidence of hypothyroidism following radiotherapy in the management of breast and nasopharyngeal carcinomas, 2/ to define the role of a systematic post therapeutic screening. Patients and methods. - From January 1996 through March 2001 a systematic evaluation of the clinical and the biological thyroid function was performed on a cohort of 84 patients that received supraclavicular irradiation. Selected patients had either a mammary (37 cases) or a nasopharyngeal (47 cases) carcinoma. Initial work up included thyroid inspection and palpation, and biological tests: serum FT4 and TSH levels, radio-immuno-chemistry, completed by dynamic thyroid stimulation, using TRH, in case of border line low T4 or isolated high TSH levels. Tests were repeated every three months the first year, and then every six months. Replacement therapy with L Thyroxine was administered in case of hypothyroidism. Results. - All selected patients had a normal function initially. With a mean two years follow up (1-5 years), 24 patients (29%) experienced hypothyroidism, half of whom (13 cases) being purely biological. Five patients (11%), with a nasopharyngeal carcinoma, presented also with associated pituitary failure. Clinical symptoms were minor or mild in all cases. Hypothyroidism was detected at a mean 21 months follow up. In 2 patients, hypothyroidism disappeared spontaneously within 6 months. Possible predictive factors were evaluated: age of the time of radiation, gender, percentage of irradiated thyroid, total dose, dose per fraction, tumour type and chemotherapy. Only age appeared significantly correlated with thyroid dysfunction (range: 10-30 years, P = 0.002). Conclusion. - Hypothyroidism is a frequent and certainly underestimated complication following radiotherapy of the neck. In such patients, a systematic clinical and biological evaluation every three months the first year, and then every six months until five years is recommended. (authors)

  13. Immunothérapie adoptive pour le traitement des infections à Adénovirus réfractaires après allogreffes de Cellules Souches Hématopoïétiques : de la recherche fondamentale à la recherche clinique

    OpenAIRE

    Qian , Chongsheng

    2017-01-01

    Hematopoietic stem cell transplantation (HSCT) is one of the only curative treatments for benign or malignant hematological diseases and primary immune deficiencies. However, viral infections and graft-versus-host disease (GVHD) are among the most frequent complications after HSCT associated with high morbidity and mortality. Viral infections often occur in the absence of specific immune reconstitution in the context of immunosuppression related to GVHD itself or to the prophylaxis or treatme...

  14. Simplified study for the proposed APR1400 condenser performance based on EL-DABAA SITE, EGYPT, with respect to BNPP and SHIN KORI NPP

    Energy Technology Data Exchange (ETDEWEB)

    Abdoelatef, M. Gomaa; Rezk, Osama; Lee, YonKwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    • Perception of nuclear power as a convenient, economically competitive and viable source of energy which, if introduced in the country, would not only complement the traditional energy sources, but would also promote technological development and serve as an incentive for social and economic progress. In this paper we will introduce APR-1400 as the most likely selected reactor type for 1st Egyptian Nuclear Power Plant. Then we will study the optimized APR-1400 condenser performance based on El-Dabaa site conditions. As the climate conditions, especially the seawater temperatures (intake for the cooling system) having a direct effects on the condenser performance and the overall NPP Efficiency, we studied the seawater temperature change based on EL-Dabaa site conditions and it's feedback on the proposed APR-1400 condenser performance and the NPP efficiency. All of the calculations and analysis had been executed by using KINGS NPA by applying EL-Dabaa seawater temperature variations for the 2 types of APR-1400 Condensers (Shinkori, south Korea and Barakah, UAE), and the main findings were as follow: For the APR-1400 condensers (Shinkori and Barakah) performance • The average difference all over the year for saturation temperature, cooling water outlet temperature, and condenser pressure are 0.135 .deg. C, .05785 .deg. C, and 0.3948 mHgA respectively. This shows that the Barakah condenser performance is not significantly better than the shinkori condenser performance based on EL-Dabaa Conditions, especially if we considered the cost difference between the two condensers designs. For APR-1400 NPPs (Shinkori and Barakah) net efficiency • The average difference all over the year for the power productions and net efficiency are 1.4791 MWe and .00037 %, respectively.

  15. The subtilisin-like protease AprV2 is required for virulence and uses a novel disulphide-tethered exosite to bind substrates.

    Directory of Open Access Journals (Sweden)

    Ruth M Kennan

    Full Text Available Many bacterial pathogens produce extracellular proteases that degrade the extracellular matrix of the host and therefore are involved in disease pathogenesis. Dichelobacter nodosus is the causative agent of ovine footrot, a highly contagious disease that is characterized by the separation of the hoof from the underlying tissue. D. nodosus secretes three subtilisin-like proteases whose analysis forms the basis of diagnostic tests that differentiate between virulent and benign strains and have been postulated to play a role in virulence. We have constructed protease mutants of D. nodosus; their analysis in a sheep virulence model revealed that one of these enzymes, AprV2, was required for virulence. These studies challenge the previous hypothesis that the elastase activity of AprV2 is important for disease progression, since aprV2 mutants were virulent when complemented with aprB2, which encodes a variant that has impaired elastase activity. We have determined the crystal structures of both AprV2 and AprB2 and characterized the biological activity of these enzymes. These data reveal that an unusual extended disulphide-tethered loop functions as an exosite, mediating effective enzyme-substrate interactions. The disulphide bond and Tyr92, which was located at the exposed end of the loop, were functionally important. Bioinformatic analyses suggested that other pathogenic bacteria may have proteases that utilize a similar mechanism. In conclusion, we have used an integrated multidisciplinary combination of bacterial genetics, whole animal virulence trials in the original host, biochemical studies, and comprehensive analysis of crystal structures to provide the first definitive evidence that the extracellular secreted proteases produced by D. nodosus are required for virulence and to elucidate the molecular mechanism by which these proteases bind to their natural substrates. We postulate that this exosite mechanism may be used by proteases produced by

  16. Variability of nursing care by APR-DRG and by severity of illness in a sample of nine Belgian hospitals.

    Science.gov (United States)

    Pirson, Magali; Delo, Caroline; Di Pierdomenico, Lionel; Laport, Nancy; Biloque, Veronique; Leclercq, Pol

    2013-10-10

    As soon as Diagnosis related Groups (DRG) were introduced in many hospital financing systems, most nursing research revealed that DRG were not very homogeneous with regard to nursing care. However, few studies are based on All Patient refined Diagnosis related Groups (APR-DRGs) and few of them use recent data. Objectives of this study are: (1) to evaluate if nursing activity is homogeneous by APR-DRG and by severity of illness (SOI) (2) to evaluate the outlier's rate associated with the nursing activity and (3) to compare nursing cost homogeneity per DRG and SOI. Study done in 9 Belgian hospitals on a selection of APR-DRG with more than 30 patients (7 638 inpatient stays). The evaluation of the homogeneity is based on coefficients of variation (CV). The 75th percentile + 1.5 × inter-quartile range was used to select high outliers. 25th percentile -1.5 × inter-quartile range was used to select low outliers. Nursing costs per ward were distributed on inpatient stays of each ward following two techniques (the LOS vs. the number of nursing care minutes per stay). The homogeneity of LOS by DRG and by SOI is relatively good (CV: 0.56). The homogeneity of the nursing activity by DRG is less good (CVs between 0.36 and 1.54) and is influenced by nursing activity outliers (high outliers' rate: 5.19%, low outliers' rate: 0.14%). The outlier's rate varies according to the studied variable. The high outliers' rate is higher for nursing activity than for LOS. The homogeneity of nursing costs is higher when costs are based on the LOS of patients than when based on minutes of nursing care (CVs between 0.26 and 1.46 for nursing costs based on LOS and between 0.49 and 2.04 for nursing costs based on minutes of nursing care). It is essential that the calculation of nursing cost by stay and by DRG for hospital financing purposes was based on nursing activity data, that more reflect resources used in wards, and not on LOS data. The only way to obtain this information is

  17. Fatou, Julia, Montel le grand prix des sciences mathématiques de 1918, et après

    CERN Document Server

    Audin, Michèle

    2009-01-01

    Comment Fatou et Julia ont inventA(c) ce que la (TM)on appelle aujourda (TM)hui les ensembles de Julia, avant, pendant et aprA]s la premiA]re guerre mondiale? La (TM)histoire est racontA(c)e, avec ses mathA(c)matiques, ses conflits, ses personnalitA(c)s. Elle est traitA(c)e A partir de sources nouvelles, et avec rigueur. On pourra sa (TM)y initier A la (TM)itA(c)ration des fractions rationnelles et A la dynamique complexe (ensembles de Julia, de Mandelbrot, ensembles-limites). Qui A(c)taient Pierre Fatou, Gaston Julia, Paul Montel? On y trouvera en particulier des informations sur un mathA(c)m

  18. O après-coup e a reconsolidação da memória

    Directory of Open Access Journals (Sweden)

    Graziele Luiza Barizon Scopel Gerbasi

    2015-04-01

    Full Text Available Em diferentes áreas do conhecimento é reconhecido que a memória está sujeita a transformações ao longo do tempo. Partindo desse pressuposto, o objetivo do presente estudo é apresentar uma discussão compreendendo a ideia de que nossas recordações são suscetíveis a transformações e a concepção de après-coup. Há o delineamento de algumas ideias acerca da temporalidade em Psicanálise e do mecanismo de reconsolidação da memória segundo as Neurociências. Utilizando-se tais conceitos, evidenciou-se a viabilidade de se pensar uma interlocução entre a Psicanálise e as Neurociências.

  19. L’amitié dans la relation ethnographique. Traitement de l’individu et rapport à l’autre dans les groupes locaux de Hijra (Delhi, Inde

    Directory of Open Access Journals (Sweden)

    Emmanuelle Novello

    2009-03-01

    Full Text Available L’amitié dans la relation ethnographique. Traitement de l’individu et rapport à l’autre dans les groupes locaux de Hijra (Delhi, Inde. « Tu es mon amie. Tu es la seule qui me comprenne. » Ces mots, toujours les mêmes, sont revenus sans cesse lors de l’enquête ethnographique que j’ai menée auprès des Hijra de Delhi. Les Hijra forment une catégorie sociale panindienne. Elles sont nées biologiquement hommes ou hermaphrodites, s’habillent et se parent continuellement comme des femmes et, parfois, sont émasculées. Les ethnologues parlent parfois de leur relation avec leurs informateurs en terme d’amitié sans que cette relation soit exprimée et pensée comme telle par ces derniers. Qu’en est-il lorsque la société étudiée désigne l’ethnologue en tant qu’ami et lorsque cette désignation transforme la nature des rapports qu’elle entretenait auparavant avec lui ? L’étude de l’amitié que les Hijra me proposèrent fournira, en premier lieu, un exemple de la façon dont l’ethnologue peut se trouver engagé dans ce rapport affectif. Il s’agira de qualifier cette relation ethnographique par la description du processus d’évolution de mon rôle d’une part, et par l’examen des comportements et des pratiques qui la sanctionnent et qui y sont engagés d’autre part. Cette réflexion sur les représentations et les valeurs auxquelles mes interlocutrices faisaient référence en me conférant la place d’amie, informera en second lieu sur le traitement de l’individu et de l’altérité prévalant dans la catégorie sociale « Hijra ».Friendship in ethnographical relations. Treatment of the individual and relation to the other in local groups of Hijra (Delhi, India. “You are my friend. You are the only person who understands me.” These words, always the same, were endlessly repeated during my ethnographical survey of the Hijra of Delhi. The Hijra form a pan-Indian social category. Born

  20. Data processing in gamma spectrometry. Application to the decay schemes study; Traitement des informations en spectrometrie gamma application a l'etude de schemas de desintegration

    Energy Technology Data Exchange (ETDEWEB)

    Boulanger, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires, departement d' electronique generale, service d' instrumentation nucleaire

    1968-06-01

    The purpose of this thesis is the processing of the data issued from a gamma spectrometer, and its applications to the decay schemes study. The mathematical analysis of the full energy peaks, in connection with the very good resolution of semi-conductor detectors, leads to a very accurate determination of the energies. The resolution of complex spectra by the least squares method, completed by a spectra generating process, allows the calculation of branching ratios. Then, the handling of the two dimensional experiments permits the coincidence exam. For each of these methods, the calculation principle, then the systematics tests realized in order to prove their validity and to determine their application ranges as well as some experimental results appropriate to illustrate their possibilities, are presented. The energies of some nuclides, frequently used as standards have been thus measured and the decay schemes of {sup 134}Cs and {sup 110m}Ag determined precisely. (author) [French] Cette these est consacree aux methodes de traitement des informations issues d'un spectrometre {gamma}, et a leur application a l'etude des schemas de desintegration: l'analyse mathematique des pics d'absorption totale, conjuguee avec l'excellent pouvoir de resolution des detecteurs semi-conducteurs, conduit a une determination tres precise des energies. La decomposition des spectres complexes par la methode des moindres carres, completee par un procede de generation de spectres, autorise le calcul des rapports de branchement. Enfin le depouillement des experiences biparametriques permet l'examen des coincidences. Pour chacune de ces methodes, on expose le principe des calculs et les essais systematiques effectues afin d'eprouver leur validite et de definir leurs domaines d'application, ainsi que quelques resultats experimentaux propres a illustrer leurs possibilites. Les energies de quelques isotopes utilises couramment comme etalons ont ainsi ete mesurees, et les schemas de

  1. Emergency measures and treatment in the event of accidental aver exposure to radiation or of radioactive contamination; Mesures d'urgence et traitement en cas de surexposition accidentelle aux rayonnements ou en cas de contamination radioactive

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    In the first part the author presents an overall view of emergency measures to be applied in the case of internal or external radioactive contamination. He states in particular, in these two cases, the methods by which it is possible to eliminate the contaminating radioactive substances from the organism. The author then considers the therapeutic methods to be adopted in the case of an accident of overexposure to radiation, distinguishing between the case of a partial irradiation and that of an acute total irradiation. There will be essentially three methods used depending on the physical measures carried out (irradiation, conditions, estimation of the dose received) and of the clinical data collected: particular treatments, treatment for helping the organism during its return to normal activity, temporary or permanent replacement of the organs affected. (author) [French] L'auteur presente, en une premiere partie, une vue d'ensemble des mesures d'urgence a appliquer en cas de contamination radioactive externe ou interne. Il fait etat en particulier, dans ces deux cas, des methodes permettant de debarrasser l'organisme des substances radioactives contaminantes. L'auteur envisage, ensuite, la therapeutique a adopter lors d'un accident de surexposition aux rayonnements, distinguant le cas d'une irradiation partielle et celui d'une irradiation totale aigue. Trois traitements seront essentiellement mis en oeuvre en fonction des mesures physiques effectuees (conditions d'irradiation, evaluation de la dose recue) et des donnees cliniques recueillies: traitements specifiques, traitement de soutien de l'organisme preparant la restauration, suppleance temporaire ou definitive d'organes defaillants. (auteur)

  2. Emergency measures and treatment in the event of accidental aver exposure to radiation or of radioactive contamination; Mesures d'urgence et traitement en cas de surexposition accidentelle aux rayonnements ou en cas de contamination radioactive

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    In the first part the author presents an overall view of emergency measures to be applied in the case of internal or external radioactive contamination. He states in particular, in these two cases, the methods by which it is possible to eliminate the contaminating radioactive substances from the organism. The author then considers the therapeutic methods to be adopted in the case of an accident of overexposure to radiation, distinguishing between the case of a partial irradiation and that of an acute total irradiation. There will be essentially three methods used depending on the physical measures carried out (irradiation, conditions, estimation of the dose received) and of the clinical data collected: particular treatments, treatment for helping the organism during its return to normal activity, temporary or permanent replacement of the organs affected. (author) [French] L'auteur presente, en une premiere partie, une vue d'ensemble des mesures d'urgence a appliquer en cas de contamination radioactive externe ou interne. Il fait etat en particulier, dans ces deux cas, des methodes permettant de debarrasser l'organisme des substances radioactives contaminantes. L'auteur envisage, ensuite, la therapeutique a adopter lors d'un accident de surexposition aux rayonnements, distinguant le cas d'une irradiation partielle et celui d'une irradiation totale aigue. Trois traitements seront essentiellement mis en oeuvre en fonction des mesures physiques effectuees (conditions d'irradiation, evaluation de la dose recue) et des donnees cliniques recueillies: traitements specifiques, traitement de soutien de l'organisme preparant la restauration, suppleance temporaire ou definitive d'organes defaillants. (auteur)

  3. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    Energy Technology Data Exchange (ETDEWEB)

    Ualikhan Zhiyenbayev [KAIST, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether.

  4. Veselības aprūpes iemaņas pusaudžiem bērnu namā

    OpenAIRE

    Zūpe, Daira

    2008-01-01

    Pētniecības darbā „Veselības aprūpes iemaņas pusaudžiem bērnu namā” autore Daira Zūpe izpēta un analizē vienu no bērnu namu aktuālajām problēmām veselības profilakses veicināšanā – veselības aprūpes iemaņu attīstīšanu. Pētījumā uzmanība pievērsta māsas lomai bērnu nama pusaudžu veselības aprūpes procesā, kur akcentēta veselības aprūpes pamatiemaņu nozīme veselības vecināšanā - fiziskās aktivitātes, ēšanas paradumi, kaitīgie ieradumi un higiēnas iemaņas. Pētniecības darba zinātniskā vadītā...

  5. The role of the Northern Sea Route in the development of floating nuclear power sources and prospects of cooperation with the EU countries, BRICS and APR

    International Nuclear Information System (INIS)

    Shadrin, A.P.; Ignat'ev, V.S.; Ivanov, V.A.

    2015-01-01

    The report discusses the construction of a transportable nuclear reactor, which will become the basis for the development of floating nuclear power sources on the Northern Sea Route. In this regard, the prospects of cooperation with the countries of the European Union, BRICS and APR [ru

  6. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    International Nuclear Information System (INIS)

    Ualikhan Zhiyenbayev; Chung, Dae Wook

    2015-01-01

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether

  7. Aprūpes īpatnības bērniem ar Dauna sindromu stacionārā

    OpenAIRE

    Lūse, Ērika

    2015-01-01

    Bakalaura darba tēma – Aprūpes īpatnības bērniem ar Dauna sindromu stacionārā. Tēmas aktualitāte pievērst uzmanību bērna ar Dauna sindroma aprūpei, kā arī mazināt stereotipus par šiem bērniem. Darba mērķis ir izpētīt Dauna sindromu un māsas lomu šo bērnu aprūpē, kā arī aprūpes īpatnības. Pētniecības uzdevumi ir veikt zinātniskās literatūras analīzi, pētījuma atbilstošas māszinību teorijas atlasi, izstrādāt anketu, veikt pilot pētījumu, iegūto datu apkopošanu, analīze un secinājumu veikšana. I...

  8. Les politiques d’employabilité en Belgique : traitement clinique des chômeurs et traitement statistique du chômage The Politics of Employability in Belgium : Clinical Treatment of the Unemployed and Statistical Treatment of Unemployment

    Directory of Open Access Journals (Sweden)

    Jean-François Orianne

    2011-03-01

    Full Text Available Cet article interroge la mise en œuvre et le suivi des politiques européennes d’employabilité en Belgique à la lumière de la sociologie de Norbert Elias, en reliant les dimensions sociogénétiques et psychogénétiques de la construction européenne. Le traitement clinique des chômeurs, qui repose principalement sur la construction professionnelle de troubles de l’employabilité, contribue à l’intériorisation de normes à grande échelle, à la socialisation de la population active au marché du travail et renforce la concurrence entre les actifs occupés et les actifs inoccupés (principale condition de stabilité de la monnaie unique. Parallèlement, le traitement statistique du chômage, qui consiste en un jeu rationnel entre États (et Régions de maximisation des indicateurs de résultats, renforce la compétition territoriale pour attirer les investisseurs et encadre, légitime, dynamise ce mouvement incertain d’harmonisation ou d’intégration des systèmes de protection sociale en Europe.This article investigates the setting up and follow-up of European employment politics in Belgium, in light of the sociology of Norbert Elias, in blending the socio-genetic and psycho-genetic dimensions of European construction. The clinical treatment of the unemployed, principally based on the professional construction of employability troubles, contributes to the internalization of standards on a vast scale, to the socialization of the active population on the job market and reinforcing competition between occupied actives and unoccupied actives (a principal condition for the stability of a unique currency. At the same time, the statistical treatment of unemployment, consisting in a deliberate game between States (and Regions of maximization of result indicators, reinforces a territorial competition aimed at attracting investors as well as organizing, legitimating and dynamizing the unsteady movement toward harmonization or

  9. Pharmacothérapie de la dépression chez les aînés

    Science.gov (United States)

    Frank, Christopher

    2014-01-01

    Résumé Objectif Discuter du traitement pharmacologique de la dépression chez les personnes âgées, y compris le choix des antidépresseurs, le titrage de la dose, la surveillance de la réponse et des effets secondaires et le traitement des cas réfractaires. Sources des données Les lignes directrices de 2006 de la Canadian Coalition for Seniors’ Mental Health sur l’évaluation et le traitement de la dépression ont servi comme source principale. Pour recenser les articles publiés après les lignes directrices, on a procédé à une recherche documentaire dans MEDLINE de 2007 à 2012 à l’aide des expressions en anglais depression, treatment, drug therapy et elderly. Message principal Le but du traitement devrait être la rémission des symptômes. L’amélioration des symptômes peut être surveillée en fonction des objectifs du patient qu’on a identifiés ou en se servant d’outils cliniques comme le Patient Health Questionnaire–9. On devrait envisager le traitement en 3 étapes: l’étape du traitement aigu pour obtenir la rémission des symptômes, une étape de continuation pour prévenir la récurrence d’un même épisode de la maladie (rechute) et une étape de maintien (prophylaxie) pour prévenir de futurs épisodes (récurrence). Le dosage initial devrait être la moitié de la dose de départ habituelle chez l’adulte et il devrait être titré régulièrement jusqu’à ce que le patient réponde, jusqu’à ce que la dose maximale soit atteinte ou encore que les effets secondaires en limitent l’augmentation. Parmi les effets secondaires fréquents, on peut mentionner les chutes, la nausée, les étourdissements, les céphalées et, moins communément, l’hyponatrémie et des changements dans l’intervalle QT. Des stratégies pour changer ou augmenter les antidépresseurs sont présentées. Les patients plus âgés devraient être traités pendant au moins un an à compter de l’observation d’une amélioration clinique et

  10. Study of the secondary electron emission during bombardment of metal targets by positive D{sup +} and D{sub 2}{sup +} ions (1960); Etude de l'emission secondaire d'electrons au cours du bombardement de cibles metalliques par des ions positifs D{sup +} et D{sub 2}{sup +} (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Leroy, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Prelec, K [Institut Rudjer Boskovic, Zagreb (Croatia)

    1960-07-01

    The secondary electron yield {gamma}-bar due to primary positive ions D{sup +} and D{sup +}{sub 2} has been measured in the 70 keV to 300 keV ion energy range. Several metallic targets have been used. The variation of this yield with the angle of incidence is proportional to sec {theta} where {theta} is the angle between the beam of primary ions and the normal to the target surface. The values {gamma}-bar decrease for increasing energy ions. At a given energy all the targets tried gave approximately the same electron yield. (author) [French] Le facteur d'emission secondaire a ete mesure pour des ions positifs D{sup +} et D{sup +}{sub 2} ayant une energie comprise entre 70 keV et 300 keV, sur differentes cibles metalliques. La variation de ce facteur avec l'angle d'incidence suit une loi de la forme {gamma}{sub 0} sec {theta}, {theta} etant l'angle entre le faisceau et la normale a la cible. Les valeurs de {gamma}-bar trouvees decroissent lorsque l'energie des ions incidents augmente, mais sont assez voisines les unes des autres, a une energie donnee, pour les differentes cibles essayees. (auteur)

  11. Thermodynamic Aspects of Supercritical Fluids Processing: Applications of Polymers and Wastes Treatment Aspects thermodynamiques des procédés mettant en oeuvre des fluides supercritiques : applications aux traitements des polymères et des déchets

    Directory of Open Access Journals (Sweden)

    Beslin P.

    2006-11-01

    , fibres et substrats (produits pharmaceutiques, explosifs, revêtements, pour le séchage des matériaux (gels. Cet article présente les propriétés physicochimiques exceptionnelles des fluides supercritiques en rapport avec leurs applications en ingénierie. Après un bref rappel des concepts fondamentaux relatifs au comportement critique des fluides purs, nous développons d'une manière plus détaillée les propriétés physicochimiques ajustables des fluides dans le domaine supercritique. La deuxième partie de l'article décrit les applications en ingénierie des fluides supercritiques relatives aux réactions chimiques et au traitement des polymères. Chaque présentation d'application est divisée en deux parties : la première rappelle les concepts de base et le contexte général ainsi que les propriétés physicochimiques, la seconde développe les applications en ingénierie se rapportant au domaine concerné.

  12. Development of the APR1400 model for countercurrent natural circulation in hot leg and steam generator under station blackout

    International Nuclear Information System (INIS)

    Park, Sang Gil; Kim, Han Chul

    2012-01-01

    In order to analyze severe accident phenomena, Korea Institute of Nuclear Safety (KINS) made a MELCOR model for APR1400 to examine natural circulation and creep rupture failure in the Reactor Coolant System (RCS) under station blackout (SBO). In this study, we are trying to advance the former model to describe natural circulation more accurately. After Fukushima accident, the concerns of severe accident management, assuring the heat removal capability, has risen for the case when the SBO is happened and there are no more electric powers to cool down decay heat. Under SBO there are three kinds of natural circulation which can delay the core heatup. One is in vessel natural circulation in the upper plenum of reactor vessel and the second is countercurrent natural circulation in hot leg through steam generator tubes and the last is full loop natural circulation when the reactor coolant pump loop seal is cleared and reactor coolant pump sealing is damaged by high temperature and high pressure. Among them this study focuses on the countercurrent natural circulation model using MELCOR1.8.6

  13. A study on the hydrogen behavior and its mitigation in the APR1400 containment during a severe accident

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Hong, Seong Wan; Park, Rae Joon; Kim, Sang Baik

    2005-02-01

    During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by the active reaction of fuel-cladding and steam in the reactor pressure vessel and released with steam into the containment. In this study, the analysis of the hydrogen and steam behavior during selected severe accidents in the APR1400 containment has been conducted by using the GASFLOW code. For the SBLOCA, hydrogen was accumulated in the containment dome region quickly when only PARSs were used. When the igniters were turned on, a standing flame was formed around a coolant pump and burnt most of the hydrogen blown-out. For the TLOFW accident, the flap-type pressure damper installed at the IRWST vents strongly affected the flow structure of the hydrogen. And by the steam-rich and oxygen starvation conditions in the IRWST, DDT is not likely to occur. For the SBO accident, dry hydrogen was release in the IRWST by the assumption of full condensation of the released steam in the IRWST water. In this case, the possibility of flame acceleration is high in the IRWST and annular compartment. In this study two design modifications were proposed in view of the hydrogen mitigation strategy and their effectiveness was evaluated by the GASFLOW analysis

  14. Consideration on hydrogen explosion scenario in APR 1400 containment building during small breakup loss of coolant accident

    Energy Technology Data Exchange (ETDEWEB)

    Park, Kweonha, E-mail: khpark@kmou.ac.kr [Division of Mechanical & Energy Systems Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of); Khor, Chong Lee, E-mail: itachi_829@hotmail.com [Department of Mechanical Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of)

    2015-11-15

    Highlights: • Hydrogen behavior in the containment building of APR1400 nuclear plant up to 15 h after the failure happened. • The risk of hydrogen explosion largely depends on the combination of air, hydrogen and steam in the containment. • Hydrogen explosion risk at different locations in the containment was analyzed. - Abstract: This paper describes the analytical result of the potential risk of hydrogen gas up to 15 h after the failure takes place. The major cause of the disaster occurred in Fukushima Daiichi nuclear reactor was the detonation of accumulated hydrogen in the containment by highly increased reactor core temperatures after the failure of the emergency cooling system. The hydrogen risk should be considered in severe accident strategies in current and future NPPs. A hydrogen explosion scenario is proposed. Hydrogen is accumulated on top of the dome during the hydrogen release period. At this point, there are no risk of explosion due to the steam that resides in upper part of the dome. As the hydrogen concentration increase, substantial amount of steams are released. Subsequently, hydrogen is forced into the lower part of the building with high air density—small explosion and dormant steam condensation phase are possible. The light hydrogen rises up slowly with air, gathering on top of the building with high air density. Massive hydrogen explosion is anticipated upon ignition at this stage.

  15. The fifteenth period report on the cooperative utilization of the AVF cyclotron at Osaka University RCNP (Dec 1982 - Apr 1983)

    International Nuclear Information System (INIS)

    1984-01-01

    The AVF cyclotron at the RCNP (Research Center for Nuclear Physics) of Osaka University has been cooperatively used by various researchers of Japanese universities or colleges. This collective report covers papers concerning various studies performed at the AVF during Dec 1982 to Apr 1983. Some of the titles of these papers are as follows : Elastic scattering of 56 MeV polarized deuterons from 12 C and 40 Ca ; Pionic three-nucleon capture reactions ; Measurement on branching ratios of short-lived beta emitter 23 Mg and its hyperfine interactions ; Half-life and branching ratios of short-lived beta emitter 13 O ; 7 Li excitation of the giant resonances in 208 Pb ; Measurements of spin polarization of residual nuclei after light particle emission in heavy ion reactions ; Target dependence of the sequential alpha decay through the narrow resonances of 20 Ne ; Analyzing power of neutron continuum spectra for the 93 Nb (p,nx) reaction and a simple one step OWBA analysis ; Energy dependence of the reaction mechanism for the 3 He and alpha induced reactions ; Medium energy gamma rays following radiative capture of polarized protons on light nuclei. (Aoki, K.)

  16. Air clearing pressure oscillation produced in a quenching tank by a prototype unit cell sparger of the APR1400

    International Nuclear Information System (INIS)

    Cho, Seok; Song, Chul-Hwa; Park, Choon-Kyong; Kim, Hwan-Yeol; Baek, Won-Pil

    2008-01-01

    KAERI has performed a series of experiments to investigate the performance of a prototype sparger for the APR1400 in view of a dynamic load oscillation with a variation of the test conditions such as a discharged air mass, a submergence of the sparger, the valve opening time, and the pool temperature during an air clearing phase. The air mass and pool temperature are in the range of 0.8-1.5 kg and 20-90 o C, respectively. The valve opening time can be adjusted within the range of 0.6-1.8 s. The maximum positive pressure amplitude, which is observed at the bottom of the quenching tank, is increased with the maximum header pressure of the sparger. The valve opening time has a considerable effect on the maximum amplitude. As the opening time decreases, the maximum amplitude at the tank wall is increased. Air mass and pool temperature, however, have a weak effect on the maximum amplitude. Oscillation frequency is decreased with an increase of the air mass in the range of 2.5-4.5 Hz

  17. Data processing in gamma spectrometry. Application to the decay schemes study; Traitement des informations en spectrometrie gamma application a l'etude de schemas de desintegration

    Energy Technology Data Exchange (ETDEWEB)

    Boulanger, J.P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires, departement d' electronique generale, service d' instrumentation nucleaire

    1968-06-01

    The purpose of this thesis is the processing of the data issued from a gamma spectrometer, and its applications to the decay schemes study. The mathematical analysis of the full energy peaks, in connection with the very good resolution of semi-conductor detectors, leads to a very accurate determination of the energies. The resolution of complex spectra by the least squares method, completed by a spectra generating process, allows the calculation of branching ratios. Then, the handling of the two dimensional experiments permits the coincidence exam. For each of these methods, the calculation principle, then the systematics tests realized in order to prove their validity and to determine their application ranges as well as some experimental results appropriate to illustrate their possibilities, are presented. The energies of some nuclides, frequently used as standards have been thus measured and the decay schemes of {sup 134}Cs and {sup 110m}Ag determined precisely. (author) [French] Cette these est consacree aux methodes de traitement des informations issues d'un spectrometre {gamma}, et a leur application a l'etude des schemas de desintegration: l'analyse mathematique des pics d'absorption totale, conjuguee avec l'excellent pouvoir de resolution des detecteurs semi-conducteurs, conduit a une determination tres precise des energies. La decomposition des spectres complexes par la methode des moindres carres, completee par un procede de generation de spectres, autorise le calcul des rapports de branchement. Enfin le depouillement des experiences biparametriques permet l'examen des coincidences. Pour chacune de ces methodes, on expose le principe des calculs et les essais systematiques effectues afin d'eprouver leur validite et de definir leurs domaines d'application, ainsi que quelques resultats experimentaux propres a illustrer leurs possibilites. Les energies de quelques isotopes utilises couramment comme etalons ont ainsi ete

  18. A combination of p53-activating APR-246 and phosphatidylserine-targeting antibody potently inhibits tumor development in hormone-dependent mutant p53-expressing breast cancer xenografts

    Directory of Open Access Journals (Sweden)

    Liang Y

    2018-03-01

    Full Text Available Yayun Liang,1 Benford Mafuvadze,1 Cynthia Besch-Williford,2 Salman M Hyder1 1Deparment of Biomedical Sciences and Dalton Cardiovascular Research Center, Columbia, MO, USA; 2IDEXX BioResearch, Columbia, MO, USA Background: Between 30 and 40% of human breast cancers express a defective tumor suppressor p53 gene. Wild-type p53 tumor suppressor protein promotes cell-cycle arrest and apoptosis and inhibits vascular endothelial growth factor–dependent angiogenesis, whereas mutant p53 protein (mtp53 lacks these functions, resulting in tumor cell survival and metastasis. Restoration of p53 function is therefore a promising drug-targeted strategy for combating mtp53-expressing breast cancer. Methods: In this study, we sought to determine whether administration of APR-246, a small-molecule drug that restores p53 function, in combination with 2aG4, an antibody that targets phosphatidylserine residues on tumor blood vessels and disrupts tumor vasculature, effectively inhibits advanced hormone-dependent breast cancer tumor growth. Results: APR-246 reduced cell viability in mtp53-expressing BT-474 and T47-D human breast cancer cells in vitro, and significantly induced apoptosis in a dose-dependent manner. However, APR-246 did not reduce cell viability in MCF-7 breast cancer cells, which express wild-type p53. We next examined APR-246’s anti-tumor effects in vivo using BT-474 and T47-D tumor xenografts established in female nude mice. Tumor-bearing mice were treated with APR-246 and/or 2aG4 and tumor volume followed over time. Tumor growth was more effectively suppressed by combination treatment than by either agent alone, and combination therapy completely eradicated some tumors. Immunohistochemistry analysis of tumor tissue sections demonstrated that combination therapy more effectively induced apoptosis and reduced cell proliferation in tumor xenografts than either agent alone. Importantly, combination therapy dramatically reduced the density of blood

  19. Research

    African Journals Online (AJOL)

    raoul

    21 janv. 2012 ... les endocrinopathies et aussi les effets secondaires des antihypertenseurs [6,7]. Les recommandations de la JNC VII [8] ... de Lomé, ayant concerné 394 patients hypertendus en traitement régulier (médicaments antihypertenseurs + mesures hygiéno-diététiques) depuis au moins 1 mois et bien observants.

  20. Complex regulation of AprA metalloprotease in Pseudomonas fluorescens M114: evidence for the involvement of iron, the ECF sigma factor, PbrA and pseudobactin M114 siderophore.

    Science.gov (United States)

    Maunsell, Bláithín; Adams, Claire; O'Gara, Fergal

    2006-01-01

    In the soil bacterium Pseudomonas fluorescens M114, extracellular proteolytic activity and fluorescent siderophore (pseudobactin M114) production were previously shown to be co-ordinately negatively regulated in response to environmental iron levels. An iron-starvation extracytoplasmic function sigma factor, PbrA, required for the transcription of siderophore biosynthetic genes, was also implicated in M114 protease regulation. The current study centred on the characterization and genetic regulation of the gene(s) responsible for protease production in M114. A serralysin-type metalloprotease gene, aprA, was identified and found to encode the major, if not only, extracellular protease produced by this strain. The expression of aprA and its protein product were found to be subject to complex regulation. Transcription analysis confirmed that PbrA was required for full aprA transcription under low iron conditions, while the ferric uptake regulator, Fur, was implicated in aprA repression under high iron conditions. Interestingly, the iron regulation of AprA was dependent on culture conditions, with PbrA-independent AprA-mediated proteolytic activity observed on skim milk agar supplemented with yeast extract, when supplied with iron or purified pseudobactin M114. These effects were not observed on skim milk agar without yeast extract. PbrA-independent aprA expression was also observed from a truncated transcriptional fusion when grown in sucrose asparagine tryptone broth supplied with iron or purified pseudobactin M114. Thus, experimental evidence suggested that iron mediated its effects via transcriptional activation by PbrA under low iron conditions, while an as-yet-unidentified sigma factor(s) may be required for the PbrA-independent aprA expression and AprA proteolytic activity induced by siderophore and iron.

  1. La prévention et le traitement des infections bactériennes chez les enfants aspléniques ou hypospléniques

    Science.gov (United States)

    1999-01-01

    L’asplénie, qu’elle soit fonctionnelle ou anatomique, s’associe à un accroissement du risque d’infection potentiellement fatale ou constituant un danger de septicémie postsplénectomie (SPS). En raison du risque accru de bactériémie par des bactéries encapsulées chez les enfants aspléniques, la vaccination visant à prévenir une infection au Streptococcus pneumoniae, à l’Haemophilus influenzae de type b (Hib) et au Neiserria meningitidis est recommandée. Malgré la prévalence croissante de S pneumoniae pénicillinorésistant, on recommande aussi l’usage de pénicilline prophylactique chez les enfants aspléniques de moins de cinq ans, et pendant au moins un an après une splénectomie. La poursuite de la prophylaxie antibiotique après cette période dépend de la situation clinique de chaque enfant et de la prévalence de S pneumoniae pénicillinorésistant au sein de la collectivité. Lorsque des enfants aspléniques font de la fièvre ou présentent des symptômes non spécifiques, ils devraient faire l’objet d’une évaluation immédiate. Si on présume la présence de septicémie bactérienne, il faut procéder à une analyse du sang et des autres liquides organiques pertinents et entreprendre sur-le-champ une antibiothérapie à large spectre par voie parentérale, laquelle doit agir également contre les souches de S pneumoniae présentes dans la collectivité. Chez les enfants aspléniques souffrant d’une septicémie foudroyante à S pneumoniae, le taux de mortalité est élevé, malgré l’utilisation rapide d’une antibiothérapie convenable, d’où l’importance des mesures préventives.

  2. L’Allemagne : un non – lieu pour les exiles judéo-allemands après 1945 ?

    OpenAIRE

    Bohnekamp, Dorothea

    2017-01-01

    L’omniprésence de l’Allemagne dans les productions littéraires des exilés judéo-allemands en France après 1945 pose tout d’abord la question des différentes représentations de ce pays chez les rescapés. Le nombre important de métaphores spatiales interroge plus particulièrement le rôle de l’espace, matériel/urbain ou symbolique, dans la mémoire des émigrants et dans la reconstruction d’une Heimat souvent imaginaire. Après la guerre, cet attachement souvent ambivalent à l’Allemagne comme patri...

  3. Benjamin Crémieux, Inquiétude et reconstruction. Essai sur la littérature d’après-guerre

    OpenAIRE

    Brangé, Mireille

    2016-01-01

    Après xxe siècle (1924) en 2010 reparaît ce recueil de 1931 où l’A. étudie ensemble «les faits littéraires, les concordances et les divergences qui caractérisent une époque, les formes spécifiques qu’y prennent les œuvres, […] leurs rapports avec le milieu historique et social, la vision de la vie qui s’y exprime» (p. 8). La même année que les Essais critiques d’Arland et que les articles de Drieu La Rochelle sur «la fin de l’après-guerre», il interroge l’inquiétude des années 1920 et envisag...

  4. Numerical Investigation of APR1400 Loop Seal Reformation and Clearing Phenomena during Post-LOCA Long-term Cooling Period using RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. I.; Jeon, J. H.; Park, J. H.; Sung, H. J.; Lee, J. I.; Choi, T. S. [KEPCO NF, Daejeon (Korea, Republic of)

    2016-10-15

    Hand calculations had been tried to show that the loop seal reformation does not degrade the LTC performance of the APR1400, but the result was unclear. Therefore, the code assessments of the phenomena for APR1400 are required to guarantee the performance of LTC. In the present study, RELAP5/MOD3.3 patch04 (3.3iy) is used for the assessments. The safety degradation, e.g., possible cladding temperature rise due to LSRC during LTC period would be stronger when the safety injection (SI) is larger, while the core uncovery is more probable when the SI is smaller. In other words, it is not easy to determine the limiting condition of safety injection as two or four safety injection pumps (SIPs) in APR1400. In the present study, both the minimum SI condition with two SIPs and the maximum SI condition with four SIPs are considered. The study focuses only on the top slot break condition due to its highest possibility of LSRC phenomena. The LSRC issues for APR1400 are discussed and investigated through numerical investigation using RELAP5MOD3.3 patch04 for top-slot cold leg (pump discharge line) breaks. The major items investigated are whether the simultaneous four loop seal reformation is possible and whether there is any possible violation of the long term coolability criteria in 10 CFR 50.46. Safety injection with two SIPs and four SIPs are investigated to find that the four loop seal reformation condition before the simultaneous injection may occur only with four SIPs.

  5. Comparison of APR1400 safety between brake site and shin-Kori site Due to the difference in the climate conditions

    International Nuclear Information System (INIS)

    Yoon, Ho Joon; Lee, Jeong Ik; Lee, Jeong Ik

    2012-01-01

    Brake Nuclear Power Plant (BNPP) is now under the construction based on APR1400 designed by Korean Electric Power Corporation (KEPCO). APR1400 is a two loop pressurized water reactor, the nuclear steam supply system (NSSS) US designed for about put of 4,000 MWt, with a corresponding electrical output of approximately 1,390 MWe. The first APR1400 (SKN 3 and 4) constructed in Shin-Kori, Korea has been modified according to the surrounding environment of the United Arab Emirates. In this paper, authors would like to compare safety issues between B NPP and Skin due to the changes of surroundings, since the site characteristics are very different. For instance, the mean annual air temperature in the UAE is 28 .deg. C and the peak air temperature was recorded as 48.8 .deg. C. Sea temperatures are varying from 17. deg. C in January to 35. deg. C in August, while that of Korea is in 9-16. deg. C range. Hot climate of UAE and the malfunction of HVAC system can lead the increasing of the water temperature in safety injection system (SIS). The heated water in SIS may affect the safety margin of the peak cladding temperature (PCT). The change of PCT and response time according to design basis accident scenarios such as large break LOCA are analyzed in detail. To evaluate such effect, Mars code was utilized to evaluate assumed condition by KAIST and the analyses of the results were carried out by Khalifa Univ.

  6. Analysis of Post-LOCA Core Inlet Blockage to Evaluate In-vessel Downstream Effect in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The method was developed to have a conservatism to cover the uncertainty of analysis and the acceptance is judged by the representative bounding estimation. However, the important safety parameters such as the available driving head need to be confirmed by the plant specific calculation. Also an interaction between the debris induced head loss and the core flow rate needs to be explained because the head loss induced by debris in actual condition may reduce the core inflow rate faster. To confirm the safety parameters, in this study, thermal-hydraulic response considering the core inlet blockage (CIB) by debris during LTCC process following a double-ended guillotine break of cold leg (CLB), one of hot leg (HLB) and one of intermediate leg (ILB) of the APR1400 were calculated, respectively. MARS-KS 1.3 code has been used. The CIB has been modeled by the closure of valves to the core in exponential manner with time to observe the behavior near the complete blockage. To understand the effect of core inlet blockage (CIB) during a long term core cooling (LTCC) phase following a loss-of-coolant accident (LOCA) in the light of in-vessel downstream effect (IDE) of Generic Safety Issue (GSI) 191, double-ended guillotine break of hot leg (HLB), one of cold leg (CLB) and one of intermediate leg (ILB) were calculated, respectively. And the important safety parameters such as the available driving head and the head loss due to debris were calculated using MARS-KS code and discussed in comparison with the WCAP method. As a result, a little delayed heatup behavior of the fuel cladding was found for all the cases, which due to the redistribution of flow within the core after blockage.

  7. Analysis of a Natural Circulation in the Reactor Coolant System Following a High Pressure Severe Accident at APR1400

    International Nuclear Information System (INIS)

    Kim, Han Chul; Cho, Yong Jin; Park, Jae Hong; Cho, Song Won

    2011-01-01

    Under a high temperature and pressure condition during a severe accident, hot leg pipes or steam generator tubes could fail due to creep rupture following natural circulation in the Reactor Coolant System (RCS) unless depressurization of the system is performed at a proper time. Natural circulation in the RCS can be a multi-dimensional circulation in the reactor vessel, a partial loop circulation of two-phase flow from the core up to steam generators (SGs), or circulation in the total loop. It can delay the reactor vessel failure time by removing heat from the reactor core. This natural phenomenon can be hardly simulated with a single flow path model for the hot spots of the RCS, since it cannot deal with the counter-current flow. Thus it may estimate accident progression faster than reality, which may cause troubles for optimized implementation of severe accident management strategies. An earlier damage in the RCS other than the reactor pressure vessel may make subsequent behaviors of hydrogen or fission products in the containment quite different from the single reactor vessel failure. Therefore, a RCS model which treats natural circulation is needed to evaluate the RCS response and the safety depressurization strategy in a best-estimate way. The aim of this study is to develop a detailed model which allows natural circulation between the reactor vessel and steam generators through hot legs, based on the existing APR1400 RCS model. The station blackout sequence was selected to be the representative high-pressure scenario. Sensitivity study on the effect of node configuration of the upper plenum and addition of cross flow paths from the upper plenum to the hot legs were carried out. This model is described herein and representative calculation results are presented

  8. Nighttime Near Infrared Observations of Augustine Volcano Jan-Apr, 2006 Recorded With a Small Astronomical CCD Camera

    Science.gov (United States)

    Sentman, D.; McNutt, S.; Reyes, C.; Stenbaek-Nielsen, H.; Deroin, N.

    2006-12-01

    Nighttime observations of Augustine Volcano were made during Jan-Apr, 2006 using a small, unfiltered, astronomical CCD camera operating from Homer, Alaska. Time-lapse images of the volcano were made looking across the open water of the Cook Inlet over a slant range of ~105 km. A variety of volcano activities were observed that originated in near-infrared (NIR) 0.9-1.1 micron emissions, which were detectable at the upper limit of the camera passband but were otherwise invisible to the naked eye. These activities included various types of steam releases, pyroclastic flows, rockfalls and debris flows that were correlated very closely with seismic measurements made from instruments located within 4 km on the volcanic island. Specifically, flow events to the east (towards the camera) produced high amplitudes on the eastern seismic stations and events presumably to the west were stronger on western stations. The ability to detect nighttime volcanic emissions in the NIR over large horizontal distances using standard silicon CCD technology, even in the presence of weak intervening fog, came as a surprise, and is due to a confluence of several mutually reinforcing factors: (1) Hot enough (~1000K) thermal emissions from the volcano that the short wavelength portion of the Planck radiation curve overlaps the upper portions (0.9-1.1 micron) of the sensitivity of the silicon CCD detectors, and could thus be detected, (2) The existence of several atmospheric transmission windows within the NIR passband of the camera for the emissions to propagate with relatively small attenuation through more than 10 atmospheres, and (3) in the case of fog, forward Mie scattering.

  9. Analysis of Post-LOCA Core Inlet Blockage to Evaluate In-vessel Downstream Effect in APR1400

    International Nuclear Information System (INIS)

    Bang, Young Seok

    2015-01-01

    The method was developed to have a conservatism to cover the uncertainty of analysis and the acceptance is judged by the representative bounding estimation. However, the important safety parameters such as the available driving head need to be confirmed by the plant specific calculation. Also an interaction between the debris induced head loss and the core flow rate needs to be explained because the head loss induced by debris in actual condition may reduce the core inflow rate faster. To confirm the safety parameters, in this study, thermal-hydraulic response considering the core inlet blockage (CIB) by debris during LTCC process following a double-ended guillotine break of cold leg (CLB), one of hot leg (HLB) and one of intermediate leg (ILB) of the APR1400 were calculated, respectively. MARS-KS 1.3 code has been used. The CIB has been modeled by the closure of valves to the core in exponential manner with time to observe the behavior near the complete blockage. To understand the effect of core inlet blockage (CIB) during a long term core cooling (LTCC) phase following a loss-of-coolant accident (LOCA) in the light of in-vessel downstream effect (IDE) of Generic Safety Issue (GSI) 191, double-ended guillotine break of hot leg (HLB), one of cold leg (CLB) and one of intermediate leg (ILB) were calculated, respectively. And the important safety parameters such as the available driving head and the head loss due to debris were calculated using MARS-KS code and discussed in comparison with the WCAP method. As a result, a little delayed heatup behavior of the fuel cladding was found for all the cases, which due to the redistribution of flow within the core after blockage

  10. Évolution des conditions d’initiation du traitement antirétroviral des patients infectés par le VIH en Afrique de l’Ouest

    Science.gov (United States)

    Bashi, J.; Balestre, E.; Messou, E.; Maiga, M.; Coffie, P.A.; Zannou, D.M.; Ba-Gomis, O.; Traore, H.A.; Eholie, S.; Minga, A.; Sow, P.S.; Bissagnene, E.; Dabis, F.; Ekouevi, D.K.

    2013-01-01

    Résumé Objectif Étudier entre 1996 et 2006, l’évolution des schémas thérapeutiques et du profil clinique et immunologique des patients infectés par le VIH au début du traitement antirétroviral (TARV) en Afrique de l’Ouest. Cadre et méthode Les données issues de 12 centres cliniques adultes (IeDEA West Africa réseau collaboratif de prise en charge de l’infection à VIH) de cinq pays (Bénin, Cote d’Ivoire, Sénégal, Gambie, Mali) ont été mises en commun et analysées. Les patients âgés de 16 ans et plus dont le sexe, la date de naissance et la date d’initiation du TARV étaient connus ont été inclus dans cette étude. Résultats Quatorze mille quatre-cent-quatre-vingt-seize patients avaient débuté un TARV entre 1996–2006 avec 55 % des patients l’ayant débuté entre 2005–2006. La proportion de femmes était de 46 % en 1996–2000 et de 63 % en 2005–2006. L’âge médian à la mise sous traitement était constant: 35 ans chez les femmes et 40 ans chez les hommes. La proportion de patients qui ont débuté le TARV avec un taux de CD4 inférieur à 200 cellules/µl était de 54 % en 1996–2000 et de 64 % en 2005–2006. Les combinaisons thérapeutiques les plus prescrites étaient: AZT/3TC (ou d4T/DDI)/IDV (27 %) en 1996–2000; d4T (ou AZT)/3TC/EFV (59 %) en 2003–2004; et d4T/3TC/NVP (49 %) en 2005–2006. Les traitements de première ligne recommandés par l’OMS étaient débutés dans 83 % de cas en 2005–2006. Conclusion De nouvelles approches pour débuter un TARV plus précocement doivent être développées pour améliorer la survie des patients sous TARV. PMID:20045273

  11. Treatment, Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant; Traitement et Elimination Future des Dechets Radioactifs a l'Usine de Traitement Chimique de L'Idaho; 0410 041d 0414 ; Tratamiento y Evacuacion de Desechos Radiactivos en la Planta de Tratamiento Quimico de Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, James I. [Phillips Petroleum Company, Atomic Energy Division, Idaho Falls (United States)

    1960-07-01

    Acidic wastes from the recovery of enriched uranium from aluminium, zirconium, and stainless-steel fuels at the Idaho Chemical Processing Plant are stored in underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste-tank farm as well as the methods of environmental disposal of low-level wastes is described. The ''concentrate and contain'' philosophy of waste disposal has as its ultimate aim the production of a solid mass containing the fission products. The disadvantage of increased treatment costs may or may not be offset by reduction in storage costs. The low thermal conductivity of solids makes storage temperature considerations more important than for liquids. The acid aluminium nitrate wastes from the processing of fuels of the Material Testing Reactor type may be converted to granular alumina by calcining in a fluidized bed from 350 Degree-Sign to 550 Degree-Sign C. The major process components are the NaK heated calciner, an off-gas cleaning system and the solids storage vessels. The process design and the research and development programme are reviewed. On the basis of the successful demonstration of fluidized-bed calcining and high-temperature solids storage in conjunction with other considerations, a number of future storage concepts and their environmental connotations are discussed. (author) [French] A l'usine de traitement chimique de l'Idaho, les dechets acides provenant de la recuperation de l'uranium enrichi contenu dans les cartouches de combustible en aluminium, zirconium, et acier inoxydable sont stockes dans des reservoirs souterrains de deux formes differentes et d'une capacite theorique de 30,000 et de 300,000 gallons. L'auteur donne une description du plan et du fonctionnement de l'annexe ou se trouvent les reservoirs a dechets, ainsi que des methodes d'elimination des dechets de faible activite dans le milieu ambiant. Le but meme du systeme qui consiste a concentrer et a

  12. Pratiques, objets et finalités de collaboration en lien avec l’intégration des tablettes numériques dans une école secondaire | Practices, Objects and Collaboration Purposes Related to the Integration of Digital Tablets in a High School

    Directory of Open Access Journals (Sweden)

    Nadia Cody

    2016-08-01

    Full Text Available Bien que les technologies de l’information et de la communication (TIC occupent une place de plus en plus prépondérante, tant au sein de la société que de l’école (Anderson, 2010, on remarque que leur intégration en contexte scolaire représente encore un défi de taille (Underwood et Dillon, 2011. Selon certains auteurs (Portelance, 2011; Desgagné, 1997, la collaboration constituerait un vecteur pour transformer les pratiques éducatives. Comment la collaboration peut-elle contribuer à ce changement que représente l’intégration des TIC? Les résultats d’une recherche-action, menée depuis trois ans de concert avec une école secondaire ayant pour objectif d’intégrer la tablette numérique, permet de mettre en lumière des pratiques, des objets et des finalités de collaboration qui ont émergé entre les différents acteurs, favorisant ainsi l’implantation de cet outil technologique. Although Information and Communication Technologies (ICT play an increasingly predominant role (Anderson, 2010, their integration in school context is still a challenge (Underwood and Dillon, 2011. According to Portelance (2011 and Desgagné (1997, collaboration is one vector that can be used to transform educational practices. How can collaboration contribute to the ICT integration process into our schools? The results of an action research, conducted for three years along with a high school that aims to integrate digital tablet, allows to highlighting practices, objects and collaboration purposes that emerged between actors, therefore facilitating the implementation of this technological tool.

  13. Fabrication de transistors mono-electroniques en silicium pour le traitement classique et quantique de l'information: une approche nanodamascene

    Science.gov (United States)

    Harvey-Collard, Patrick

    Les transistors mono-electroniques (SETs) sont des dispositifs ayant un grand potentiel d'applications, comme la detection de charge ultra-sensible, la logique a basse consommation de puissance, la memoire ou la metrologie. De plus, la possibilite de pieger un seul electron et de manipuler son etat de spin pourrait permettre des applications en informatique quantique. Le silicium est un materiau interessant pour fabriquer l'ilot d'un SET. Son gap semi-conducteur permet le fonctionnement du dispositif dans le regime a un seul electron ou trou et pourrait permettre d'etendre la plage d'operation du SET en temperature en augmentant l'energie d'addition du diamant central de la valeur du gap. En outre, le silicium beneficie de plus de quarante annees d'expertise en microfabrication et d'une compatibilite avec la technologie metal--oxyde--semi-conducteur complementaire (CMOS). Cependant, la fabrication de ces dispositifs fait face a de serieuses limitations a cause de la taille nanometrique requise pour l'ilot. A ce jour, les procedes de fabrication proposes permettant l'operation a la temperature ambiante sont trop peu reproductibles pour permettre des applications a grande echelle. Dans ce memoire de maitrise, la fabrication de transistors mono-electroniques en silicium (Si-SETs) pour le traitement classique et quantique de l'information est realisee avec un procede nanodamascene. Le polissage chimico-mecanique (CMP) est introduit comme etape clef de la fabrication du transistor, permettant le controle au nanometre pres (nanodamascene) de l'epaisseur du transistor. Cet outil permet la fabrication de dispositifs ayant une geometrie auparavant impossible a realiser et ouvre la porte a l'innovation technologique. De plus, un procede de gravure du silicium par plasma a couplage inductif (ICP) est developpe pour permettre la fabrication de nanostructures de silicium sur une nanotopographie alliant le nano et le 3D. Les Si-SETs fabriques sont caracterises a basse

  14. Binary analysis: 1. part: definitions and treatment of binary functions; 2. part: applications and functions of trans-coding; Analyse binaire: 1ere partie: definitions et traitements des fonctions binaires; 2eme partie: applications et fonctions de transcodage

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    The study of binary groups under their mathematical aspects constitutes the matter of binary analysis, the purpose of which consists in developing altogether simple, rigorous and practical methods needed by the technicians, the engineers and all those who may be mainly concerned by digital processing. This subject, fast extending if not determining, however tends actually to play a main part in nuclear electronics as well as in several other research areas. (authors) [French] L'analyse binaire a pour objet l'etude mathematique des proprietes d'ensembles binaires algebriques et pour but l'elaboration de methodes simples, rigoureuses et pratiques, destinees aux techniciens, aux ingenieurs et a tous ceux qu'interesse directement le traitement numerique de l'information, discipline en expansion rapide qui, deja, en electronique nucleaire comme dans de nombreux autres domaines de la recherche, tend a jouer un role essentiel sinon determinant. (auteurs)

  15. Procédés de traitements des effluents de cave adaptés au secteur des vins biologiques : état des lieux et perspectives

    Directory of Open Access Journals (Sweden)

    Rochard Joël

    2017-01-01

    Full Text Available Au-delà des itinéraires viticoles et œnologiques, la viticulture biologique doit également s'intéresser aux difflérents aspects de la viticulture durable concernant notamment le traitement des effluents de cave, avec une approche écologique. Parallèlement à la performance d'épuration, le traitement des effluents doit intégrer difflérentes orientations écologiques : faible consommation d'énergie et limitation des déchets (boues de plus en plus difflicile à gérer par voie agronomique. En complément, en liaison avec le concept d'éco-oenotourisme, une intégration harmonieuse de dispositif peut être envisagée, qui associe à la fois une limitation des nuisances olfactives et sonores, une valorisation paysagère et de la biodiversité ainsi qu'éventuellement une réutilisation des eaux traitées pour l'irrigation. Les techniques de lits ou massifs plantés ont prouvé leur efflicacité dans le domaine de l'épuration des effluents d'origine domestique. Leur application aux effluents de cave qui fait l'objet de difflérentes recherches depuis plusieurs années, permet de valoriser l'environnement esthétique et écologique de la cave. L'objectif de la communication et de présenter le principe de l'épuration par lit planté de roseaux avec les difflérentes mises en œuvre envisageable au niveau des caves.

  16. Real-time PCR quantification and diversity analysis of the functional genes aprA and dsrA of sulfate-reducing bacteria in marine sediments of the Peru continental margin and the Black Sea

    Directory of Open Access Journals (Sweden)

    Axel eSchippers

    2011-12-01

    Full Text Available A quantitative, real-time PCR (Q-PCR assay for the functional gene adenosine 5´-phosphosulfate reductase (aprA of sulfate-reducing bacteria (SRB was designed. This assay was applied together with described Q-PCR assays for dissimilatory sulfite reductase (dsrA and the 16S rRNA gene of total Bacteria to marine sediments from the Peru margin (0 – 121 meters below seafloor (mbsf and the Black Sea (0 – 6 mbsf. Clone libraries of aprA show that all isolated sequences originate from SRB showing a close relationship to aprA of characterised species or form a new cluster with only distant relation to aprA of isolated SRB. Below 40 mbsf no aprA genes could be amplified. This finding corresponds with results of the applied new Q-PCR assay for aprA. In contrast to the aprA the dsrA gene could be amplified up to sediment depths of 121 mbsf. Even in such an extreme environment a high diversity of this gene was detected. The 16S rRNA gene copy numbers of total Bacteria were much higher than those of the functional genes at all sediment depths and used to calculate the proportion of SRB to the total Bacteria. The aprA and dsrA copy numbers comprised in average 0.5 - 1 % of the 16S rRNA gene copy numbers of total Bacteria in the sediments up to a depth of ca. 40 mbsf. Depth profiles of the aprA and dsrA copy numbers were almost equal for all sites. Gene copy numbers decreased concomitantly with depth from around 108 / g sediment close to the sediment surface to less than 105 / g sediment at 5 mbsf. In the zone without detectable sulfate in the pore water from ca. 40 – 121 mbsf (Peru margin ODP site 1227, only dsrA (but not aprA was detected with copy numbers of less than 104 / g sediment, comprising ca. 14 % of the 16S rRNA gene copy numbers of total Bacteria. In this zone sulfate might be provided for SRB by anaerobic sulfide oxidation.

  17. Comparison of the Economic Aspects of the Treatment and Storage of Fission Products from Installations Processing Irradiated Natural Uranium; Aspects Economiques Compares du Traitement et du Stockage des Produits de Fission Issus des Usines de Traitement de l'Uranium Naturel Irradie; Sravnitel'nye ehkonomicheskie aspekty obrabotki i khraneniya produktov deleniya, poluchaemykh na zavodakh po pererabotke obluchennogo prirodnogo urana; Aspectos Economicos Comparados del Tratamiento y del Almacenamiento de los Productos de Fision que Salen de las Plantas de Tratamiento de Uranio Natural Irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L.; Lesur, P.; Giraud, R. [Commissariat a l' Energie Atomique, Paris (France); Wanlin, J. [Societe Saint-Gobain Techniques Nouvelles, Paris (France)

    1966-02-15

    The paper summarizes the main policies adopted for the management of fission product effluents and briefly describes the essential technical features of the stainless steel storage installations (in acid medium) used in France, giving a breakdown of the costs involved. The dependence of these costs on the activity of the solutions stored and on their heat release is shown. The second part of the paper discusses the cost of storage in terms of feasible tank size. The optimum size for such tanks and the rate at which they are placed in service are determined in relation to the characteristics of the fission products to be stored and to the respective capacities of the installations for processing irradiated natural uranium. It is shown that although storage costs depend on the assumptions made regarding the useful life of installations, rates of interest and operating costs, optimum policy decisions (as to size and rate of entry into service) are independent of these assumptions, being determined solely by the variation in the cost of tanks, according to size. These are the factors which enter into the optimized cost of storing these effluents indefinitely. In the third part, this method of indefinite storage is compared with other possibilities of fission product management, e.g. vitrification and separation of Cs and Sr. The paper discusses the economics of the various methods and summarizes some possible long-term solutions. (author) [French] Apres avoir rappele les principales politiques de gestion le plus souvent envisagees pour les produits de fission, le memoire decrit sommairement les caracteristiques techniques essentielles des installations de stockage en acier inoxydable (en milieu acide) utilisees en France et la structure des couts de ces installations. U montre la sensibilite de ces couts a l'activite des solutions stockees et a leur degagement de chaleur. Dans une deuxieme partie, les auteurs examinent leur cout de stockage, selon la taille des

  18. Molecular Analysis of the Diversity of Sulfate-Reducing and Sulfur-Oxidizing Prokaryotes in the Environment, Using aprA as Functional Marker Gene▿ †

    Science.gov (United States)

    Meyer, Birte; Kuever, Jan

    2007-01-01

    The dissimilatory adenosine-5′-phosposulfate reductase is a key enzyme of the microbial sulfate reduction and sulfur oxidation processes. Because the alpha- and beta-subunit-encoding genes, aprBA, are highly conserved among sulfate-reducing and sulfur-oxidizing prokaryotes, they are most suitable for molecular profiling of the microbial community structure of the sulfur cycle in environment. In this study, a new aprA gene-targeting assay using a combination of PCR and denaturing gradient gel electrophoresis is presented. The screening of sulfate-reducing and sulfur-oxidizing reference strains as well as the analyses of environmental DNA from diverse habitats (e.g., microbial mats, invertebrate tissue, marine and estuarine sediments, and filtered hydrothermal water) by the new primer pair revealed an improved microbial diversity coverage and less-pronounced template-to-PCR product bias in direct comparison to those of the previously published primer set (B. Deplancke, K. R. Hristova, H. A. Oakley, V. J. McCracken, R. Aminov, R. I. Mackie, and H. R. Gaskins, Appl. Environ. Microbiol. 66:2166-2174, 2000). The concomitant molecular detection of sulfate-reducing and sulfur-oxidizing prokaryotes was confirmed. The new assay was applied in comparison with the 16S rRNA gene-based analysis to investigate the microbial diversity of the sulfur cycle in sediment, seawater, and manganese crust samples from four study sites in the area of the Lesser Antilles volcanic arc, Caribbean Sea (Caribflux project). The aprA gene-based approach revealed putative sulfur-oxidizing Alphaproteobacteria of chemolithoheterotrophic lifestyle to have been abundant in the nonhydrothermal sediment and water column. In contrast, the sulfur-based microbial community that inhabited the surface of the volcanic manganese crust was more complex, consisting predominantly of putative chemolithoautotrophic sulfur oxidizers of the Betaproteobacteria and Gammaproteobacteria. PMID:17921272

  19. Molecular analysis of the diversity of sulfate-reducing and sulfur-oxidizing prokaryotes in the environment, using aprA as functional marker gene.

    Science.gov (United States)

    Meyer, Birte; Kuever, Jan

    2007-12-01

    The dissimilatory adenosine-5'-phosphosulfate reductase is a key enzyme of the microbial sulfate reduction and sulfur oxidation processes. Because the alpha- and beta-subunit-encoding genes, aprBA, are highly conserved among sulfate-reducing and sulfur-oxidizing prokaryotes, they are most suitable for molecular profiling of the microbial community structure of the sulfur cycle in environment. In this study, a new aprA gene-targeting assay using a combination of PCR and denaturing gradient gel electrophoresis is presented. The screening of sulfate-reducing and sulfur-oxidizing reference strains as well as the analyses of environmental DNA from diverse habitats (e.g., microbial mats, invertebrate tissue, marine and estuarine sediments, and filtered hydrothermal water) by the new primer pair revealed an improved microbial diversity coverage and less-pronounced template-to-PCR product bias in direct comparison to those of the previously published primer set (B. Deplancke, K. R. Hristova, H. A. Oakley, V. J. McCracken, R. Aminov, R. I. Mackie, and H. R. Gaskins, Appl. Environ. Microbiol. 66:2166-2174, 2000). The concomitant molecular detection of sulfate-reducing and sulfur-oxidizing prokaryotes was confirmed. The new assay was applied in comparison with the 16S rRNA gene-based analysis to investigate the microbial diversity of the sulfur cycle in sediment, seawater, and manganese crust samples from four study sites in the area of the Lesser Antilles volcanic arc, Caribbean Sea (Caribflux project). The aprA gene-based approach revealed putative sulfur-oxidizing Alphaproteobacteria of chemolithoheterotrophic lifestyle to have been abundant in the nonhydrothermal sediment and water column. In contrast, the sulfur-based microbial community that inhabited the surface of the volcanic manganese crust was more complex, consisting predominantly of putative chemolithoautotrophic sulfur oxidizers of the Betaproteobacteria and Gammaproteobacteria.

  20. Validation of the All Patient Refined Diagnosis Related Group (APR-DRG) Risk of Mortality and Severity of Illness Modifiers as a Measure of Perioperative Risk.

    Science.gov (United States)

    McCormick, Patrick J; Lin, Hung-Mo; Deiner, Stacie G; Levin, Matthew A

    2018-03-22

    The All Patient Refined Diagnosis Related Group (APR-DRG) is an inpatient visit classification system that assigns a diagnostic related group, a Risk of Mortality (ROM) subclass and a Severity of Illness (SOI) subclass. While extensively used for cost adjustment, no study has compared the APR-DRG subclass modifiers to the popular Charlson Comorbidity Index as a measure of comorbidity severity in models for perioperative in-hospital mortality. In this study we attempt to validate the use of these subclasses to predict mortality in a cohort of surgical patients. We analyzed all adult (age over 18 years) inpatient non-cardiac surgery at our institution between December 2005 and July 2013. After exclusions, we split the cohort into training and validation sets. We created prediction models of inpatient mortality using the Charlson Comorbidity Index, ROM only, SOI only, and ROM with SOI. Models were compared by receiver-operator characteristic (ROC) curve, area under the ROC curve (AUC), and Brier score. After exclusions, we analyzed 63,681 patient-visits. Overall in-hospital mortality was 1.3%. The median number of ICD-9-CM diagnosis codes was 6 (Q1-Q3 4-10). The median Charlson Comorbidity Index was 0 (Q1-Q3 0-2). When the model was applied to the validation set, the c-statistic for Charlson was 0.865, c-statistic for ROM was 0.975, and for ROM and SOI combined the c-statistic was 0.977. The scaled Brier score for Charlson was 0.044, Brier for ROM only was 0.230, and Brier for ROM and SOI was 0.257. The APR-DRG ROM or SOI subclasses are better predictors than the Charlson Comorbidity Index of in-hospital mortality among surgical patients.

  1. PRIMA-1Met/APR-246 induces apoptosis and tumor growth delay in small cell lung cancer expressing mutant p53

    DEFF Research Database (Denmark)

    Zandi, Roza; Selivanova, Galina; Christensen, Camilla Laulund

    2011-01-01

    Small cell lung cancer (SCLC) is a highly malignant disease with poor prognosis, necessitating the need to develop new and efficient treatment modalities. PRIMA-1(Met) (p53-dependent reactivation of massive apoptosis), also known as APR-246, is a small molecule, which restores tumor suppressor...... function to mutant p53 and induces cancer cell death in various cancer types. Since p53 is mutated in more than 90% of SCLC, we investigated the ability of PRIMA-1(Met) to induce apoptosis and inhibit tumor growth in SCLC with different p53 mutations....

  2. Intervention intégrée quant au risque de diabète après le diabète ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Les femmes ayant souffert de diabète sucré de la grossesse, un diabète temporaire qui apparaît pendant la grossesse, présentent un risque élevé de développer le diabète de type 2 après leur grossesse. Cette étude de recherche abordera le problème en Afrique du Sud par l'intermédiaire d'une intervention novatrice au ...

  3. L'Islam noir à Bahia d'après les travaux de l'école ethnologique brèsilienne

    Directory of Open Access Journals (Sweden)

    Roger Bastide

    1951-03-01

    Full Text Available RICARD (Robert. - L'Islam noir à Bahia d'après les travaux de l'école ethnologique brèsilienne (Primeiro Artigo do Parágrafo Depois da publicação, em frances, do livro de Nina Rodrigues sobre O animismo fetichista dos negros da Bahia e da duas memórias do Piére Etienne, parece que a França pouco tem ouvido falar dos problemas afro-brasileiras.

  4. Study of Combined Treatment for Damp-Harvested Maize: Gamma Irradiation and Drying by Controlled Ventilation; Etude d'un Traitement Combine pour le Conditionnement du Mais Recolte Humide: Irradiation Gamma et Sechage par Ventilation Controlee; Izuchenie kombinirovannoj obrabotki kukuruzy molochno-voskovoj spelosti; Estudio de un Tratamiento Combinado para el Acondicionamiento del Maiz Recolectado Humedo: Irradiacion Gamma y Secado por Ventilacion Controlada

    Energy Technology Data Exchange (ETDEWEB)

    Saint-Lebe, L.; Pelegrin, P. [Centre d' Etudes Nucleaires de Cadarache (France); Guilbot, A. [Institut National de la Recherche Agronomique, Massy (France)

    1966-11-15

    optimales de la radiopasteurisation du maies. En possession de ces donnees les auteurs abordent a l'echelle du laboratoire le probleme du traitement combine irradiation-ventilation, dans des conditions experimentales faciles a transposer sur le plan industriel. Ils etudient les modifications microbiologiques et biochimiques qui se produisent dans la fraction des grains humides atteinte en dernier par le flux d'air sechant, ce qui correspond au cas le plus defavorable. D'un point de vue quantitatif, il apparait dans cette zone que l'effet depressif de l'irradiation sur la mycoflore persiste meme apres 26 jours; cet effet est encore plus important sur les bacteries. D'un point de vue qualitatif, on observe la regeneration prioritaire d'une mycoflore precisement sensible au flux d'air sec qui doit l'atteindre. Des applications industrielles sont en vue; mais, avant de passer au stade pilote, phase indispensable a retablissement d'un prix de revient, il est necessaire de mener plus avant des investigations biochimiques. De meme, le point de vue de la sante publique ne devra pas etre neglige pour le cas ou le procede trouverait une application dans le domaine de l'alimentation animale ou humaine. (author) [Spanish] La asociacion de los efectos de la irradiacion gamma con cobalto-60 y del secado lento por ventilacion en frio (10 a 25 Degree-Sign C) en las celdas de almacenamiento se practica con el fin de hallar un sustitutivo a la solucion clasica de secado rapido con aire calentado a alta temperatura, pues el primer tratamiento es mas apropiado para mantener la integridad del grano'y ejerce al mismo tiempo un efecto purificador desde el punto de vista microbiologico. Este problema afecta en Francia a un millon de toneladas de maiz humedo (1964) y cobrara cada vez mas importancia tanto en Europa como en los paises de la zona tropical. Los autores estudian primero la influencia directa de las radiaciones gamma sobre el rendimiento y las caracteristicas tecnicas del almidon. Este

  5. A Study on the Coupled FEM-Analysis for Reactor Vessel Lower Head of APR1400 under the Severe Accident Scenario

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyonam; Namgung, Ihn [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    For the stabilization of the RPV the in-vessel retention strategy with external reactor vessel cooling (IVR-ERVC) is adopted in APR1400. Under this severe accident condition, a good understanding of the mechanical behavior of the reactor vessel lower head (RVLH) is necessary both for verification of structural integrity and for improving the design applying appropriate accident mitigation strategies. The purpose of this study is to develop the analysis method of the RVLH with thermo-mechanical analysis using FEM tool (ANSYS v.15) in case of core-melting severe accident condition, and then analyze the RVLH of APR1400 including creep behavior. The plastic strain can be the major cause of lower head failure on the reactor vessel, and the creep cannot be not negligible factor of the failure under the severe accident condition. In the study, we applied constant convection coefficient at assumed temperature on the outside wall of RPV and substitute creep data of SA-508. In addition, it was found that the steel ablation at the interface between corium and vessel steel is not only a thermal phenomenon in the METCOR experiments. Corrosion processes and the formation of eutectics lead to the erosion of the vessel steel at temperatures that are significantly lower than the melting temperature of steel. It called thermo-chemical attack of the corium (corrosion). Reduced wall thickness because of the thermo-chemical effect by corium increase the equivalent plastic strain, and decrease the minimum time to reach 20% creep strain.

  6. Recovery and radio-resistance in mice after external irradiation; Restauration et radio-resistance chez la souris apres irradiation externe

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    The author presents a literature study concerning recovery from external irradiation and an analysis of experimental data (which appear to suggest the idea of a radio-resistance in animals), as well as the hypotheses put forward for explaining this phenomenon. The author then describes an experiment carried out on mice whose LD 50/30 days increased from 1005 to 1380 rads and for which it was shown that an increase occurs in the number of certain anti-bodies circulating after a low dose of {gamma} irradiation. (author) [French] L'auteur presente une etude bibliographique de la restauration apres irradiation externe et une analyse des donnees experimentales qui paraissent suggerer la notion de radioresistance chez les animaux ainsi que les hypotheses cherchant a expliquer ce phenomene. Il relate ensuite une experience realisee sur des souris dont la DL 50/30 jours est passee de 1005 a 1380 rads et dans laquelle est montree l'augmentation de certains anticorps circulant apres une faible dose d'irradiation gamma. (auteur)

  7. Failure Mode and Effect Analysis of the Application Software of the Safety-critical I and C System in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Koheun; Kim, Yong geul; Choi, Woong seok; Sohn, Se do [KEPCO Engineering and Construction, Daejeon (Korea, Republic of)

    2016-10-15

    In APR1400, the computer software hazard analysis is performed by hazard and operability analysis (HAZOP) method. Meanwhile, HAZOP has its limitation and cannot be considered better than fault tree analysis (FTA) or failure mode and effect (FMEA) analysis. HAZOP assumes that the system has been carefully studied, and all possible hazards, their effects or consequences and remedies are incorporated in the system. But incorporating every possible event in the design is impossible. In this light, this paper attempts to use FMEA method for evaluating the risk for safety-critical instrumentation and control (I and C) system software for NPP which is more practically than HAZOP. It is possible because the software failures are due to systematic faults that causing simultaneous failure in multiple division when the triggering event happens. This analysis is applied to safety-critical system of Shin-Hanul units 1 and 2 NPP, i.e., APR1400. Through SFMEA, the critical software failure modes and tasks that could result in CCF are identified and also evaluated to determine the associated risk level (e.g. high or intermediate or low) based on the failure effect. Biggest benefit from this analysis comparing with HAZOP is it can reveal the possible weak points and provide the guidance to the V and V team by helping to generate the test cases.

  8. Recovery and radio-resistance in mice after external irradiation; Restauration et radio-resistance chez la souris apres irradiation externe

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    The author presents a literature study concerning recovery from external irradiation and an analysis of experimental data (which appear to suggest the idea of a radio-resistance in animals), as well as the hypotheses put forward for explaining this phenomenon. The author then describes an experiment carried out on mice whose LD 50/30 days increased from 1005 to 1380 rads and for which it was shown that an increase occurs in the number of certain anti-bodies circulating after a low dose of {gamma} irradiation. (author) [French] L'auteur presente une etude bibliographique de la restauration apres irradiation externe et une analyse des donnees experimentales qui paraissent suggerer la notion de radioresistance chez les animaux ainsi que les hypotheses cherchant a expliquer ce phenomene. Il relate ensuite une experience realisee sur des souris dont la DL 50/30 jours est passee de 1005 a 1380 rads et dans laquelle est montree l'augmentation de certains anticorps circulant apres une faible dose d'irradiation gamma. (auteur)

  9. Une installation expérimentale pour l'étude du traitement par combustion des fumées industrielles An Experimental Plant for Processing Industrial Fumes by Combustion

    Directory of Open Access Journals (Sweden)

    Morillon R.

    2006-11-01

    Full Text Available Le rejet à l'atmosphère d'effluents gazeux d'origine industrielle entraîne un accroissement sensible de la pollution atmosphérique ; en outre, il s'accompagne souvent d'une perte d'énergie lorsque l'élément polluant est un hydrocarbure. Dans ce cas, l'utilisation du gaz naturel pour le traitement par combustion des fumées industrielles apporte une solution élégante et souvent peu coûteuse grâce à la récupération d'énergie qu'il est possible de faire. La première partie de l'article rappelle les aspects théoriques de ce traitement ; en particulier, l'influence des divers éléments sur son efficacité y est discutée (composition de l'atmosphère polluée, température, temps de séjour, etc.. II apparaît ainsi que diverses conditions doivent être remplies simultanément pour obtenir une efficacité satisfaisante. Afin de disposer d'éléments d'ingénierie permettant de construire les unités de traitement les plus efficaces et les plus sûres possible, au coût le plus bas possible, la Direction des études et techniques nouvelles du Gaz de France a réalisé une installation expérimentale qui est présentée dans la deuxième partie de l'article. Enfin, quelques examples d'utilisation de cette installation expérimentale, qui constitue un nouvel outil de travail mis à la disposition des utisitateurs et des constructeurs, sont décrits dans la troisième partie de l'article. The discharge into the atmosphere of industrial waste gases causes substantially increased air pollution. Moreover, it is often accompanied by loss of energy when the polluting element is a hydrocarbon. In such cases, the use of natural gas for processing industrial fumes by combustion provides an elegant solution, which moy often prove economical too becouse of the recovery of energy it makes possible. The first part of this article reviews the theoretical aspects of such processing. The way in which its effectiveness is affected by various parameters

  10. Des recommandations probantes pour surveiller l’innocuité des antipsychotiques de deuxième génération chez les enfants et les adolescents

    Science.gov (United States)

    Pringsheim, Tamara; Panagiotopoulos, Constadina; Davidson, Jana; Ho, Josephine

    2012-01-01

    HISTORIQUE : Au Canada, l’utilisation d’antipsychotiques, notamment les antipsychotiques de deuxième génération (ADG), a augmenté de façon considérable depuis cinq ans chez les enfants ayant des troubles de santé mentale. Ces médicaments ont le potentiel de causer de graves complications métaboliques et neurologiques lorsqu’on les utilise de manière chronique. OBJECTIF : Synthétiser les données probantes relatives aux effets secondaires métaboliques et neurologiques précis associés à l’usage d’ADG chez les enfants et fournir des recommandations probantes sur la surveillance de ces effets secondaires. MÉTHODOLOGIE : Les auteurs ont procédé à une analyse systématique des essais cliniques contrôlés des ADG auprès d’enfants. Ils ont fait des recommandations à l’égard de la surveillance de l’innocuité des ADG d’après un modèle de classification fondé sur le système GRADE (système de notation de l’évaluation et de l’élaboration des recommandations). Lorsque les données probantes n’étaient pas suffisantes, ils fondaient leurs recommandations sur le consensus et l’avis d’experts. Un groupe consensuel multidisciplinaire a analysé toutes les données probantes pertinentes et est parvenu à un consensus à l’égard des recommandations. RÉSULTATS : Les recommandations probantes portant sur la surveillance de l’innocuité des ADG figurent dans les présentes lignes directrices. Les auteurs indiquent la qualité des recommandations relatives à des examens physiques et tests de laboratoire précis à l’égard de chaque ADG à des moments déterminés. CONCLUSION : De multiples essais aléatoires et contrôlés ont permis d’évaluer l’efficacité de bon nombre des ADG utilisés pour traiter les troubles de santé mentale en pédiatrie. Toutefois, leurs avantages ne sont pas sans risques : on observe à la fois des effets secondaires métaboliques et neurologiques chez les enfants traités au moyen d

  11. Aspects descriptifs du VIH/SIDA chez les sujets âgés de 50 ans et plus suivis au Centre de Traitement Agréé de Bafoussam - Cameroun

    Science.gov (United States)

    Mbopi-Kéou, François-Xavier; Djomassi, Lucienne Dempouo; Monebenimp, Francisca

    2012-01-01

    Introduction La littérature scientifique dispose de très peu de données relatives à l’épidémiologie du VIH chez les sujets âgés en Afrique subsaharienne. Au Cameroun, les caractéristiques épidémiologiques de l'infection par le VIH chez les sujets âgés de 50 ans et plus ne sont pas documentées. Méthodes Dans une étude de cohorte rétrospective et une enquête transversale, nous avons comparé les caractéristiques clinico-biologiques et la survie post thérapeutique des patients âgés de 50 ans et plus, sous traitement antirétroviral au Centre de Traitement Agrée de Bafoussam - Cameroun, aux adultes plus jeunes. Résultats L’âge moyen était de 39 ans, les extrêmes étant 17 et 88 ans. Les sujets âgés de 50 ans et plus représentaient 14,1% des cas. Les plus âgés étaient moins bien informés sur les modes de transmission du virus (p = 0,04). Leur séropositivité au VIH était le plus souvent découverte au décours d'une infection opportuniste (p = 0,02). La fréquence de comorbidité était significativement plus élevée chez les personnes âgées de 50 ans et plus (p VIH. La promotion du dépistage et les programmes d’éducation sanitaire relatifs au VIH/SIDA devraient être renforcés au sein de cette communauté déjà affaiblie par le poids de l’âge, afin de réduire l'incidence du SIDA et de leur assurer prise en charge précoce. PMID:23133707

  12. Etude de l'anémie chez les enfants séropositifs au VIH naïfs au traitement antirétroviral à Lubumbashi, République Démocratique du Congo

    Science.gov (United States)

    Mwadianvita, Costa Kazadi; Ilunga, Eric Kasamba; Djouma, Jackson; Wembonyama, Cecile Watu; Mutomb, Florence Mujing A; Ekwalanga, Michel Balaka; Kabongo, Joe; Mundongo, Henri; Mupoya, Kalombo; Wembonyama, Stanis; Kalenga Mwenze, Prosper; Nkoy, Albert Mwembo-Tambwe A

    2014-01-01

    Introduction Beaucoup d'enfants infectés par le VIH arrivent à la consultation dans un état d'anémie. Notre objectif était d’évaluer la prévalence et le typage de l'anémie chez ces enfants. Méthodes C'est une étude transversale réalisée dans 3 centres de prise en charge des Personnes Vivant avec le VIH à Lubumbashi de Mai 2010 à Mai 2011. La population d’étude était de 152 enfants, âgés de 6 à 180 mois, naïfs au traitement antirétroviral. Les statistiques descriptives usuelles ont été utilisées. Résultats La prévalence globale de l'anémie (définie comme l'hémoglobine < 11g/dl) était de 69,1% (n=105) et 11,4% avaient une anémie sévère (Hg < 7,0 g/dl). Parmi eux, 16% ont été transfusés au moins 1 fois. L'anémie sévère était positivement associée au stade clinique de la maladie (p=0,02). L'anémie microcytaire était majoritaire dans les deux tranches d’âge. Elle était plus hypochrome chez les enfants en âge préscolaire soit 9,5% et plus normochrome en âge scolaire soit 15,2%. L'anémie normocytaire était plus normochrome dans les deux tranches d’âge soit 12,4% en âge préscolaire et 6,7% en âge scolaire. L'anémie macrocytaire était rare. Conclusion Environ sept enfants sur dix, âgés de moins de 15 ans infectés par le VIH naïfs au traitement antirétroviral dans notre milieu sont anémiques. L'anémie est corrélée à la sévérité de la maladie. Il est important d'associer une prise en charge nutritionnelle et corriger l'anémie avant une trithérapie antirétrovirale. PMID:25018796

  13. Behaviour of BF{sub 3} counters after in-pile irradiation; Comportement de compteurs a BF{sub 3} apres irradiation dans un reacteur

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    The behaviour of a proportional BF{sub 3}LCT 14 NE 31 counter with aluminium cathode has been studied after irradiation from 10{sup 5} to 10{sup 6} n.cm{sup -2} in the swimming-pool reactor Triton. The pulse spectrum was only slightly modified by two successive irradiations at 10{sup 15} n.cm{sup -2}, and 1 hour after the end of the irradiation the decrease in sensitivity reached 10 to 20 per cent. One hour after irradiation at 10{sup 16} n.cm{sup -2} this decrease was 20 per cent but the pulse spectrum was affected. The advantages of an aluminium cathode with respect to a standard counter using a copper cathode and irradiated under the same conditions are given. Beforehand, it had been established that the limit for use of an aluminium-cathode counter in the presence of {gamma} radiation is about 200 R.h{sup -1}. (author) [French] Le comportement d'un compteur proportionnel a BF-3LCT 14 NE 31, a cathode d'aluminium, a ete etudie apres des irradiations de 10{sup 5} a 10{sup 6} n.cm{sup -2} dans la pile-piscine TRITON. Deux irradiations successives de 10{sup 15} n.cm{sup -2} ont peu modifie le spectre des impulsions et 1 heure apres la fin de l'exposition la perte de sensibilite etait de 10 a 20 pour cent. Une heure apres une irradiation de 10{sup 16} n.cm{sup -2}, cette perte etait de 20 pour cent mais le spectre d'impulsions etait perturbe. L'avantage d'une cathode en aluminium est mis en evidence par comparaison avec un compteur standard a cathode de cuivre irradie dans les memes conditions. En preliminaire, on avait etabli que la limite d'utilisation d'un compteur a cathode d'aluminium en presence de rayonnements {gamma} etait de l'ordre de 200 R.h{sup -1}. (auteur)

  14. Real-Time PCR Quantification and Diversity Analysis of the Functional Genes aprA and dsrA of Sulfate-Reducing Prokaryotes in Marine Sediments of the Peru Continental Margin and the Black Sea.

    Science.gov (United States)

    Blazejak, Anna; Schippers, Axel

    2011-01-01

    Sulfate-reducing prokaryotes (SRP) are ubiquitous and quantitatively important members in many ecosystems, especially in marine sediments. However their abundance and diversity in subsurface marine sediments is poorly understood. In this study, the abundance and diversity of the functional genes for the enzymes adenosine 5'-phosphosulfate reductase (aprA) and dissimilatory sulfite reductase (dsrA) of SRP in marine sediments of the Peru continental margin and the Black Sea were analyzed, including samples from the deep biosphere (ODP site 1227). For aprA quantification a Q-PCR assay was designed and evaluated. Depth profiles of the aprA and dsrA copy numbers were almost equal for all sites. Gene copy numbers decreased concomitantly with depth from around 10(8)/g sediment close to the sediment surface to less than 10(5)/g sediment at 5 mbsf. The 16S rRNA gene copy numbers of total bacteria were much higher than those of the functional genes at all sediment depths and used to calculate the proportion of SRP to the total Bacteria. The aprA and dsrA copy numbers comprised in average 0.5-1% of the 16S rRNA gene copy numbers of total bacteria in the sediments up to a depth of ca. 40 mbsf. In the zone without detectable sulfate in the pore water from about 40-121 mbsf (Peru margin ODP site 1227), only dsrA (but not aprA) was detected with copy numbers of less than 10(4)/g sediment, comprising ca. 14% of the 16S rRNA gene copy numbers of total bacteria. In this zone, sulfate might be provided for SRP by anaerobic sulfide oxidation. Clone libraries of aprA showed that all isolated sequences originate from SRP showing a close relationship to aprA of characterized species or form a new cluster with only distant relation to aprA of isolated SRP. For dsrA a high diversity was detected, even up to 121 m sediment depth in the deep biosphere.

  15. Real-time PCR quantification and diversity analysis of the functional genes aprA and dsrA of sulfate-reducing bacteria in marine sediments of the Peru continental margin and the Black Sea

    OpenAIRE

    Axel eSchippers; Anna eBlazejak

    2011-01-01

    A quantitative, real-time PCR (Q-PCR) assay for the functional gene adenosine 5´-phosphosulfate reductase (aprA) of sulfate-reducing bacteria (SRB) was designed. This assay was applied together with described Q-PCR assays for dissimilatory sulfite reductase (dsrA) and the 16S rRNA gene of total Bacteria to marine sediments from the Peru margin (0 – 121 meters below seafloor (mbsf)) and the Black Sea (0 – 6 mbsf). Clone libraries of aprA show that all isolated sequences originate from SRB...

  16. Precificação de consultoria empresarial com a contribuição das estratégias de apreçamento = Entrepreneurial Counseling Pricing with Pricing Strategy Contribution

    OpenAIRE

    Nivaldo João dos Santos; Erves Ducati; Antonio Cezar Bornia

    2008-01-01

    A precificação de serviços de consultoria também pode se beneficiar dos conceitos e idéias das estratégias de apreçamento de bens de consumo de massa, especificamente na área de consultoria de gestão empresarial. Apesar deste campo ser dominado por grandes corporações multinacionais, ainda existe espaço para empresas e profissionais nacionais. Por se tratar de mercado que envolve valores de grande magnitude, imaginasse que as instituições de sucesso adotem estratégia de apreçamento. Neste tra...

  17. Recovery of sludge from the treatment of liquid radioactive effluents by co-precipitation with calcium carbonate: laboratory study; Recuperation des boues de traitement des effluents radioactifs liquides par coprecipitation avec le carbonate de calcium: etude de laboratoire

    Energy Technology Data Exchange (ETDEWEB)

    Patti, F.; Gailledreau, C.; Cohen, P.

    1961-02-24

    As during the treatment by co-precipitation with calcium carbonate of liquid radioactive residues, a partial decontamination can be obtained by simply agitating an already formed radioactive sludge with the effluent to be processed, the authors study whether it would be possible to first perform a co-precipitation with a lower dose of calcium carbonate and then to complete decontamination by agitating with an adequate quantity of sludge stored during preceding operations. The authors report the study of the influence of reactant quantity on the chemical treatment efficiency, of the evolution of the activity of a radioactive residual solution in contact with a precipitate, of the cleaner element, of a precipitate reuse, of the technological and economic aspects, and of another possibility of reduction of the precipitate volume [French] Dans le traitement par coprecipitation avec le carbonate de calcium des residus radioactifs liquides, une decontamination partielle peut etre obtenue en agitant simplement une boue radioactive deja formee avec l'effluent a traiter. En consequence, il pourrait etre possible d'effectuer d'abord une coprecipitation avec une dose plus faible de carbonate de calcium et de completer ensuite la decontamination en agitant le liquide avec une quantite convenable de boue stockee a partir d'operations precedentes. (auteurs)

  18. La Greffe de Peau dans le Traitement des Sequelles de la Main Brulee. A Propos de 152 Cas - Experience du Service de Chirurgie Plastique du Centre Hospitalier Universitaire Ibn-Sina, Rabat, Maroc

    Science.gov (United States)

    El Mazouz, S.; Fejjal, N.; Hafidi, J.; Cherkab, L.; Mejjati, H.; Belfqih, R.; Gharib, N.; Abbassi, A.

    2010-01-01

    Summary La main est fréquemment exposée aux brûlures, entraînant des séquelles esthétiques et fonctionnelles. Le traitement de ces séquelles est surtout chirurgical et consiste en la greffe de peau, dont le type dépend de la localisation de la brûlure et du type des séquelles. Dans ce travail rétrospectif, nous rapportons une série de 152 cas de brûlures des mains colligés au service de chirurgie plastique du Centre Hospitalier Universitaire Ibn-Sina de Rabat sur une période de dix ans, allant de 1998 à 2007. Les indications thérapeutiques dépendent du type de séquelles et de la localisation de la brûlure. En tout, 97 patients ont bénéficié d'une greffe cutanée, dont 76% par greffe de peau totale, 21% par greffe de peau demi-épaisse et 3% par peau fine. Les séquelles des brûlures des mains posent un problème thérapeutique majeur, malgré la diversité des procédés chirurgicaux, d'où l'intérêt de la prévention. PMID:21991196

  19. Radiation protection measurements at Paks and its surroundings after the accident of the Chernobylsk nuclear power plant from 28 Apr 1986

    International Nuclear Information System (INIS)

    German, Endre; Kemenes, Laszlo; Rosa, Geza; Szabo, I.C.; Ormai, Peter; Ronaky, Jozsef; Divos, Ferenc; Varju, Bela; Horvath, Etelka.

    1986-08-01

    Experimental data on the contaminantion measured within a radius of 30 km from the Paks Nuclear Power Plant due to the accident of the Chernobylsk-4 reactor are given for the period between 28 Apr and 13 Jun 1986. Measurements on airborne and fallout activities, surface contamination of the ground, dose rates of γ radiation, activity concentration of the Danube, of milk, plant and food samples and the activity of human thyroid gland were carried out in the environmental control lab of the Paks NPP. According to the preliminary dose calculations the increment of the radiation exposure of the population is regarded to mount up to the average dose burden for half a year due to natural environmental radiation. (V.N.)

  20. The LasB Elastase of Pseudomonas aeruginosa Acts in Concert with Alkaline Protease AprA To Prevent Flagellin-Mediated Immune Recognition.

    Science.gov (United States)

    Casilag, Fiordiligie; Lorenz, Anne; Krueger, Jonas; Klawonn, Frank; Weiss, Siegfried; Häussler, Susanne

    2016-01-01

    The opportunistic pathogen Pseudomonas aeruginosa is capable of establishing severe and persistent infections in various eukaryotic hosts. It encodes a wide array of virulence factors and employs several strategies to evade immune detection. In the present study, we screened the Harvard Medical School transposon mutant library of P. aeruginosa PA14 for bacterial factors that modulate interleukin-8 responses in A549 human airway epithelial cells. We found that in addition to the previously identified alkaline protease AprA, the elastase LasB is capable of degrading exogenous flagellin under calcium-replete conditions and prevents flagellin-mediated immune recognition. Our results indicate that the production of two proteases with anti-flagellin activity provides a failsafe mechanism for P. aeruginosa to ensure the maintenance of protease-dependent immune-modulating functions. Copyright © 2015, American Society for Microbiology. All Rights Reserved.

  1. Identification of sulfur-cycle prokaryotes in a low-sulfate lake (Lake Pavin) using aprA and 16S rRNA gene markers.

    Science.gov (United States)

    Biderre-Petit, Corinne; Boucher, Delphine; Kuever, Jan; Alberic, Patrick; Jézéquel, Didier; Chebance, Brigitte; Borrel, Guillaume; Fonty, Gérard; Peyret, Pierre

    2011-02-01

    Geochemical researches at Lake Pavin, a low-sulfate-containing freshwater lake, suggest that the dominant biogeochemical processes are iron and sulfate reduction, and methanogenesis. Although the sulfur cycle is one of the main active element cycles in this lake, little is known about the sulfate-reducer and sulfur-oxidizing bacteria. The aim of this study was to assess the vertical distribution of these microbes and their diversities and to test the hypothesis suggesting that only few SRP populations are involved in dissimilatory sulfate reduction and that Epsilonproteobacteria are the likely key players in the oxidative phase of sulfur cycle by using a PCR aprA gene-based approach in comparison with a 16S rRNA gene-based analysis. The results support this hypothesis. Finally, this preliminary work points strongly the likelihood of novel metabolic processes upon the availability of sulfate and other electron acceptors.

  2. Syndrome parkinsonien secondaire à une maladie de Wilson chez ...

    African Journals Online (AJOL)

    Nous apportons une observation d'un cas de la maladie de Wilson, révélé par un syndrome parkinsonien. Le diagnostic a reposé sur les troubles neuropsychiques, la présence de l'anneau cornéen de Kayser-Fleischer, et les troubles du métabolisme du cuivre. Le scanner cérébral était normal, et l'IRM cérébrale a montré ...

  3. Effect of Decontamination of Feed Mixtures by Heat Treatment and Gamma Radiation on Growth and Feed Conversion in Fattening Pigs; Effet de la Decontamination de Melanges Alimentaires par Traitement Thermique et Irradiation Gamma sur la Croissance et sur la Conversion des Aliments Chez les Porcs d'Elevage; Vliyanie obezzarazhivaniya kormovykh smesej teplovoj obrabotkoj i gamma-oblucheniem na rost i.konversiyu pishchi u otkarmlivaemykh svinej; Efecto de la Descontaminacion por Tratamiento Termico e Irradiacion Gamma de Piensos Compuestos Sobre el Desarrollo y Engorde de Cerdos Cebones

    Energy Technology Data Exchange (ETDEWEB)

    Dammers, J.; Kampelmacher, E. H.; Edel, W.; Van Schothorst, M. [Research Institute for Animal Nutrition, Hoorn (Netherlands); National Institute of Public Health, Utrect (Netherlands)

    1966-11-15

    chaleur et le troisieme des aliments non traites. L'experience etait menee parallelement dans deux instituts differents, afin de tenir compte des facteurs geographiques, et portait donc sur un nombre total de 48 betes. Le traitement thermique a ete pratique a une temperature de 80 a 85 Degree-Sign C pendant 30 min. Les enterobacteriacees contenues dans les nourritures non traitees ont ete comptees; on en a trouvee 1,0 x 10{sup 5}/g. Apres les deux traitements de decontamination, on a preleve au hasard 30 echantillons de 50 g des produits traites et on a recherche les enterobacteriacees apres enrichissement. On a constate que cinq des echantillons traites par la chaleur et deux des echantillons irradies n'etaient pas entierement exempts de ces bacteries; toutefois, ces echantillons peuvent etre consideres comme suffisamment decontamines en ce qui concerne Salmonella. Dans l'un des instituts, les porcs ont ete engraisses pendant a peu pres 100 jours et ont atteint un poids d'environ 100 kg. La croissance moyenne par animal et par jour etait de 767 g pour le groupe alimente avec des nourritures non traitees, de 770 g pour le groupe engraisse avec des nourritures traitees par la chaleur, et de 800 g pour le groupe eleve avec des nourritures irradiees. La quantite de nourriture absorbee par kilogramme de croissance pour ces memes groupes etait de 2,85, 2,81 et 2,74 respectivement. Dans l'autre institut, les porcs ont ete engraisses pendant 155 jours environ et ont atteint un poids de pres de 116 kg. La croissance moyenne par animal et par jour etait de 627 g pour le groupe alimente avec de la nourriture non traitee, de 643 g pour le groupe alimente avec de la nourriture traitee par la chaleur, et de 625 g pour le groupe engraisse avec des aliments irradies. La quantite de nourriture absorbee par kilogramme d'accroissement ont ete pour ces differents groupes de 3,30, 3,23 et 3,24 kg respectivement. On peut conclure d'apres ces resultats que ni l'irradiation ni le traitement

  4. Precificação de consultoria empresarial com a contribuição das estratégias de apreçamento = Entrepreneurial Counseling Pricing with Pricing Strategy Contribution

    Directory of Open Access Journals (Sweden)

    Nivaldo João dos Santos

    2008-11-01

    Full Text Available A precificação de serviços de consultoria também pode se beneficiar dos conceitos e idéias das estratégias de apreçamento de bens de consumo de massa, especificamente na área de consultoria de gestão empresarial. Apesar deste campo ser dominado por grandes corporações multinacionais, ainda existe espaço para empresas e profissionais nacionais. Por se tratar de mercado que envolve valores de grande magnitude, imaginasse que as instituições de sucesso adotem estratégia de apreçamento. Neste trabalho, estratégias de apreçamento foram selecionadas para exame e verificação de aplicabilidade quando do estabelecimento valor pelos serviços da consultoria de gestão empresarial. O apreçamento de desnatação, apreçamento de penetração, apreçamento neutro e apreçamento baseado em valor tiveram seus conceitos sintetizados para fins de verificação. O apreçamento baseado em valor se revelou o mais propício para este tipo de produto (consultoria e o processo de comunicação é o elemento crítico para evidenciar valor, benefícios e, finalmente, justificar o preço do serviço. A sugestão de roteiro para apreçamento de serviço de consultoria empresarial é apresentada ao final, como resultado da análise das diversas estratégias de apreçamento.The pricing of counseling services may also benefit from strategy concepts and ideas ofmass consumption goods pricing, specifically within the entrepreneurial managementcounseling area. Even though this field has been taken over by big multinationalcorporations, there is still some space for national enterprisings and professionals. As itis a market that involves values of great magnitude, it is thought that successfulinstitutions adopt this pricing strategy. In this study, pricing strategies were selectedfor analysis and applicability checking by the time the price for entrepreneurialmanagement counseling service was established. The skimming pricing, penetratingpricing, neutral

  5. Les types d’arguments dans le traitement du débat sur la crise des banlieues par la télévision Types of Arguments Used on TV in the French Suburban Crisis Debate

    Directory of Open Access Journals (Sweden)

    Anne Kalinic

    2008-09-01

    Full Text Available Les émeutes de novembre 2005 survenues dans les banlieues françaises ont suscité un débat médiatisé à propos des causes de la crise et des modes d’intervention pour sa résolution. A travers son traitement discursif, le journal télévisé configure un cadrage du débat dans lequel les prises de position des différents acteurs interviewés viennent s’opposer. L’analyse des arguments des discours cités se décomposera sur les trois niveaux proposés par P. Charaudeau : problématisation, positionnement et probation, en tenant compte de leur valeur - par exemple, éthique, pragmatique ou émotionnelle - afin de dégager les différentes stratégies à visée persuasive.The October and November 2005 riots of the French suburbs, following the death of two teenagers chased by the police, have kindled a debate in the media on the causes of the crisis and the means used to resolve it. By its treatment of the question, TV discourse frames this debate, in which the stands of the various interviewed actors are in conflict. The analysis of the quoted arguments is performed on the three levels described by P. Charaudeau: “problematizing”, positioning, proving, while considering their value—for example, ethical, pragmatical or emotional—in order to find out the different strategies meant at persuading.

  6. Application de la théorie des graphes au traitement de la carte géologique Applying the Theory of Graphs to the Treatment of Geological Maps

    Directory of Open Access Journals (Sweden)

    Bouillé F.

    2006-11-01

    Full Text Available La saisie des informations d'une carte géologique par les méthodes classiques (grilles ou relevés aléatoires de courbes ne constitue pas une base de données opérationnelle. Par contre, l'assimilation des limites géologiques à un graphe orienté répond aux critères d'optimalité (encombrement très réduit, temps minimal, fiabilité, et permet une digitalisation rationnelle de la carte, une bonne structuration du fichier, et la réalisation d'applications intéressantes : restitutions graphiques sélectives à toutes échelles, calculs de pendages, surfaces, volumes, études de corrélation. Nous avons donc établi une chaîne de traitement de la carte géologique dont chaque maillon (saisie des informations; contrôle, mise à jour, consultation, application opère sur un ou plusieurs graphes. Obtaining data from geological maps by conventional methods (grids or random curve plotting is not an operational data base. However, the comparison of geological boundaries with a directional graph meets criteria of optimalness (very small bulk, minimum time, reliability and makes it possible to digitize the map rationally, to structure the file properly and to achieve significant applications such as selective graph plotting on all scales, calculating dips, areas and volumes, and making correlotion analyses. Therefore, we worked out a geological map processing sequence in which each element (data acquisition, checking, updating, consulting, applications operates on one or several graphs.

  7. Technical and Economic Problems Associated with the Development of Methods of Processing and Using Radioactive Waste; Problemes techniques et economiques lies au developpement des methodes de traitement et d'utilisation des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L; Sauteron, J; Oger, C [Commissariat a l' Energie Atomique, Fontenay-Aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The paper briefly reviews the various techniques used in processing the radioactive wastes which unavoidably result from the generation of electric power from nuclear sources. The paper goes on to define the relative importance, in nuclear fuel cycles, of the problem raised by these wastes. Emphasis is placed on the economic influence of management policies on the cost of power generation, and hence on the relative position of nuclear energy. A substantial percentage of these wastes can be economically utilized. Attention is drawn to the major technical and economic features of the industry which will come into being as a result of this utilization. The major uses anticipated are discussed: radiation sources, heat sources, auxiliary power generation. The paper concludes that satisfactory solutions have already been found to these problems, and describes possible improvements. (author) [French] La communication rappelle d'abord succinctement les differentes techniques de traitement des dechets radioactifs resultant necessairement de la production d'electricite d'origine nucleaire. On situe ensuite l'importance du probleme pose par ces residus dans le cycle du combustible nucleaire. On fait ressortir l'influence economique du choix des methodes de gestion sur le cout de production de l'energie, et par consequent sur la place devolue a l'energie nucleaire. Une part importante de ces dechets peut faire l'objet d'une utilisation rentable de l'industrie qui naitra de cette utilisation. Les principales applications envisagees sont evoquees: sources d'irradiation, sources chauffantes, generateurs auxiliaires d'energie. On conclut que d'ores et deja des solutions satisfaisantes ont ete apportees a ces problemes, et l'on decrit les perspectives d'amelioration concevables. (auteur)

  8. Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Park, Rae-Joon, E-mail: rjpark@kaeri.re.kr; Ha, Kwang-Soon; Rhee, Bo-Wook; Kim, Hwan Yeol

    2016-03-15

    Highlights: • Ex-vessel core catcher of PECS is installed in EU-APR1400. • CE-PECS has been conducted to test a cooling capability of the PECS. • Two phase flow in CE-PECS and PECS was analyzed using RELAP5/MOD3. • RELAP5 results are very similar to the CE-PECS data. • The super-step design is suitable for steam injection into the downcomer in PECS. - Abstract: The ex-vessel core catcher of the PECS (Passive Ex-vessel corium retaining and Cooling System) is installed to retain and cool down the corium in the reactor cavity of the EU (European Union)-APR (Advanced Power Reactor) 1400. A verification experiment on the cooling capability of the PECS has been conducted in the CE (Cooling Experiment)-PECS. Simulations of a two-phase natural circulation flow using the RELAP5/MOD3 computer code in the CE-PECS and PECS have been conducted to predict the two-phase flow characteristics, to determine the natural circulation mass flow rate in the cooling channel, and to evaluate the scaling in the experimental design of the CE-PECS. Particularly from a comparative study of the prototype PECS and the scaled test facility of the CE-PECS, the orifice loss coefficient in the CE-PECS was found to be 6 to maintain the coolant circulation mass flux, which is approximately 273.1 kg/m{sup 2} s. The RELAP5 results on the coolant circulation mass flow rate are very similar to the CE-PECS experimental results. An increase in the coolant injection temperature and the heat flux lead to an increase in the coolant circulation mass flow rate. In the base case simulation, a lot of vapor was injected into the downcomer, which leads to an instability of the two-phase natural circulation flow. A super-step design at a downcomer inlet is suitable to prevent vapor injection into the downcomer piping.

  9. Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

    International Nuclear Information System (INIS)

    Park, Rae-Joon; Ha, Kwang-Soon; Rhee, Bo-Wook; Kim, Hwan Yeol

    2016-01-01

    Highlights: • Ex-vessel core catcher of PECS is installed in EU-APR1400. • CE-PECS has been conducted to test a cooling capability of the PECS. • Two phase flow in CE-PECS and PECS was analyzed using RELAP5/MOD3. • RELAP5 results are very similar to the CE-PECS data. • The super-step design is suitable for steam injection into the downcomer in PECS. - Abstract: The ex-vessel core catcher of the PECS (Passive Ex-vessel corium retaining and Cooling System) is installed to retain and cool down the corium in the reactor cavity of the EU (European Union)-APR (Advanced Power Reactor) 1400. A verification experiment on the cooling capability of the PECS has been conducted in the CE (Cooling Experiment)-PECS. Simulations of a two-phase natural circulation flow using the RELAP5/MOD3 computer code in the CE-PECS and PECS have been conducted to predict the two-phase flow characteristics, to determine the natural circulation mass flow rate in the cooling channel, and to evaluate the scaling in the experimental design of the CE-PECS. Particularly from a comparative study of the prototype PECS and the scaled test facility of the CE-PECS, the orifice loss coefficient in the CE-PECS was found to be 6 to maintain the coolant circulation mass flux, which is approximately 273.1 kg/m"2 s. The RELAP5 results on the coolant circulation mass flow rate are very similar to the CE-PECS experimental results. An increase in the coolant injection temperature and the heat flux lead to an increase in the coolant circulation mass flow rate. In the base case simulation, a lot of vapor was injected into the downcomer, which leads to an instability of the two-phase natural circulation flow. A super-step design at a downcomer inlet is suitable to prevent vapor injection into the downcomer piping.

  10. Treatment of radiostrontium uptake in man; Traitement de la fixation de radiostrontium chez l'homme; Lechenie posledstvij pogloshcheniya radioaktivnogo strontsiya u cheloveka; Tratamiento de la radiotoxemla humana causada por absorcion de radioestroncio

    Energy Technology Data Exchange (ETDEWEB)

    Volf, V. [Department of Ionizing Radiation Institute of Industrial Hygiene and Occupational Disease, Prague, CSSR (Czech Republic)

    1963-02-15

    In short-term experiments on rats the passage of radioactive strontium through the intestinal wall was modified by oral treatment using barium sulphate and normal calcium phosphate. However, in rats on a diet containing barium sulphate there was no change in the absorption of Sr{sup 90} given in drinking water. It was concluded that this substance could be of value in first-aid treatment only. In two cases of slight internal contamination following accidental Sr{sup 90} nitrate inhalation, barium sulphate (Skiabaryum Spofa) was administered orally within 10 and 30 min after the inhalation of Sr{sup 90}. The effectiveness of this treatment was tested in model experiments on rats performed under similar conditions as in the accidents. More recently, experiments on similar lines have been carried out on several cancer patients, in order to investigate further possibilities of first-aid treatment following acute internal radiostrontium contamination in man. (author) [French] Dans des experiences de breve duree sur les rats, le passage de radiostrontium a travers la paroi de l'intestin etait modifie par l'administration par voie buccale de sulfate de baryum et de phosphate de calcium normal. Toutefois, chez des rats dont le regime alimentaire contenait du sulfate de baryum, il n'y a pas eu de modification de l'absorption de {sup 90}Sr melange a l'eau de boisson. On en conclut que cette substance ne peut etre utile que pour un traitement de premiere urgence. Dans deux cas de legere contamination interne par inhalation accidentelle de {sup 90}Sr sous forme de nitrate, on a administre du sulfate de baryum (Skiabaryum Spofa) par voie buccale dans les 10 et les 30 min qui ont suivi l'inhalation de {sup 90}Sr. L'efficacite de ce traitement a ete etudiee au cours d'experiences temoins effectuees sur des rats dans des conditions identiques a celles des accidents. Plus recemment, on a procede a des experiences analogues sur plusieurs cancereux en vue de trouver d

  11. Extension of Surveillance Test Interval of Safety Injection Pump for APR-1400 Reactors to Improve Reliability and Availability of the Pump

    Energy Technology Data Exchange (ETDEWEB)

    Osama, A. Rezk; Jung, J. C.; Lee, Yong-Kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    The safety features function to localize, control, mitigate, and terminate such incidents and to hold exposure levels below applicable limits. The safety injection system is comprised of four independent mechanical trains without any tie line among the injection paths and two electrical divisions. Each train has one active Safety Injection Pump (SIP) and one passive Safety Injection Tank (SIT) equipped with a Fluidic Device (FD), each train provides 50% of the minimum injection flow rate for breaks larger than the size of a direct vessel injection line. For breaks equal to or smaller than the size of a direct vessel injection line, each train has 100% of the required capacity. The low pressure injection pumps with common header installed in the conventional design are eliminated, and the functions for safety injection and shutdown cooling are separated. The arrangement of safety injection system for APR-1400 as shown in figure (1). The results obtained in this work show that STI extensions for the SIS feasible without any unacceptable increase in the plant total risk, STI extensions are acceptable for safety injection system to provide plant operational flexibility in the performance of both corrective and preventive maintenance for the safety injection system.

  12. Impaired epithelial differentiation of induced pluripotent stem cells from ectodermal dysplasia-related patients is rescued by the small compound APR-246/PRIMA-1MET.

    Science.gov (United States)

    Shalom-Feuerstein, Ruby; Serror, Laura; Aberdam, Edith; Müller, Franz-Josef; van Bokhoven, Hans; Wiman, Klas G; Zhou, Huiqing; Aberdam, Daniel; Petit, Isabelle

    2013-02-05

    Ectodermal dysplasia is a group of congenital syndromes affecting a variety of ectodermal derivatives. Among them, ectrodactyly, ectodermal dysplasia, and cleft lip/palate (EEC) syndrome is caused by single point mutations in the p63 gene, which controls epidermal development and homeostasis. Phenotypic defects of the EEC syndrome include skin defects and limbal stem-cell deficiency. In this study, we designed a unique cellular model that recapitulated major embryonic defects related to EEC. Fibroblasts from healthy donors and EEC patients carrying two different point mutations in the DNA binding domain of p63 were reprogrammed into induced pluripotent stem cell (iPSC) lines. EEC-iPSC from both patients showed early ectodermal commitment into K18(+) cells but failed to further differentiate into K14(+) cells (epidermis/limbus) or K3/K12(+) cells (corneal epithelium). APR-246 (PRIMA-1(MET)), a small compound that restores functionality of mutant p53 in human tumor cells, could revert corneal epithelial lineage commitment and reinstate a normal p63-related signaling pathway. This study illustrates the relevance of iPSC for p63 related disorders and paves the way for future therapy of EEC.

  13. L'endométriose pariétale cicatricielle après césarienne: une entité rare

    Science.gov (United States)

    El Fahssi, Mohammed; Lomdo, Massama; Bounaim, Ahmed; Ali, Abdelmounaim Ait; Sair, Khalid

    2016-01-01

    L'endométriose de la paroi est une entité clinique rare, dont la physiopathologie demeure imprécise. Elle survient le plus souvent après une intervention chirurgicale gynécologique ou obstétricale. Nous rapportons le cas d'une patiente présentant une douleur cyclique, au niveau de la cicatrice de césarienne, Avec à l'examen clinique une masse de 5cm localisée au niveau de la fosse iliaque droite. la tomodensitométrie montre une masse de densité tissulaire de 45mm de grand axe. D'où la décision d'excision large de la lésion dont l’étude anatomopathologique confirme le diagnostic d'endométriose pariétale. Les suites postopératoires étaient simples avec un recul de 20 mois sans récidive de la masse ni de la douleur. A travers notre cas, nous insisterons sur les caractéristiques de cette pathologie, ce qui permettra au praticien de comprendre l'intérêt du diagnostic et de la prise en charge précoce de cette affection ainsi que la possibilité de sa prévention au cours de chaque chirurgie gynécologique ou obstétricale. PMID:27642418

  14. Liquid entrainment and off-take at the top of the pressurizer in the case of the actuation of safety depressurization system of APR1400

    International Nuclear Information System (INIS)

    Kim, Chang Hyun; No, Hee Cheon

    2003-01-01

    In order to determine the bleed capacity of Safety Depressurization System (SDS) of Advanced Power Reactor 1400 (APR1400) in case of Total Loss of Feed Water (TLOFW), we performed an experimental study of liquid entrainment and liquid off-take from the swelled two-phase mixture surface in a vessel. A total of 208 experimental data on the entrainment and off-take are obtained using a test vessel with the height of 2.0m and the inner diameter of 0.3m having a top break with diameter of 0.05m. Two-phase mixture levels are measured by the ultrasonic sensor within ? .77% with respect to the visual level data. Droplet entrainments are measured and compared with the existing pool entrainment data. The empirical correlation for the onset of off-take is developed in terms of the Froude number (Fr g ) at the break and non-dimensional inception height (h b /d). This correlation shows agreement with the present experimental data within ? 5%. The present off-take quality data is in agreement with Schrock's off-take quality correlation with the r.m.s. error of 15.8%. In the present experiment, droplet entrainment E fg strongly depends upon jg * /h * and is proportional to the 7 th power of jg * /h * in the same way as the off-take data

  15. Development of a system for a linked analysis of RELAP5 and MAAP4 and its application for an analysis of LB-LOCA case of APR1400

    International Nuclear Information System (INIS)

    Park, Chang Hwan; Lee, Un Chul; Park, Goon Cherl; Suh, Kune Yull

    2004-01-01

    The RELAP5 (1995) and MAAP4 (1994) linked-analysis system was designed and illustrative calculation was performed. A large-break loss-of-coolant accident (LBLOCA) was taken as the reference case for the APR1400 (Advanced Power Reactor 1400MWe). For the early phase of this case, the calculational results of two codes have some deviations in water level depletion and hot assembly temperature. Ordinarily, it is considered that RELAP5 has enough accuracy in calculation of the thermal hydraulic behavior of typical PWR during design basis accidents. If the data set for the thermal hydraulic state of RELAP5 can be well-transferred to MAAP4 as an initial condition, the overall transients given by the linked analysis can get more reliability. In this study, the linked analysis system of RELAP5 and MAAP4 doesn't mean the mechanically integrated code structure. The objective of this study is to formulate the linked analysis system of RELAP5 and MAAP4, which should precede construction of mechanically integrated analyzer. Thus, the main scope of this work covers development of the methodology for data linkage and decision of the transfer timing

  16. Folate, vitamin B12, and vitamin B6 status of a group of high socioeconomic status women in the Alberta Pregnancy Outcomes and Nutrition (APrON) cohort.

    Science.gov (United States)

    Fayyaz, Faiqa; Wang, Flora; Jacobs, René L; O'Connor, Deborah L; Bell, Rhonda C; Field, Catherine J

    2014-12-01

    Folic acid supplementation and food fortification policies have improved folate status in North American women of child bearing age. Recent studies have reported the possible inadequacy of vitamin B12 and B6 in the etiology of neural tube defects in folate-fortified populations. The aims of this study were to describe folate status and its relationship to supplementation and to assess vitamin B12 and B6 status in a cohort of pregnant women. Supplement intake data were collected in each trimester from the first cohort (n = 599) of the Alberta Pregnancy Outcomes and Nutrition (APrON) study. Red blood cell folate (RBCF) and plasma folate, holotranscobalamin, and pyridoxal 5-phosphate were measured. Overt folate deficiency was rare (3%) but 24% of women in their first trimester had suboptimal RBCF concentration (1360 nmol·L(-1)) was observed in approximately half of the women during each pregnancy trimester. Vitamin B12 and B6 deficiencies were rare (pregnancy and over half the women had abnormally high RBCF, suggesting that supplementation during pregnancy is not appropriate in a cohort of women considered to be healthy and a low risk for nutritional deficiencies.

  17. A study on Requirements of Data Base Translator for APR1400 Computerized Procedure System at Shin-Hanul unit 1 and 2

    International Nuclear Information System (INIS)

    Seong, Nokyu; Lee, Sungjin

    2015-01-01

    The CPS is one of the Man Machine Interface (MMI) resources and the CPS can directly display plant graphic objects which are in the Digital Control System (DCS). And the CPS can send a request to DCS to provide DCS screen which is called step support display through DCS link button on a computerized procedure. The procedure writers can insert DCS graphic information to computerized procedure through data base which is provided by CPS Editing System (CPSES). The data base which is provided by CPSES conforms to the naming rule of DCS graphic objects. The naming rule of DCS graphic objects is defined by vendor thus status of DCS graphic objects which are in computerized procedure at Shin-Kori plant cannot be displayed on CPS at Shin-Hanul plant. To use computerized procedure which is written by other plant procedure writer, DCS graphic objects shall be translated by its plant data base. This paper introduces requirements of data base translator to reduce translation and re-inserting graphic objects burden. This paper introduces the requirements of data base translator of CPSES for APR1400 CPS at Shin-Hanul unit 1 and 2. The translator algorithms shall be tested to update data base of CPSES effectively. The prototype of translator is implemented and is being tested using real plant DB. This translator can be applied to Shin- Hanul unit1 and 2 through software V and V

  18. A study on Requirements of Data Base Translator for APR1400 Computerized Procedure System at Shin-Hanul unit 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Seong, Nokyu; Lee, Sungjin [KHNP, Daejeon (Korea, Republic of)

    2015-05-15

    The CPS is one of the Man Machine Interface (MMI) resources and the CPS can directly display plant graphic objects which are in the Digital Control System (DCS). And the CPS can send a request to DCS to provide DCS screen which is called step support display through DCS link button on a computerized procedure. The procedure writers can insert DCS graphic information to computerized procedure through data base which is provided by CPS Editing System (CPSES). The data base which is provided by CPSES conforms to the naming rule of DCS graphic objects. The naming rule of DCS graphic objects is defined by vendor thus status of DCS graphic objects which are in computerized procedure at Shin-Kori plant cannot be displayed on CPS at Shin-Hanul plant. To use computerized procedure which is written by other plant procedure writer, DCS graphic objects shall be translated by its plant data base. This paper introduces requirements of data base translator to reduce translation and re-inserting graphic objects burden. This paper introduces the requirements of data base translator of CPSES for APR1400 CPS at Shin-Hanul unit 1 and 2. The translator algorithms shall be tested to update data base of CPSES effectively. The prototype of translator is implemented and is being tested using real plant DB. This translator can be applied to Shin- Hanul unit1 and 2 through software V and V.

  19. Japānas un Amerikas Savienoto Valstu kauja par Okinavu 1945. gada: 1.aprīlis – 22. jūnijs

    OpenAIRE

    Leimanis, Normunds

    2017-01-01

    Bakalaura darba tēmas nosaukums ir „Japānas un Amerikas Savienoto Valstu kauja par Okinavu 1945. gada: 1. aprīlis – 22. jūnijs ”. Tā ir viena no lielākajām un asiņainākajām kaujām, kura notika Otrā Pasaules kara laika beigās. Tā bija viena no pēdējām kaujām Otrā Pasaules kara laikā. Kaujā par Okinavu piedalijās amerikāņu un japāņu karaspēki, kas cīnījās par savu valsti un tās godu. Galvenie Okinavas kaujas dalībnieki bija japāņu 32. armija un amerikāņu 10.armija. Galvenais atbildīgais par ...

  20. After Arizona: Military Musicians in the Second World War Après Arizona: les musiciens dans la marine américaine pendant la Seconde Guerre mondiale

    Directory of Open Access Journals (Sweden)

    Rosemary Peters

    2012-03-01

    Full Text Available Cet article traite du rôle des musiciens dans la marine américaine pendant la Seconde Guerre mondiale. L’histoire de l’USS Arizona — et de son orchestre, noyé avec le cuirassé lors de l’attaque surprise des forces japonaises — étant bien connue, je m’appuie sur cet exemple comme point de départ afin de contextualiser la situation des musiciens militaires après les événements de Pearl Harbor, en décembre 1941. Dans le sillage de ce grand moment de l’Histoire, j’évoque ici des histoires à une autre échelle, celle de la « micro-histoire »— celle d’un militaire seul au milieu d’autres militaires. À travers les lettres échangées entre des recrues ayant suivi ensemble la même formation, je trace ici leurs expériences de guerre en tant qu’artistes, ainsi que les divers conflits pratiques et idéologiques qui se manifestent dans la tension entre l’art musical et l’art martial.

  1. Measurement of the dead time of a G.M. counter and of the secondary emission of the cathode by the method of the delayed coincidences; Mesure du temps mort d'un compteur G.M. et de l'emission secondaire de la cathode par la methode des coincidences retardees

    Energy Technology Data Exchange (ETDEWEB)

    Picard, E; Rogozinski, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1953-07-01

    The dead time of a G.M counter is measured with the method of delayed coincidences. The pulses of the counter that supplies the circuit of coincidences, arrive there, on the one hand, directly, and in the other part, after a known and variable delay. This method permits besides, to study the parasitic impulses coming from the impact of the positive ions on the cathode of the meter. From the results relative to several counters working in various conditions are given. (author) [French] Le temps mort d'un compteur G.M. est mesure a l'aide d'un methode de coincidences retardees. Les impulsions du compteur qui alimentent le circuit de coincidences, y parviennent, d'une part, directement, et, dautre part, apres un retard connu et variable. Cette methode permet de plus, d'etudier les impulsions parasites provenant de l'impact des ions positifs sur la cathode du compteur. Des resultats relatifs a plusieurs compteurs fonctionnant dans des conditions diverses sont donnes. (auteur)

  2. Case report

    African Journals Online (AJOL)

    ebutamanya

    1 oct. 2015 ... Les troubles de l'hémostase secondaires à une LV ou à un SAM sont fréquents, mais la survenue d'une coagulation intra-vasculaire disséminée (CIVD) est peu rapportée [3, 4]. Le traitement de la LV par Glucantime® peut être responsable de plusieurs effets indésirables ; la survenue d'une pancréatite est ...

  3. Case series

    African Journals Online (AJOL)

    ebutamanya

    4 sept. 2015 ... rapport avec la stase urinaire (infection urinaire, lithiase vésicale). [12] des complications plus rares ont été rapportées telles que la survenue d'une tumeur vésicale intraherniaire [13] ou une insuffisance rénale secondaire à la compression du trigone [5]. En cas de diagnostic pré-opératoire le traitement ...

  4. Study of the retention of fission products by a few common minerals. Application to the treatment of medium activity effluents (1962); Etude de la retention des produits de fission par quelques mineraux usuels. Application aux traitements d'effluents de moyenne activite specifique (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1962-07-01

    The conditions in which strontium is fixed on calcite (the object of the Geneva report P/395 - USA - 1958) are more closely studied and the work is extended to five fission products present in the effluents, and to 17 common rocks and minerals. Although as it turns out this fixation is not suitable as a method of treating the S.T.E. effluents (i.e. those from the Effluent Treatment plant at Marcoule), the study shows that all the crystals considered are strongly contaminated by simple contact with the effluents. (author) [French] Les conditions de fixation du strontium sur la calcite (objet du rapport de Geneve P/395 - USA - 1958) sont approfondies et l'etude est etendue aux cinq produits de fission presents dans les effluents et a 17 roches et minerais courants. Bien qu'en definitive cette fixation se revele inutilisable comme procede de traitement d'effluents S.T.E. (Station de Traitement des Effluents, Marcoule), l'etude montre que tous les cristaux consideres se contaminent fortement par simple contact avec les effluents. (auteur)

  5. Análise do efeito não linear do patrimônio líquido no apreçamento de fundos de investimento em ações

    Directory of Open Access Journals (Sweden)

    Paulo Rogério Faustino Matos

    2012-01-01

    Full Text Available Este artigo faz uso do Capital Asset Pricing Model (CAPM, em sua versão canônica e com extensões não lineares, visando a apreçar um painel de 75 fundos de investimento em ações no Brasil, ao longo dos últimos 11 anos. O resultado sugere que a versão linear desse arcabouço não seja capaz de apreçar ou de prever retornos reais de fundos que possuam elevados patrimônio líquido (PL e outperformance, em relação ao índice da Bolsa de Valores de São Paulo (Ibovespa, corroborando evidências anteriores. A versão não linear com thresholds baseados no PL parece lidar melhor com a questão de alfas de Jensen significativos, apesar de ser estatisticamente indicada apenas para poucos fundos com elevado PL, mas baixa outperformance. Essa é uma evidência de que, apesar de o tamanho influenciar na gestão e, possivelmente, na performance de um fundo, a modelagem de apreçamento desse efeito deve ser feita linearmente.

  6. Etude des facteurs liés à l'observance au traitement antirétroviral chez les patients suivis à l'Unité de Prise En Charge du VIH/SIDA de l'Hôpital de District de Dschang, Cameroun

    Science.gov (United States)

    Mbopi-Kéou, François-Xavier; Dempouo Djomassi, Lucienne; Monebenimp, Francisca

    2012-01-01

    Introduction Etudier les facteurs liés à l'observance au traitement antirétroviral chez les patients adultes suivis à l'Unité de Prise en Charge du VIH/SIDA (UPEC) de l'hôpital de District de Dschang. Méthodes Dans une étude descriptive transversale conduite à l'hôpital de District de Dschang, l'observance a été évaluée sur la base des déclarations des patients et sur la régularité du renouvellement de leurs ordonnances (observance calculée). Résultats Parmi les 389 patients répondant à nos critères d'inclusion, 356 ont été interrogés. La durée moyenne du suivi était de 27 mois. La moyenne d’âge était égale à 41 ans et le sexe ratio 2,46 en faveur du sexe féminin. Le statut sérologique était découvert pour 60,56% des patients à l'occasion d'un épisode maladif. Le niveau d'observance déclarée était significativement plus élevé que le niveau global de l'observance calculée (80,2% vs 51,5%, p<10−5). Les deux principales barrières à l'observance étaient l'oubli et le travail. Les patients référés dans cette UPEC étaient moins bien observants (p<10−4). L'observance au traitement antirétroviral était d'autant meilleure quand le taux de CD4 en début de traitement était élevé (p= 0,01) et que la durée du traitement était prolongée (p=0,00). Conclusion La discordance observée entre les résultats des deux méthodes utilisées pour estimer l'observance, tout en soulévant les contraintes liées à l’évaluation de l'observance thérapeutique, souligne l'importance des méthodes biologiques. Les facteurs individuels se sont avérés être les principales raisons de non-observance. Enfin, un accent devrait être mis sur les consultations d’éducation thérapeutique et le suivi psycho-social des patients sous traitement antirétroviral dans cette UPEC. PMID:22937195

  7. Processing radioactive effluents with ion-exchanging resins: study of result extrapolation; Traitement des effluents radioactifs par resines echangeuses d'ions: etude de l'extrapolation des resultats

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1960-05-03

    As a previous study showed the ion-exchanging resins could be used in Saclay for the treatment of radioactive effluents, the author reports a study which aimed at investigating to which extent thus obtained results could be extrapolated to the case of higher industrial columns. The author reports experiments which aimed at determining extrapolation modes which could be used for columns of organic resin used for radioactive effluent decontamination. He notably studied whether the Hiester and Vermeulen extrapolation law could be applied. Experiments are performed at constant percolation flow rate, at varying flow rate, and at constant flow rate [French] Plusieurs etudes ont ete faites dans le but d'examiner les possibilites d'emploi des resines echangeuses d'ions pour le traitement des effluents radioactifs. Dans un rapport preliminaire, nous avons montre dans quelles limites un tel procede pouvait etre utilise au Centre d'Etudes Nucleaires de Saclay. Les essais ont ete effectues sur des petites colonnes de resine au laboratoire; il est apparu ensuite necessaire de prevoir dans quelle mesure les resultats ainsi obtenus peuvent etre extrapoles a des colonnes industrielles, de plus grande hauteur. Les experiences dont les resultats sont exposes dans ce rapport, ont pour but de determiner les modes d'extrapolation qui pourraient etre employes pour des colonnes de resine organique utilisees pour la decontamination d'effluents radioactifs. Nous avons en particulier recherche si la loi d'extrapolation de Hiester et Vermeulen qui donne de bons resultats dans le cas de fixation d'ions radioactifs en presence d'un ion macrocomposant sur des terres, pouvait etre appliquee. Les experiences, en nombre limite, ont montre que la loi d'extrapolation de Hiester et Vermeulen pouvait s'appliquer dans le cas de l'effluent considere quand les debits de percolation sont tres faibles; quand ils sont plus forts, les volumes de liquide percoles, a fixation egale, sont proportionnels aux

  8. Risk Analysis of Flare Flame-out Condition in a Gas Process Facility Analyse des risques des conditions d’extinction de torche au sein d’une installation de traitement de gaz

    Directory of Open Access Journals (Sweden)

    Zadakbar O.

    2011-02-01

    Full Text Available Flaring is a common method of disposal of flammable waste gases in the downstream industries. Flare flame out (flame lift-off or blow-outs often occurs causing toxic vapors to discharge. The toxic gases released may have hazardous effects on the surrounding environment. To study the effect of inhalation exposure of these toxic gases on human health, the four steps of the EPA (Environmental Protection Agency framework with the field data to quantify the cancer and non-cancer health risks are integrated in this paper. As a part of exposure assessment, gas dispersion modeling using AERMOD and UDM-PHAST is applied in two different conditions of normal flaring and flare flame out during a particular climate condition in Khangiran region. Recommendations to avoid flare flame out conditions are also presented here. Le torchage est un procédé courant d’élimination des gaz résiduaires inflammables dans les industries de traitement. L’extinction de la torche (par décollage ou soufflage de flamme provoque souvent une émission de vapeurs toxiques. Ces gaz toxiques libérés peuvent présenter des effets dangereux sur le milieu environnant. Pour étudier l’effet d’une exposition par inhalation de ces gaz toxiques sur la santé, cet article croise les quatre étapes de la démarche de l’EPA (Environmental Protection Agency, Agence de protection de l’environnement avec les données d’exploitation afin de quantifier le risque sanitaire cancérologique et non cancérologique. Dans le cadre de l’estimation d’exposition, une modélisation de dispersion des gaz utilisant AERMOD et UDM-PHAST est évaluée dans deux configurations différentes de torchage normal et d’extinction de torche à l’occasion de conditions climatiques particulières dans la région du Khangiran. L’article propose également des recommandations destinées à éviter les conditions d’une extinction de flamme de torche.

  9. Use of X-ray fluorescence in a laboratory for the treatment of uranium ores (1960); Utilisation de la fluorescence X dans un laboratoire de traitements de minerais d'uranium (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    A brief description will be given of some aspects of the experience gained over a year during which X-ray fluorescence was used at the laboratory or the present Section Autonome d'Etudes, Recherches et Applications Chimiques of the Commissariat a l'Energie Atomique. First part. - Reproducibility of results. A standard is tested daily. The observations made during the months from december 58 to may 59 are described. Second part. - Study of two chemical treatment processes using X-ray fluorescence, without development of a detailed method of analysis. a) Acid lixiviation of uranium ores. The residues are analysed by X-Ray fluorescence directly in powder form. b) Fixation and elution of vanadium on ion exchange resin. Third part. - Method for the quantitative analysis of the uranium in solution. A method of analysis of the uranium in solution is described for concentrations between 30 {gamma}/cc and 600 {gamma}/cc, whatever may be the impurities present (except for the elements between Zn and Rb, and between Ir and Pa). (author) [French] On se propose de decrire brievement quelques aspects de l'experience acquise en une annee d'utilisation de fluorescence X au laboratoire de l'actuelle Section Autonome d'Etudes, Recherches et Applications chimiques du Commissariat a l'Energie Atomique. Premiere Partie. - Etude de la reproductibilite des resultats. Un standard est teste quotidiennement. On donne la description des observations faites durant les mois de decembre 58 a mai 59. Deuxieme Partie. - Etude de deux procedes de traitements chimiques au moyen de la fluorescence X sans mise au point de methode d'analyse elaboree. a) Liziviation acide de minerais d'uranium. Les residus sont analyses par fluorescence X directement sous forme pulverulente. b) Fixation et elution du vanadium sur resine echangeuse d'ions. Troisieme partie. - Methode d'analyse quantitative de l'uranium en solution. On decrit une methode d'analyse de l'uranium en solution pour des concentrations allant

  10. Traitement des séquelles de brûlures de la main dans les pays à ressources limitées ; notre expérience en république démocratique du Congo

    Science.gov (United States)

    Kibadi, K.; Moutet, F.

    2015-01-01

    Summary Les séquelles de brûlures de la main sont encore fréquentes dans les pays à ressources limitées. Trente-deux patients, représentant 38 mains, ont été admis et traités, entre le 1er décembre 2010 et le 1er mai 2014 aux Cliniques Universitaires de Kinshasa en République Démocratique du Congo (RDC). nous avons observé 22 patients (69 %) dans le groupe de jeunes (patients âgés de moins de 18 ans), et 10 patients (31 %) chez les adultes (18 à 59 ans). Aucun patient dans le groupe de seniors (60 ans et plus) n’a été observé. Dans le groupe de jeunes, la tranche d’âge de 1 à 5 ans a été la plus atteinte avec 13 malades (40 %). l’accident à la maison était le plus fréquent (72 %). le mécanisme de la brûlure était le plus souvent thermique par flammes (51 %) ou par liquide chaud (34 %). les rétractions et brides sont les lésions le plus observées (84 %). la rétraction dorsale globale « main en griffe» est observée chez 40 % de patients traités, associée à des cicatrices hypertrophiques et chéloïdiennes dans 84 % de cas. Chez les 32 mains traitées chirurgicalement, des excision-greffes ont été réalisées dans 43,7 %, des lambeaux locaux dans 43,7 % et des lambeaux à distance dans 12,5 % de cas. A la sortie de l’hôpital, 84 % de « bons » résultats ont été observés. le suivi a été de 18 mois. le traitement des séquelles de brûlures de la main est possible dans ces pays, exemple de la rDC. Mais les défis à surmonter dans ces pays sont nombreux : la faible accessibilité aux techniques actuelles de la chirurgie plastique, la prise en charge initiale inadéquate des brûlures, la pauvreté. PMID:26668560

  11. A Study on Large Display Panel Design for the Countermeasures against Team Errors within the Main Control Room of APR-1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sa Kil; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The personal aspect of human errors has been mainly overcome by virtue of the education and training. However, in the system aspect, the education and training system needs to be reconsidered for more effective reduction of human errors affected from various systems hazards. Traditionally the education and training systems are mainly not focused on team skills such as communication, situational awareness, and coordination, etc. but individual knowledge, skill, and attitude. However, the team factor is one of the crucial issues to reduce the human errors in most industries. In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Team error is one of the typical organizational errors that may occur during performing operations in nuclear power plants. The large display panel is a representative feature of digitalized control room. As a group-view display, the large display panel provides plant overview to the operators. However, in terms of team performance and team errors, the large display panel is on a discussion board still because the large display panel was designed just a concept of passive display. In this study, we will propose revised large display panel which is integrated with several alternative interfaces against feasible team errors.

  12. Use of micronutrient supplements among pregnant women in Alberta: results from the Alberta Pregnancy Outcomes and Nutrition (APrON) cohort.

    Science.gov (United States)

    Gómez, Mariel Fajer; Field, Catherine J; Olstad, Dana Lee; Loehr, Sarah; Ramage, Stephanie; McCargar, Linda J

    2015-10-01

    Maternal nutrient intake in the prenatal period is an important determinant of fetal growth and development and supports maternal health. Many women, however, fail to meet their prenatal nutrient requirements through diet alone and are therefore advised to consume nutrient supplements. The purpose of this study was to describe the use of natural health products (NHP) by pregnant women in each trimester of pregnancy. Women (n = 599) participating in the first cohort of the Alberta Pregnancy Outcomes and Nutrition (APrON) study completed an interviewer-administered supplement intake questionnaire during each trimester of pregnancy. NHP use was high, with >90% taking multivitamin/mineral supplements, and nearly half taking at least one additional single-nutrient supplement. Compliance with supplementation guidelines was high for folic acid (>90%), vitamin D (∼70%) and calcium (∼80%), but low for iron (<30%) and for all four nutrients together (≤11%). On average, women met or exceeded the recommended dietary allowance for folic acid, vitamin D and iron from NHPs alone, with median daily intakes of 1000 μg, 400 IU and 27 mg, respectively. The median calcium intake was 250 mg d(-1) . Up to 26% of women exceeded the tolerable upper intake level for folic acid and up to 19% did so for iron at some point of their pregnancy. Findings highlight the need to consider both dietary and supplemental sources of micronutrients when assessing the nutrient intakes of pregnant women. © 2013 John Wiley & Sons Ltd.

  13. Coadministration of Hedera helix L. Extract Enabled Mice to Overcome Insufficient Protection against Influenza A/PR/8 Virus Infection under Suboptimal Treatment with Oseltamivir.

    Science.gov (United States)

    Hong, Eun-Hye; Song, Jae-Hyoung; Shim, Aeri; Lee, Bo-Ra; Kwon, Bo-Eun; Song, Hyuk-Hwan; Kim, Yeon-Jeong; Chang, Sun-Young; Jeong, Hyeon Gun; Kim, Jong Geal; Seo, Sang-Uk; Kim, HyunPyo; Kwon, YongSoo; Ko, Hyun-Jeong

    2015-01-01

    Several anti-influenza drugs that reduce disease manifestation exist, and although these drugs provide clinical benefits in infected patients, their efficacy is limited by the emergence of drug-resistant influenza viruses. In the current study, we assessed the therapeutic strategy of enhancing the antiviral efficacy of an existing neuraminidase inhibitor, oseltamivir, by coadministering with the leaf extract from Hedera helix L, commonly known as ivy. Ivy extract has anti-inflammatory, antibacterial, antifungal, and antihelminthic properties. In the present study, we investigated its potential antiviral properties against influenza A/PR/8 (PR8) virus in a mouse model with suboptimal oseltamivir that mimics a poor clinical response to antiviral drug treatment. Suboptimal oseltamivir resulted in insufficient protection against PR8 infection. Oral administration of ivy extract with suboptimal oseltamivir increased the antiviral activity of oseltamivir. Ivy extract and its compounds, particularly hedrasaponin F, significantly reduced the cytopathic effect in PR8-infected A549 cells in the presence of oseltamivir. Compared with oseltamivir treatment alone, coadministration of the fraction of ivy extract that contained the highest proportion of hedrasaponin F with oseltamivir decreased pulmonary inflammation in PR8-infected mice. Inflammatory cytokines and chemokines, including tumor necrosis factor-alpha and chemokine (C-C motif) ligand 2, were reduced by treatment with oseltamivir and the fraction of ivy extract. Analysis of inflammatory cell infiltration in the bronchial alveolar of PR8-infected mice revealed that CD11b+Ly6G+ and CD11b+Ly6Cint cells were recruited after virus infection; coadministration of the ivy extract fraction with oseltamivir reduced infiltration of these inflammatory cells. In a model of suboptimal oseltamivir treatment, coadministration of ivy extract fraction that includes hedrasaponin F increased protection against PR8 infection that could be

  14. Coadministration of Hedera helix L. Extract Enabled Mice to Overcome Insufficient Protection against Influenza A/PR/8 Virus Infection under Suboptimal Treatment with Oseltamivir.

    Directory of Open Access Journals (Sweden)

    Eun-Hye Hong

    Full Text Available Several anti-influenza drugs that reduce disease manifestation exist, and although these drugs provide clinical benefits in infected patients, their efficacy is limited by the emergence of drug-resistant influenza viruses. In the current study, we assessed the therapeutic strategy of enhancing the antiviral efficacy of an existing neuraminidase inhibitor, oseltamivir, by coadministering with the leaf extract from Hedera helix L, commonly known as ivy. Ivy extract has anti-inflammatory, antibacterial, antifungal, and antihelminthic properties. In the present study, we investigated its potential antiviral properties against influenza A/PR/8 (PR8 virus in a mouse model with suboptimal oseltamivir that mimics a poor clinical response to antiviral drug treatment. Suboptimal oseltamivir resulted in insufficient protection against PR8 infection. Oral administration of ivy extract with suboptimal oseltamivir increased the antiviral activity of oseltamivir. Ivy extract and its compounds, particularly hedrasaponin F, significantly reduced the cytopathic effect in PR8-infected A549 cells in the presence of oseltamivir. Compared with oseltamivir treatment alone, coadministration of the fraction of ivy extract that contained the highest proportion of hedrasaponin F with oseltamivir decreased pulmonary inflammation in PR8-infected mice. Inflammatory cytokines and chemokines, including tumor necrosis factor-alpha and chemokine (C-C motif ligand 2, were reduced by treatment with oseltamivir and the fraction of ivy extract. Analysis of inflammatory cell infiltration in the bronchial alveolar of PR8-infected mice revealed that CD11b+Ly6G+ and CD11b+Ly6Cint cells were recruited after virus infection; coadministration of the ivy extract fraction with oseltamivir reduced infiltration of these inflammatory cells. In a model of suboptimal oseltamivir treatment, coadministration of ivy extract fraction that includes hedrasaponin F increased protection against PR8

  15. A Study on Large Display Panel Design for the Countermeasures against Team Errors within the Main Control Room of APR-1400

    International Nuclear Information System (INIS)

    Kim, Sa Kil; Lee, Yong Hee

    2015-01-01

    The personal aspect of human errors has been mainly overcome by virtue of the education and training. However, in the system aspect, the education and training system needs to be reconsidered for more effective reduction of human errors affected from various systems hazards. Traditionally the education and training systems are mainly not focused on team skills such as communication, situational awareness, and coordination, etc. but individual knowledge, skill, and attitude. However, the team factor is one of the crucial issues to reduce the human errors in most industries. In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Team error is one of the typical organizational errors that may occur during performing operations in nuclear power plants. The large display panel is a representative feature of digitalized control room. As a group-view display, the large display panel provides plant overview to the operators. However, in terms of team performance and team errors, the large display panel is on a discussion board still because the large display panel was designed just a concept of passive display. In this study, we will propose revised large display panel which is integrated with several alternative interfaces against feasible team errors

  16. Complications thromboemboliques apres catheterisme veineux ...

    African Journals Online (AJOL)

    L' objectif de notre etude a ete de determiner la survenue de thrombose veineuse chez les patients hemodialyses porteurs de catheter veineux femoral et d'en preciser les facteurs favorisants. 11 s'agissait d'une etude retrospective sur 18 mois incluant tousles patients ayant beneficie de la pose d'un catheter veineux ...

  17. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel,; Menoux,; Candillon, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    loaded water, 10) Impot elements other than Sr{sup 90} are also studied. (author) [French] Le probleme du traitement des residus radioactifs liquides au CEA est envisage sous l'angle du rejet ultime en riviere dans des conditions optima permettant de satisfaire aux Normes de la protection. 2) A Saclay, ou l'on ne dispose que d'un etang ou l'eau ne se renouvelle pas, les liquides epures sont envoyes par camion citerne a Fontenay-aux-Roses, ou ils sont deverses provisoirement - dans les egouts - en attendant qu'un point de rejet en Seine ait ete determine. 3) Au Bouchet, les eaux residuaires de l'Usine de traitement de minerais d'urano-thorianite devront etre traitees en deux temps de facon a separer le radium dans une premiere phase, ce qui facilitera l'epuration au cours de la deuxieme phase. 4) En vue des futurs rejets a Marcoule, une etude a ete conduite a Saclay, sur des effluents synthetiques - type Marcoule - ayant pour but de mettre au point des procedes d'elimination selective du Sr d'une part, du Cs d'autre part, par coprecipitation. 5) Dans le cas general du rejet ultime en riviere, les problemes suivants sont successivement envisages: - predilution entre les bassins de stockage des eaux epurees et le fleuve; - mode d'injection dans le fleuve; - dilution dans le fleuve (etude prealable par traceurs); - evolution de l'activite dans les eaux du fleuve (adsorption par les organismes inertes ou vivants, contamination des berges); - incidence sur le choix d'un site; - dilution isotopique. 6) Ce dernier probleme est specialement detaille. 7) La teneur de l'eau en un element donne conditionne la dilution isotopique de son isotope radioactif. L'analyse decelant une carence, il est possible d'y suppleer par des rejets d'isotope stable. 8) Cette methode conduit en certains cas a des analyses delicates (en particulier dans le cas du {sup 90}Sr), la teneur en isotope stable necessaire a une forte dilution isotopique restant faible (ce qui est d'ailleurs un avantage). 9

  18. Influence du taux d'humidité et de traitements de surface (laser et implantations d'ions) sur la corrosion atmosphérique de matériaux utilisés en connectique (nickel doré)

    Science.gov (United States)

    Perrin, C.; Simon, D.

    1999-07-01

    . Dans la deuxième partie de ce travail, différents traitements de surface par faisceaux de hautes énergies (laser et implantation d'ions (titane ou titane et azote ou hélium)) de ce matériau ont été réalisés afin d'essayer de supprimer les défauts d'étanchéité de la couche d'or. Ces différents traitements ont montré une efficacité certaine quant à la suppression des porosités, confirmée par les tests de corrosion qui montrent une nette amélioration du comportement du matériau vis-à-vis de la corrosion atmosphérique.

  19. Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

    Energy Technology Data Exchange (ETDEWEB)

    Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

    1963-10-15

    numerous, observed or suspected, deficiencies or malfunctions of components which led to additional testing and analyses. In some instances, repair or modification of components was necessary to correct fabrication or engineering errors. Major problem areas are discussed: Elk River Reactor. Discovery of cracks in portions of the reactor vessel surface cladding led to extensive investigations and analyses and required some repairs and vessel modifications. Insufficient steam separation capacity required replacement and modification of some reactor vessel internal hardware. Hallam Nuclear Power Facility. Entrainment of the helium cover gas led to modifications of the secondary sodium loops. Failure of a tube in the intermediate (sodium to sodium) heat exchanger led to analyses to determine the cause of failure followed by removal and repair of the heat exchanger. Piqua Nuclear Power Facility. Chemical cleaning of the piping system damaged several valves which required mere repair or replacement. Leaks in the organic coolant and steam tracing systems caused repeated delays. After completion of the necessary repairs and modifications, the actual performance characteristics of each of the three reactors closely matched design predictions. (author) [French] Les resultats des essais apres construction de trois centrales nucleaires, dans le cadre du programme de demonstration des centrales nucleaires de la Commission de l'energie atomique des Etats-Unis (CEA-EU), permettront peut-etre de faire certaines generalisations concernant cette phase de la construction et de l'exploitation des centrales. Ces trois centrales, le reacteur de puissance d'Elk River (ERR), la centrale nucleaire de Hallam (HNPF), et la centrale nucleaire de Piqua (PNPF), appartiennent a trois filieres differentes: reacteur a eau bouillante a circulation naturelle, reacteur a graphite et a sodium et reacteur ralenti et refroidi par un fluide organique. La periode des essais apres construction a commence a la fin

  20. Untitled

    African Journals Online (AJOL)

    en nutriments dans les especes de Vermonia amer (V. amygdalina, V. cahoana var. amere) et non amer (V. colorata et V. cahoana var. non amere) rencontrées au Cameroun. Les traitements utilisés sont le lavage, le lavage après blanchiment Sans natron, le lavage après blanchiment avec une concentration de natron.

  1. Sinusites maxillaires : Epidemiologie, diagnostic et traitement | Boko ...

    African Journals Online (AJOL)

    The predisposing factors were of allergic and dental origin. Grounds for consultation were headache (43.99%), cough (25.70%), rhinorrhea (12.52%), nasal ... Conclusion: Maxillary sinusitis is common. It affects mostly young adults. The predominant predisposing factors are allergy and tooth decay. An early diagnosis has to ...

  2. Traitement Chirurgical De L\\'hyperparathyroidie Primaire ...

    African Journals Online (AJOL)

    The aim : of this work is to study our therapeutic strategy in cases of primary hyperparathyroidism and its results. Patients and methods: We proceed to a retrospective study about 34 patients treated for primary hyperparathyroidism during the period between 1992 and 2004. Results: The middle age of our patients was of 51 ...

  3. Two-phase flow parameters of a downcomer boiling during a postulated reflood phase of APR1400; Parametres d'ecoulement diphasique dans un ebullition a la cuve en acier pendant un refroidissement d'un APRP de APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Byong-Jo, Yun; Dong-Jin, Euh; Chul-Hwa, Song [Korea Atomic Energy Research Inst. (Korea, Republic of)

    2009-07-01

    Downcomer boiling phenomena is one of the key issues for a postulated large-break LOCA (LBLOCA) in a conventional pressurized water reactor, because it can degrade the hydraulic head of the coolant in the downcomer and consequently affect the reflood flow rate for a core cooling. To investigate the thermal hydraulic behavior in the downcomer region of the APR1400, a test program for a downcomer boiling is being progressed for the reflood phase of a postulated LBLOCA. Test was performed in a one side heated rectangular test channel which was designed by adopting a full-pressure, full-height, and full-size downcomer-gap approach, but with the circumferential length was reduced 47.08-fold. The test consists of two steps: (I) for the global two-phase flow parameters and (II) for the local two-phase flow parameters. The step-I test has already been completed. In the present paper, the experimental results of the step-II test are introduced. (authors)

  4. Optimisation énergétique des procédés de séparation en raffinage et en traitement de gaz naturel Optimal Use of Energy in Separation Processes for Refining and Natural Gas Treatment

    Directory of Open Access Journals (Sweden)

    Rojey A.

    2006-11-01

    Full Text Available Cet article présente une méthode d'optimisation des procédés de séparation basée sur une analyse thermodynamique. Cette analyse s'appuie sur un bilan exergétique qui est établi dans le cas général d'un système quelconque opérant en régime permanent. Les facteurs qui conditionnent le rendement exergétique d'un procédé de séparation sont ensuite examinés. Il en résulte une méthode d'optimisation basée sur une réduction des irréversibilités thermodynamiques. Des exemples concrets d'application en raffinage et en traitement de gaz naturel sont présentés, et on montre comment cette analyse peut déboucher sur la conception de procédés innovants. The optimization of separation units in refining and natural-gas processing must take into consideration new needs and constraints that may seem incompatible. New installations must be designed not only on the basis of energy optimization but also by seeking to minimize investments and to respect new rules concerning environmental protection. The optimization described in this article is based on a thermodynamic analysis of different material and energy exchanges, The energybalance provides a suitable basis for making this analysis. It leads to the defining of an exergy efficiency that is all the higher as the thermodynamic irreversibilities are reduced, and that tends toward one for an ideal reversible system. For a separation process, a separation exergyterm is defined that correspond to the minimum separation work . Distillation is the basic separation operation. The exergy efficiency of this operation is low, and we show that, even in a relatively favorable cas, it is no greater than a value of about 6%. For an atmospheric distillation operation of crude oil, the exergy efficiency is about 4%. This overall exergy efficiency is the product of an external exergy efficiency and an internal exergy efficiency. The external exergy efficiency can be improved by better thermal

  5. Influence of heat treatment in {beta} and {gamma} phases on the microscopic structure of uranium; Influence des traitements thermiques en phases {beta} et {gamma} sur la structure micrographique de l'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Robillard, A

    1958-06-02

    'orientation den structures polygonisees. En utilisant cette technique d'examen on a montre l'existence de sous-structures, differentes de celles dues a la polygonisation de la phase {alpha}, dans l'uranium traite en phase {gamma} et refroidi a une vitesse qui depend de la temperature de maintien en {gamma}. ces sous-structures sont materialisees par la precipitation d'impuretes sur les dislocations induites par les tensions qui accompagnent la transformation {gamma} {yields} {beta}. Des traitements analogues sur un alliage U-Cr 1,4 % ou la phase {beta} peut etre retenue a la temperature ambiante, confirme cette explication. En plus de ces sous-structures, on observe dans le reseau des discontinuites formant un reseau de 'joints blancs'. La comparaison avec les structures revelees par attaque thermique indique qu'il s'agit des traces des joints de la phase {gamma}. La methode d''attaque-oxydation' a permis la mise en evidence d'une phase 'aureolee' identifiee comme etant UH{sub 3}. Les conditions d'apparition et de disparition de cette phase sont etudiees. La sensibilite de la methode a detecter les traces ultimes d'H dans U est tres grande. On a enfin etudie l'influence de la teneur en hydrogene sur les proprietes mecaniques du metal uranium. (auteur)

  6. Influence of heat treatment in {beta} and {gamma} phases on the microscopic structure of uranium; Influence des traitements thermiques en phases {beta} et {gamma} sur la structure micrographique de l'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Robillard, A

    1958-06-02

    aux faibles variations d'orientation den structures polygonisees. En utilisant cette technique d'examen on a montre l'existence de sous-structures, differentes de celles dues a la polygonisation de la phase {alpha}, dans l'uranium traite en phase {gamma} et refroidi a une vitesse qui depend de la temperature de maintien en {gamma}. ces sous-structures sont materialisees par la precipitation d'impuretes sur les dislocations induites par les tensions qui accompagnent la transformation {gamma} {yields} {beta}. Des traitements analogues sur un alliage U-Cr 1,4 % ou la phase {beta} peut etre retenue a la temperature ambiante, confirme cette explication. En plus de ces sous-structures, on observe dans le reseau des discontinuites formant un reseau de 'joints blancs'. La comparaison avec les structures revelees par attaque thermique indique qu'il s'agit des traces des joints de la phase {gamma}. La methode d''attaque-oxydation' a permis la mise en evidence d'une phase 'aureolee' identifiee comme etant UH{sub 3}. Les conditions d'apparition et de disparition de cette phase sont etudiees. La sensibilite de la methode a detecter les traces ultimes d'H dans U est tres grande. On a enfin etudie l'influence de la teneur en hydrogene sur les proprietes mecaniques du metal uranium. (auteur)

  7. Le Domaine des Co-infections et des Maladies Concomitantes du Réseau Canadien pour les Essais VIH des IRSC : Lignes Directrices Canadiennes pour la Prise en Charge et le Traitement de la Co-Infection par le VIH et l’Hépatite C chez les Adultes

    Directory of Open Access Journals (Sweden)

    Mark Hull

    2014-01-01

    Full Text Available HISTORIQUE: De 20 % à 30 % des Canadiens qui vivent avec le VIH sont co-infectés par le virus de l’hépatite C (VHC, lequel est responsable d’une morbidité et d’une mortalité importantes. La prise en charge du VIH et du VHC est plus complexe en raison de l’évolution accélérée de la maladie hépatique, du choix et des critères d’initiation de la thérapie antirétrovirale et du traitement anti-VHC, de la prise en charge de la santé mentale et des toxicomanies, des obstacles socioéconomiques et des interactions entre les nouvelles thérapies antivirales à action directe du VHC et les antirétroviraux

  8. Délire dermatozoïque: à propos d'un cas

    Science.gov (United States)

    Jawaher, Masmoudi; Ines, Feki; Rim, Sallemi; Imen, Baati; Abdellaziz, Jaoua

    2013-01-01

    Le délire dermatozoïque est un délire particulier survenant chez les personnes âgées et caractérisé par la présence d'un délire hallucinatoire essentiellement cénesthésique, avec la conviction d’être infesté par des petites bêtes. Ce délire aboutit à des lésions de grattage pouvant être graves, mais sans aucune étiologie organique, et leurrant souvent le dermatologue. Notre observation est originale, par le fait que le patient a été adressé par un ophtalmologue, et faisant étendre le champ du diagnostic à plusieurs spécialités, s'occupant des patients âgés. il s'agit d'un patient âgé de 67 ans, ayant présenté da façon concomitante à une intervention chirurgicale et au mariage de son dernier fils, un délire hallucinatoire avec une conviction d’être attaqué par des moustiques lui suçant le sang. Des lésions d'excoriation cutanée ont été secondaires à ce délire, et ont été à l'origine d'une consultation psychiatrique. L’évolution après six mois de traitement a été marquée par l'enkystement du délire et l'amélioration des lésions cutanées. Réputé rare, le délire dermatozoïque pourrait être déroutant si on ne fait pas le diagnostic positif. Tout clinicien peut être confronté dans sa pratique à ce type de syndrome. Sa compréhension facilite une prise en charge adéquate, basée essentiellement sur un soutien psychologique et un traitement neuroleptique. PMID:24570786

  9. Epidémiologie et facteurs de risque des complications respiratoires majeures après chirurgie de l'aorte abdominale au CHU Ibn Sina, Maroc

    Science.gov (United States)

    Awab, Almahdi; Elahmadi, Brahim; Lamkinsi, Tarik; El Moussaoui, Rachid; El Hijri, Ahmed; Azzouzi, Abderrahim; Alilou, Mustapha

    2013-01-01

    Introduction L'incidence des complications respiratoires postopératoires (CRPO) reste très diversement appréciées selon les critères diagnostiques retenues dans les différentes études, ce qui la fait varier de 5 à plus de 50%. Les CRPO majeurs après chirurgie de l'aorte abdominale sont responsables d'une grande morbi-mortalité pouvant aller jusqu’à 36%, d'une durée d'hospitalisation et d'un coût plus importants. Ainsi dans l'optique d'améliorer notre prise en charge périopératoire de la chirurgie de l'aorte, nous avons décidé de mener une étude pour dresser le profil épidémiologique et déterminer les facteurs de risque des complications respiratoires dans notre contexte Méthodes Il s'agit d'une étude de cohorte rétrospective du mois de Janvier 2007 au mois de décembre 2011 portant sur l'ensemble des patients opérés pour pathologie aortique au bloc opératoire central de l'hôpital Ibn Sina de Rabat, Maroc. Résultats Cent vingt cinq patients ont été inclus dans notre étude, 24 patients ont été opérés pour anévrysme de l'aorte abdominale et 101 patients pour lésion occlusive aortoiliaque. Dans notre série 22 malades soit 17,6% ont présenté une complication respiratoire majeure avec, une reventilation dans 4,8% des cas, une difficulté de sevrage de la ventilation artificielle dans 3,2% des cas, une pneumopathie dans 4% des cas, un syndrome de détresse respiratoire aigue (SDRA) dans 4% des cas et une nécessité de fibroaspiration bronchique dans 1,6% des cas. En analyse univariée: l’âge, la présence d'une BPCO avec dyspnée stade 3 ou 4, la présence d'une anomalie à l'EFR préopératoire, la présence d'un stade avancé (III ou IV) de LOAI et la reprise chirurgicale étaient statistiquement associés à la survenue d'une complication respiratoire postopératoire. En analyse multivariée, seule une anomalie à l'EFR en préopératoire constituait un facteur de risque indépendant de survenue d'une complication

  10. Réutilisation d'argiles très plastiques (A4) en remblai : Suivi du comportement après trois ans de réalisation

    OpenAIRE

    BERCHE, Véronique; ROBERT, Nicolas; BOUSSAFIR, Yasmina; FERBER, Valéry

    2013-01-01

    Cet article présente la réalisation de remblais en argile très plastiques en 2003 sur l'A34 dans les Ardennes (France) ainsi que les résultats du suivi du comportement de ces remblais dans le temps. Après un bref rappel des conditions de réalisation de ces remblais, un résumé des résultats de portance et de densité à court et moyen terme sera exposé. Dans un deuxième temps, des résultats de densité (double sonde Gamma et passage au banc Gamma) et essais Dynaplaque réalisés en 2006 seront c...

  11. PRIMA-1 and PRIMA-1Met (APR-246: From Mutant/Wild Type p53 Reactivation to Unexpected Mechanisms Underlying Their Potent Anti-Tumor Effect in Combinatorial Therapies

    Directory of Open Access Journals (Sweden)

    Anne Perdrix

    2017-12-01

    Full Text Available p53 protects cells from genetic assaults by triggering cell-cycle arrest and apoptosis. Inactivation of p53 pathway is found in the vast majority of human cancers often due to somatic missense mutations in TP53 or to an excessive degradation of the protein. Accordingly, reactivation of p53 appears as a quite promising pharmacological approach and, effectively, several attempts have been made in that sense. The most widely investigated compounds for this purpose are PRIMA-1 (p53 reactivation and induction of massive apoptosis and PRIMA-1Met (APR-246, that are at an advanced stage of development, with several clinical trials in progress. Based on publications referenced in PubMed since 2002, here we review the reported effects of these compounds on cancer cells, with a specific focus on their ability of p53 reactivation, an overview of their unexpected anti-cancer effects, and a presentation of the investigated drug combinations.

  12. Technical and Administrative Considerations in the Management of Radioactive Wastes; Considerations Techniques et Administratives Relatives au Traitement des Dechets Radioactifs; 0422 0415 0425 041d 0418 0427 0415 0421 041a 0414 ; Aspectos Tecnicos y Administrativos de la Manipulacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Wolman, Abel [Johns Hopkins University, Baltimore, MD (United States); Division of Reactor Development, U.S. Atomic Energy Commission, Washington, DC (United States); Lieberman, Joseph A. [Environmental and Sanitary Engineering Branch, Division of Reactor Development, U.S. Atomic Energy Commission, Washington, DC (United States)

    1960-07-01

    administratifs du traitement des dechets en rattachant cette analyse aux mesures qu'il pourrait etre necessaire de prendre dans l'avenir pour assurer un traitement et un controle efficaces, sur le plan administratif et juridique, des effluents radioactifs resultant de la production d'energie atomique. Les auteurs repartissent tout d'abord en de larges categories les differentes sortes de dechets pour bien souligner que le probleme de leur traitement presente de multiples aspects et qu'on ne saurait en donner une solution unique. Ils examinent rapidement le role des differents milieux dans le choix des methodes de traitement des dechets et definissent les procedes fondamentaux de controle (dilution et dispersion, concentration et confinement). Les auteurs distinguent entre les normes fondamentales de protection radiologique et les criteres de fonctionnement qui doivent etre fixes pour realiser le controle des effluents de facon a veiller a ce que les normes fondamentales soient respectees. Les auteurs examinent les progres realises en matiere de normes et criteres ainsi que l'application de ceux-ci dans l'etablissement de reglements de sante et de securite et la mise au point de procedures administratives et juridiques. A cet egard, ils signalent les avantages que presente, du point de vue de l'opinion publique et du travail administratif, l'utilisation la plus large des textes legislatifs et des procedures administratives dans les services deja crees aux divers echelons de l'autorite. Malgre l'importance des depenses qu'entrainent le traitement et l'elimination des dechets radioactifs, le cout par unite d'energie electrique produite ne represente qu'une partie relativement restreinte du cout total par unite d'energie. Les auteurs indiquent d'autres facteurs economiques qui jouent un role dans la manipulation et l'elimination des dechets, notamment en fonction de l'emplacement de l'usine et du point d'evacuation. En outre, ils examinent d'autres aspects du traitement des dechets

  13. Case series

    African Journals Online (AJOL)

    ebutamanya

    9 juin 2008 ... longtemps débattue, après avoir proposé initialement une origine musculaire striée les études récentes sont en faveur d'une origine neurogène schwannienne confirmées par une étude immunohistochimique. Le traitement de la tumeur à cellules granuleuses est un traitement chirurgical, il permet un ...

  14. Phylogenetic diversity and spatial distribution of the microbial community associated with the Caribbean deep-water sponge Polymastia cf. corticata by 16S rRNA, aprA, and amoA gene analysis.

    Science.gov (United States)

    Meyer, Birte; Kuever, Jan

    2008-08-01

    Denaturing gradient gel electrophoresis (DGGE)-based analyses of 16S rRNA, aprA, and amoA genes demonstrated that a phylogenetically diverse and complex microbial community was associated with the Caribbean deep-water sponge Polymastia cf. corticata Ridley and Dendy, 1887. From the 38 archaeal and bacterial 16S rRNA phylotypes identified, 53% branched into the sponge-specific, monophyletic sequence clusters determined by previous studies (considering predominantly shallow-water sponge species), whereas 26% appeared to be P. cf. corticata specifically associated microorganisms ("specialists"); 21% of the phylotypes were confirmed to represent seawater- and sediment-derived proteobacterial species ("contaminants") acquired by filtration processes from the host environment. Consistently, the aprA and amoA gene-based analyses indicated the presence of environmentally derived sulfur- and ammonia-oxidizers besides putative sponge-specific sulfur-oxidizing Gammaproteobacteria and Alphaproteobacteria and a sulfate-reducing archaeon. A sponge-specific, endosymbiotic sulfur cycle as described for marine oligochaetes is proposed to be also present in P. cf. corticata. Overall, the results of this work support the recent studies that demonstrated the sponge species specificity of the associated microbial community while the biogeography of the host collection site has only a minor influence on the composition. In P. cf. corticata, the specificity of the sponge-microbe associations is even extended to the spatial distribution of the microorganisms within the sponge body; distinct bacterial populations were associated with the different tissue sections, papillae, outer and inner cortex, and choanosome. The local distribution of a phylotype within P. cf. corticata correlated with its (1) phylogenetic affiliation, (2) classification as sponge-specific or nonspecifically associated microorganism, and (3) potential ecological role in the host sponge.

  15. Valutazione dell'appropriatezza dei ricoveri in un Policlinico Universitario: analisi mediante l'uso comparativo dei sistemi di classificazione isogravitá APR-DRG e Disease Staging e del PRUO

    Directory of Open Access Journals (Sweden)

    M. Volpe

    2003-05-01

    Full Text Available

    Obiettivi: valutare l’appropriatezza organizzativa dei ricoveri effettuati in un Policlinico Universitario attraverso la comparazione di due metodi, dei quali uno basato sui dati della scheda di dimissione ospedaliera ed utilizza, rispettivamente, i sistemi di classificazione iso-gravità APR-DRG e Disease Staging e l’altro sulla revisione delle cartelle cliniche mediante il PRUO.

    Metodi: oggetto di analisi sono i ricoveri ordinari effettuati nell’anno 2001 ed afferenti ai DRG inclusi nella delibera della Giunta Regionale del Lazio 864/2002 che recepisce il D.P.C.M. 29/11/2001 sui livelli essenziali di assistenza.

    Risultati: i risultati evidenziano che le due varianti del
    metodo basato sulla SDO (metodo APPRO mostrano quote di ricoveri inappropriati sovrapponibili rispetto al complesso dei ricoveri oggetto di analisi, ma con differenze anche rilevanti tra APR-DRG e Disease Staging in relazione ai singoli DRG considerati, riconducibili ai diversi algoritmi di attribuzione del livello di severità utilizzati dai due sistemi. L’analisi campionaria effettuata con il metodo PRUO su casi afferenti ai DRG della DGR 864/2002 caratterizzati da livelli di severità minimi evidenzia una proporzione di ricoveri inappropriati superiore a quella determinata tramite i metodi basati sulla SDO. Tale differenza è verosimilmente dovuta al ruolo del valore delle soglie percentuali di accettabilità individuate dalla Regione Lazio per ciascun DRG: le quote di ricoveri che eccedono tali soglie sono considerate inappropriate.

    Conclusioni: sulla base dei risultati ottenuti gli autori
    descrivono gli interventi organizzativi adottati per ottimizzare il contesto di erogazione delle prestazioni
    oggetto di analisi, discutono vantaggi e limiti dei metodi SDO-based e del metodo analitico PRUObased e ne propongono l

  16. Tarifa e Ocupação em Hotéis: provocando o modelo de apreçamento convencional

    Directory of Open Access Journals (Sweden)

    Eder Paschoal Pinto

    2010-07-01

    -style:italic; mso-bidi-font-style:normal;} p.Captulo, li.Captulo, div.Captulo {mso-style-name:Capítulo; mso-style-unhide:no; margin-top:12.0pt; margin-right:0cm; margin-bottom:12.0pt; margin-left:0cm; text-align:justify; mso-pagination:widow-orphan; font-size:12.0pt; font-family:"Times New Roman","serif"; mso-fareast-font-family:"Times New Roman"; font-weight:bold; mso-bidi-font-weight:normal;} .MsoChpDefault {mso-style-type:export-only; mso-default-props:yes; font-size:10.0pt; mso-ansi-font-size:10.0pt; mso-bidi-font-size:10.0pt;} @page WordSection1 {size:612.0pt 792.0pt; margin:70.85pt 3.0cm 70.85pt 3.0cm; mso-header-margin:36.0pt; mso-footer-margin:36.0pt; mso-paper-source:0;} div.WordSection1 {page:WordSection1;} -->

    Resumo

    O objetivo central deste trabalho é discutir a relação entre tarifa e taxa de ocupação em hotéis. As teorias de segmentação de clientes, composto mercadológico e estratégia de apreçamento foram aplicadas ao estudo. Os hotéis de Santos classificados como Turístico e Luxo foram escolhidos intencionalmente. Oitenta e três por cento deles responderam ao

  17. Treatment of Radioactive Waste at Japan's Atomic Energy Research Institute; Traitement des Dechets Radioactifs a l'Institut Japonais de Recherches sur l'Energie Atomique; 041e 0411 0420 0410 0411 041e 0422 041a 0410 0420 0410 0414 ; Tratamiento de los Desechos Radiactivos en el Instituto de Investigaciones sobre Energia Atomica del Japon

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Yutaka [University of Toyko (Japan); Japan Atomic Energy Research Institute (Japan); Ito, Masukuni F.; Ishihara, Takehiko; Mitsuishi, Nobuo [Sadahiro Sakata, Japan Atomic Energy Research Institute (Japan)

    1960-07-01

    The paper describes the origin, nature and treatment of the radioactive wastes. The very low-level liquid waste is diluted and released to the sea, while the low- and medium-level liquid waste is treated by flocculation, evaporation and ion-exchange methods. The solid waste is collected and the combustible waste incinerated. (author) [French] Le present memoire decrit l'origine, la nature et le traitement des dechets radioactifs. Les dechets liquides de tres faible activite sont dilues et evacues dans la mer, tandis que les dechets liquides d'activite faible et moyenne sont traites par des methodes de floculation, d'evaporation et d'echange d'ions. Les dechets solides sont rassembles et les dechets combustibles sont incineres. (author) [Spanish] Los aiutores describen el origen y la naturaleza de los desechos radiactivos, asi como los metodos seguidos para su tratamiento. Los desechos liquidos de muy bajo nivel de actividad se diluyen primero y luego se descargan en el mar, en tanto que los desechos liquidos de bajo y mediano nivel se tratan mediante procedimientos de floculacion, evaporacion e intercambio ionico. Los residuos solidos se acopian y los residuos combustibles se incineran. (author) [Russian] V dokumente opisyvajutsja priroda i harakter radioaktivnyh othodov i metody ih obrabotki. Zhidkie othody ochen' nizkoj aktivnosti razbavljajutsja i otvodjatsja v morja, a zhidkie othody nizkoj i srednej aktivnosti obrabatyvajutsja metodami flokkuljacii, vyparivanija i ionnogo obmena. Tverdye othody sobirajutsja i po vozmozhnosti szhigajutsja. (author)

  18. Automatic Sample and Data Processing in Studies of Calcium Metabolism in Rats; Traitement Automatique des Echantillons et des Donnees dans l'Etude du Metabolisme Calcique chez le Rat; Avtomaticheskaya obrabotka obraztsov i dannykh pri izuchenii obmena kal'tsiya u krysy; Tratamiento Automatico de las Muestras y de los Datos en el Estudio del Metabousmo del Calcio en la Rata

    Energy Technology Data Exchange (ETDEWEB)

    Onkelinx, C.; Richelle, L. J.; Debras, J. [Universite de Liege (Belgium)

    1965-10-15

    the standard deviation shown by the measurements for each sample; (2) analysing the specific activity curve of the plasma and expressing it in mathematical terms; comparing the theoretical curve with the experimental measurements; (3) evolving the complete model by calculating the various parameters. The results are printed out in full and also punched onto cards by the computer for further processing later. The advantages of digital over analogue computers for this work are discussed. (author) [French] L'etude du metabolisme calcique du rat en fonction de l'age ou de divers traitements exige une experimentation portant sur de grandes series d'animaux. Ces explorations requierent, d'une part, l'etude de l'evolution avec le temps de la concentration serique d'une dose traceuse de {sup 45}Ca injectees par voie intraveineuse et, d'autre part, la mesure d'un bilan chimique et radiochimique. La combinaison de ces deux types d'informations et leur traitement mathematique conduit a la resolution d'un modele general du metabolisme calcique qui permet de connaitre la taille des compartiments echangeables et la grandeur de differents vecteurs tels que l'absorption intestinale, l'excretion renale et intestinale, le depot et la sortie de calcium de l'os. Les travaux ont ete facilites par le developpement de methodes automatiques de mesure des echantillons et de traitement des donnees, qui font l'objet du memoire. Traitement des echantillons: les mesures de radioactivite sont effectuees sur des echantillons plasmatiques de faible volume (20 a 40 {lambda}) preleves de maniere repetee et sur des collections fecales et urinaires faites entre deux limites de temps. La chaine de mesure utilisee comporte un detecteur a anti-coiencidence de faible bruit de fond, un passeur d'echantillons et un ensemble electronique dont les mesures sont enregistrees par une machine imprimante. Les methodes originales de preparation des echantillons et les performances de la chatoie de mesure sont

  19. La chronologie du royaume de Qatabân du Ier siècle avant J.-C. au Ier siècle après J.-C.

    Directory of Open Access Journals (Sweden)

    Mounir Arbach

    2002-04-01

    Full Text Available Les nouvelles découvertes archéologiques et épigraphiques de ces dernières années, effectuées au cours des fouilles franco-italiennes à Tamna`, l'ancienne capitale du royaume de Qatabân, permettent d'établir une nouvelle chronologie des souverains de Qatabân entre le Ier siècle avant J.-C. et le Ier siècle après J.- C.The chronology of the kingdom of Qatabân, from the 1st century BC to the 1st century AD. Archaeological and epigraphical discoveries made in recent years by the Franco-Italian excavations at Tamna`, the ancient capital of the kingdom of Qatabân, allows us to establish a new chronology for the kings of Qatabân during the 1st century BC and the 1st century AD.

  20. [Evaluation of the appropriateness of hospital admissions using the iso-gravity classification systems APR-DRG and Disease Staging and the Italian version of Appropriateness Evaluation Protocol (AEP)].

    Science.gov (United States)

    D'Andrea, G; Capalbo, G; Volpe, M; Marchetti, M; Vicentini, F; Capelli, G; Cambieri, A; Cicchetti, A; Ricciardi, G; Catananti, C

    2006-01-01

    Our main purpose was to evaluate the organizational appropriateness of admissions made in a university hospital, by comparing two iso-gravity classification systems, APR-DRG and Disease Staging, with the Italian version of AEP (PRUO). Our analysis focused on admissions made in 2001, related to specific Diagnosis Related Groups (DRGs), which, according an Italian Law, would be considered at high risk of inappropriateness, if treated as ordinary admissions. The results obtained by using the 2 classification systems did not show statistically significant differences with respect to the total number of admissions. On the other hand, some DRGs showed statistically significant differences due to different algorithms of attribution of the severity levels used by the two systems. For almost all of the DRGs studied, the AEP-based analysis of a sample of medical records showed an higher number of inappropriate admissions in comparison with the number expected by iso-gravity classification methods. The difference is possibly due to the percentage limits of tolerability fixed by the Law for each DRG. Therefore, the authors suggest an integrated use of the two methods to evaluate organizational appropriateness of hospital admissions.

  1. Instruments used to measure or check {alpha}, {beta}, {gamma} activity and neutron emission in the course of processing ore or irradiated fuel; Appareils de mesure ou de controle {alpha}, {beta}, {gamma}, n, des circuits des usines de traitement du minerai ou du combustible irradie

    Energy Technology Data Exchange (ETDEWEB)

    Blanc, A; Brunet, M; Kermagoret, M; Labeyrie, J; Roux, G; Vasseur, J; Weil, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    One of the methods checking ores in the course of treatment is the rapid quantitative determination of thorium. This measurement is carried out by means of a scintillation instrument which shows the {beta} and {alpha} coincidences of ThC and ThC'. The treatment of irradiated fuel is accompanied by a large number of radioactive checks relative to the performance of the fixation and elution operations of uranium in the ion exchangers, to the concentration of radioactivity of effluent sent from the plant into watercourses. The operations of fixation and elution of the uranium are checked automatically by an instrument which takes a sample of 5 cm{sup 3} of solution, evaporates it and measures its activity every 10 or 20 minutes. Plutonium concentrations are measured: - in the presence of strong {beta} {gamma} activities, by means of rotating cylinder detectors; - in the presence of weak {beta} {gamma} activities, by means of {alpha} detectors scanning a constant level liquid surface; - by means of fission chambers relatively insensitive to {gamma}. Fission product concentrations are measured by chambers, counters or scintillators, according to the amount of {gamma} activity present. Finally, the activity of effluent to be emptied into watercourses is checked by means of a scintillation instrument, which measures the {alpha} activity on the one hand, and on the other hand the {beta} {gamma} activity of residue from a 100 cm{sup 3} sample taken and evaporated in 20 minutes. (author) [French] Parmi les controles relatifs au minerai en cours de traitement, figure le dosage rapide de thorium. Cette mesure est realisee au moyen d'un appareillage a scintillation qui met en evidence la coincidence des emissions {beta} et {alpha} du ThC et du ThC'. Le traitement des combustibles irradies s'accompagne d'un grand nombre de controles radioactifs portant sur le fonctionnement des operations de fixation et d'elution de l'uranium dans les echangeurs d'ions, sur la concentration du

  2. Evaluation du traitement antirétroviral chez les femmes enceintes VIH-1 positif, sur la transmission de l'infection de la mère à l'enfant: cas du Centre Médical Saint Camille de Ouagadougou, au Burkina Faso

    Science.gov (United States)

    Soubeiga, Serge Theophile; Compaore, Rebecca; Djigma, Florencia; Zagre, Nicaise; Assengone, Elsa; Traore, Lassina; Diarra, Birama; Bisseye, Cyrille; Ouermi, Djeneba; Sagna, Tani; Karou, Simplice; Pietra, Virginio; Simpore, Jacques

    2015-01-01

    Introduction L'infection au VIH chez les nouveau-nés par leur mère peut être réduite grâce à des programmes de prévention de transmission mère-enfant du VIH (PTME). L'objectif dans cette étude était d’évaluer le traitement antirétroviral chez les femmes enceintes VIH-1 positif sur la transmission mère-enfant de l'infection au Centre Médical Saint Camille de Ouagadougou, Burkina Faso. Méthodes Des échantillons de spot de sang total ont été collectés chez 160 enfants âgés de 6 semaines, nés de mères VIH-1 positif et chez 40 enfants âgés de 2 à 13 mois provenant d'orphelinats et dont les mères étaient inconnues. Ces échantillons ont été testés avec le kit Abbott Real Time HIV-1 Qualitative. Un questionnaire a permis de connaitre les âges et les fonctions des femmes enceintes. Résultats Les femmes enceintes avaient un âge moyen global de 29,50±5,19 ans. Au total, 50,5% (101/200) ont été mises sous combinaison AZT/3TC/NVP et 29,5% (59/200) étaient sous prophylaxie (AZT/3TC). Le taux de transmission verticale du VIH-1 était de 0,0% (0/160) (p VIH-1 de la mère à l'enfant. De plus, le dépistage par PCR, des enfants orphelins infectés verticalement par le VIH, permet leur prise en charge thérapeutique précoce. PMID:26301003

  3. The development of a cell-assembly for the treatment of irradiated fuels on a semi-industrial scale; Etude concernant la realisation d'un ensemble de cellules destinees a des traitements de combustibles irradies a l'echelle semi-industrielle

    Energy Technology Data Exchange (ETDEWEB)

    Faugeras, P; Couture, J; Lefort, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    The main studies and experiments involved in the development of a cell-assembly for the treatment of irradiated fuels on a semi-industrial scale are described. It must be possible to modify or transform each of these cells without interrupting the rest of the pilot. A full-scale prototype cell (3 x 4 x 6 m) has been built with an {alpha}-protection independent of the {gamma}-protection. It features all the main characteristics: tightness to {gamma} losses, dense glass lighting, ventilation. This cell has made possible trials on transfer, remote-controls and tele-dismantling, as well as the development of new methods of rapidly connecting hydraulic circuits. In conclusion the final form is given of the cells selected for the pilot. (author) [French] Il est decrit les principales etudes et experiences faites en vue de la realisation d'un ensemble de cellules destinees a des traitements de combustibles irradies a l'echelle semi-industrielle. Chacune de ces cellules doit pouvoir etre modifiee ou transformee sans interrompre le reste du pilote. Une cellule prototype vraie grandeur (3x4x6 m) est construite avec une protection {alpha} independante de la protection {gamma}. Elle comporte tous les elements importants: porte {gamma} etanche, eclairage verre dense, ventilation. Cette cellule a permis des experiences de transferts de telemanipulateurs et de teledemontages, ainsi que la mise au point de nouveaux procedes de jonction rapide pour des circuits hydrauliques. En conclusion, on indique la forme definitive des cellules retenues pour le pilote. (auteur)

  4. 120 Activité hypoglycémique de l'extrait aqueux d'Ajuga iva L ...

    African Journals Online (AJOL)

    PR BOKO

    Les plantes constituent une source potentielle de médicaments hypoglycémiants composés dérivés de plantes ont été utilisées dans le traitement du diabète. Le diabète touche environ 5% de la population mondiale [2] et la gestion du diabète sans aucun effet secondaire est toujours un défi pour le système de santé [3].

  5. Les lémuriens du site Ramsar de Torotorofotsy

    African Journals Online (AJOL)

    s secondaires qui évoluent vers une formation clima- cique appelée savoka et qui sera à nouveau exploitable après cinq à dix ans de jachère (Kiener 1963, Aubert et al. 2003, Styger et al. 2007). Ce dynamisme de formation végétale entraine un dynamisme d'éparpillement des hameaux en fonction des terrains fertiles.

  6. Favoriser la rencontre entre la littérature et les lycéens

    NARCIS (Netherlands)

    Rentrop - Weij, Joke|info:eu-repo/dai/nl/314449302; Haenen, Jacques|info:eu-repo/dai/nl/070566135

    2014-01-01

    Comment engager les élèves à la littérature? Une enseignante de secondaire de FLE et une didacticienne d’une université de FLE aux PaysBas collaborent dans le but général d’inciter les élèves à lire des romans littéraires pendant et après leur vie scolaire. Elles ont développé deux cours de

  7. Contribution to the study of physico-chemical properties of surfaces modified by laser treatment. Application to the enhancement of localized corrosion resistance of stainless steels; Contribution a l'etude des proprietes physico-chimiques des surfaces modifiees par traitement laser. Application a l'amelioration de la resistance a la corrosion localisee des aciers inoxydables

    Energy Technology Data Exchange (ETDEWEB)

    Pacquentin, W.

    2011-11-25

    integrite sur des periodes de plus en plus longues. L'objectif de ce travail de these est d'evaluer le potentiel d'un traitement de refusion laser pour ameliorer la resistance a la corrosion d'un acier inoxydable de type 304L; l'utilisation du laser dans le domaine des traitements de surface constituant un procede en pleine evolution a cause des changements recents dans la technologie des lasers. Dans le cadre de ce travail, le choix du laser s'est porte sur un laser nano-impulsionnel a fibre dopee ytterbium dont les caracteristiques permettent la fusion quasiinstantanee sur quelques microns de la surface traitee, immediatement suivie d'une solidification ultra-rapide avec des vitesses de refroidissement pouvant atteindre 1011 K/s. La combinaison de ces processus favorise l'elimination des defauts surfaciques, la formation de phases hors equilibre, la segregation d'elements chimiques et la formation d'une nouvelle couche d'oxyde dont les proprietes sont gouvernees par les parametres laser. Afin de les correler avec la reactivite electrochimique de la surface, l'influence de deux parametres laser sur les proprietes physicochimiques de la surface a ete etudiee: la puissance du laser et le taux de recouvrement des impacts laser. Pour clarifier ces relations, la resistance a la corrosion par piquration des surfaces traitees a ete determinee par des tests electrochimiques. Pour des parametres laser specifiques, le potentiel de piquration d'un acier inoxydable de type 304L augmente de plus de 500 mV traduisant ainsi une meilleure tenue a la corrosion localisee en milieu chlorure. L'interdependance des differents phenomenes resultant du traitement laser a rendu complexe la hierarchisation de leur effet sur la sensibilite de l'alliage teste. Cependant, il a ete montre que la nature de l'oxyde thermique forme au cours de la refusion laser et ses defauts sont du premier ordre pour l'amorcage des

  8. Evolution de la gonadotropine plasmatique t-GtH après synchronization des ovulations par injection de 17α hydroxy-20β dihydroprogesterone chez la truite arc-en-ciel (Salmo gairdneri R.) : Evolution of plasmatic gonadotropin t-gth after synchronization of ovulations by injection of 17-α hydroxy-20β dihydroprogesterone in rainbow-trout (Salmo gairdneri R.)

    OpenAIRE

    Jalabert, Bernard; Breton, Bernard; Bry, C.

    1980-01-01

    L'injection de 17α hydroxy-