WorldWideScience

Sample records for rayonnements residuels apres

  1. After-Ripening of Red Pepper (Capsicum Annuum) as Affected by Ionizing Radiation; Effets des Rayonnements Ionisants sur le Murissement du Piment (Capsicum Annuum) Apres la Recolte; Vliyanie ioniziruyushchego izlucheniya na dozrevanie krasnogo pertsa (Capsicum Annuum); Efecto de las Radiaciones Ionizantes en la Postmaturacion del Pimiento Rojo (Capsicum Annuum)

    Energy Technology Data Exchange (ETDEWEB)

    Farkas, J.; Kiss, I.; Andrassy, Eva [Central Food Research Institute, Budapest (Hungary)

    1966-11-15

    'effet direct des rayons X a des doses comprises entre 0 et 800 krad sur le piment doux fraichement cueilli et a des doses comprises entre 0 et 100 krad sur le murissement du piment apres la recolte. Sous l'effet de l'exposition a une dose comprise entre 400 et 800 krad, les pericarpes se-sont amollis; toutefois, la teneur en carotenoides n'a pas ete sensiblement reduite, meme apres exposition a une dose de 800 krad. Au cours de la periode de neuf semaines consecutives a l'irradiation, pendant laquelle les piments ont ete emmagasines a la temperature ambiante, on a constate que la teneur totale en pigments, sous forme de capsanthine avait augmente d'environ 90% dans les echantillons non traites. La formation des pigments a base de carotenoides a ete acceleree dans une certaine mesure par l'exposition a une dose de 80 rad et sensiblement acceleree par l'exposition a une dose de 2 krad. Les echantillons soumis a une dose de 2 krad avaient au bout de trois semaines la meme teneur en pigments que les echantillons temoins au bout de huit semaines. Toutefois, la teneur en pigments des echantillons irradies a diminue apres une periode d'emmagasinage de quatre a cinq semaines. L'exposition a des doses superieures a 10 krad a ralenti ou inhibe la formation des carotenoides pendant la periode d'emmagasinage (apres maturation). La reduction de la teneur en sucres et la vitesse de dessiccation n'ont pas ete affectees par l'exposition a des doses de 0 a 100 krad. Etant donne les effets nefastes de l'exposition aux doses de rayonnements de plusieurs centaines de krad necessaires pour detruire les moisissures qui provoquent l'alteration du piment a forte teneur en eau, ou pour inhiber fortement le developpement de ces organismes, il ne semble pas souhaitable d'utiliser les rayonnements pour reduire les pertes de piments fraichement cueillis. Neanmoins, l'application des doses tres faibles qui stimulent la formation des carotenoides semble devoir donner de bons resultats, car elle abrege la

  2. Détection de rayonnements et instrumentation nucléaire

    CERN Document Server

    Lyoussi, Abdallah

    2010-01-01

    La détection de rayonnements nucléaires passe obligatoirement par leur interaction avec le milieu détecteur. Ces interactions génèrent directement ou indirectement des charges électriques lesquelles, une fois collectées sont (pré)amplifiées et converties en signaux électriques. Cette opération est rendue possible grâce à la polarisation électrique du détecteur conduisant à l'établissement d'un champ électrique responsable du mouvement des charges produites et de leur collection. D'une manière générale la détection et la mesure de rayonnements est un processus à plusieurs étapes comme le montre le synoptique de la figure 1.1. Il s'agit dans un premier temps de faire interagir le rayonnement incident utile avec le milieu détecteur après qu'il ait franchi l'espace «source-détecteur». Ces interactions sont ensuite converties en impulsions électriques qui sont traitées électroniquement et acheminées vers une unité d'acquisition et d'analyse. On obtient ainsi un premier résultat a...

  3. Effets des rayonnements de haute energie sur le cristallin de la souris

    CERN Document Server

    Di Paola, M; Bianchi, M; Bianchi, M no 1; Baarli, J no 1; Di Paola, M no 1

    1973-01-01

    L'opacification du cristallin après irradiation par des neutrons et d'autres rayonnements ionisants a été largement étudiée, vu l'importance de telles recherches en radioprotection et la possibilité offerte par ce système d'analyser les effets produits par de petites doses de rayonnement. Les neutrons de haute énergie sont d'un intéret particulier pour la radioprotection près des accélérateurs et dans l'espace, mais jusqu'à présent les études ont été limitées aux neutrons d'énergie inférieur à 14 MeV. L'opacification du cristallin chez la souris, après irradiation par des neutrons de 400 MeV produits par le Synchro-Cyclotron du CERN, a été étudiée. Le valeurs d'E.B.R. ont été déterminées par comparaison avec des rayons X de 250 kV. Une breve discussion des résultats obtenus est inclue dans la présentation.

  4. ParticipACTION, cinq ans après sa relance : enquête quantitative sur son rayonnement et sur le pouvoir d'action des organisations au Canada en matière d’initiatives consacrées à l’activité physique

    Directory of Open Access Journals (Sweden)

    Guy Faulkner

    2018-01-01

    Full Text Available Introduction. ParticipACTION est un organisme canadien relancé en 2007 dédié à la communication et au marketing social en matière d’activité physique. Cette étude porte sur le pouvoir d'action des organismes canadiens dans l'adoption, la mise en oeuvre et la promotion des initiatives en ce domaine. Nos objectifs étaient de comparer les résultats de base (2008 avec les résultats de suivi (2013 en ce qui concerne (1 la connaissance de ParticipACTION, (2 la capacité d'un organisme à adopter, à mettre en oeuvre et à promouvoir des initiatives d’activité physique et (3 les différences potentielles en matière de pouvoir d'action d'une organisation en fonction de sa taille, de son secteur et de son mandat ainsi que (4 d’évaluer la perception de ParticipACTION cinq ans après sa relance. Méthodologie. Dans le cadre de cette étude transversale, des représentants d’organismes locaux, provinciaux, territoriaux et nationaux ont rempli un questionnaire en ligne visant à évaluer la capacité de leur organisme à adopter, à mettre en oeuvre et à promouvoir des initiatives d’activité physique. Nous avons utilisé des méthodes de statistique descriptive et des analyses de variance à un facteur pour répondre à nos objectifs. Résultats. Le taux de réponse correspondant aux personnes ayant ouvert le courriel d’invitation à répondre au sondage et ayant consenti à y participer était de 40,6 % (685/1 688. Au total, 540 questionnaires de sondage ont été remplis. Le taux de connaissance de ParticipACTION, qui se chiffrait à 54,6 % lors de l’étude initiale, avait atteint 93,9 % au moment du suivi (objectif 1. Tant les résultats initiaux que les résultats de suivi ont fait état d’un pouvoir d'action important des organismes dans l'adoption, la mise en oeuvre et la promotion d'initiatives d’activité physique (objectif 2, avec cependant de légères variations en fonction du secteur et du mandat de chaque

  5. Radioprotection rayonnements, dosimétrie, protection

    CERN Document Server

    Marey, Gérard

    2014-01-01

    Pour tous les travailleurs du nucléaire comme pour les étudiants des licences professionnelles et des BTS Environnement nucléaire et BTS radioprotection, l'ouvrage rassemble de façon progressive, claire et précise toutes les informations scientifiques et pratiques qui leur sont indispensables. Une première partie résume les données de base relatives à la structure de la matière, la stabilité des noyaux, les différents rayonnements, leur énergie et la décroissance radioactive. La deuxième partie constitue une approche progressive de la radioprotection s'appuyant sur l'influence des rayonnement sur la matière pour définir les notions de dose et aborder le dimensionnement des protections biologiques et des éléments de ventilation. Enfin, la dernière partie traite de la mise en oeuvre pratique de la radioprotection sur le terrain et de la gestion des déchets nucléaires en application de la technologie actuelle, de la réglementation et des directives imposées par l'exploitant qu'est EDF. De...

  6. 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,...

  7. Une méthode pour estimer l’interception du rayonnement par un couvert bas : application au colza avant montaison

    Directory of Open Access Journals (Sweden)

    Denoroy Pascal

    2002-01-01

    introduire dans l’équation 2 un paramètre représentant le taux de couverture du sol. Si l’estimation par mesure directe de epsiloni et donc l’estimation de k sont assez simples, au moins dans le principe pour un couvert développé en hauteur (colza après montaison [3], une telle mesure devient beaucoup plus complexe dans le cas d’un couvert discontinu et bas. Dans ce milieu hétérogène (et souvent dans des conditions hivernales sévères, une distribution représentative des capteurs de rayonnement est difficile, les risques de perturbation de la mesure (salissure des capteurs, déréglages sont élevés. Plusieurs études ont déjà traité de epsiloni et k dans le cas du colza [3-7]. Elles sont fondées sur des mesures d’interception du rayonnement et concernent des couverts fermés, après montaison. Une autre approche consiste à effectuer un calcul précis de PARi avec des modèles détaillés utilisant une description complète des paramètres (géométriques et radiatifs du feuillage, et du rayonnement incident [8]. Mais les données nécessaires sont alors nombreuses, complexes à obtenir et donc généralement non disponibles en expérimentation. Pour répondre aux besoins de calcul de l’interception du rayonnement dans les phases d’installation du colza, cet article présente une méthode permettant de calculer epsiloni en tenant compte des principales caractéristiques de la morphologie du couvert et du régime radiatif auquel ce dernier est soumis. Les données nécessaires sont limitées : l’indice foliaire, les taux de couverture du sol (deux définitions, la latitude du lieu considéré, la date et le rayonnement incident quotidien. Ce calcul permet une estimation du coefficient moyen d’extinction k (équation 2. On verra que k peut être corrélé à l’IF, la période de l’année et la latitude du lieu, ce qui permet de proposer une estimation simple de k et donc un calcul simplifié de epsiloni, adapté au cas des faibles IF

  8. 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

  9. Polarization of Bremsstrahlung; Polarisation du rayonnement de freinage

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

    The numerical results for the polarization of Bremsstrahlung are presented. The multiple scattering of electrons in the target is taken into account. The angular-and photon energy dependences are seen on the curves for an incident 25 MeV electron energy. (Author) [French] Le taux de polarisation d'un spectre de rayonnement de freinage est calcule pour une cible d'epaisseur finie en tenant compte de la diffusion multiple des electrons dans la cible. Les courbes sont tracees pour les electrons incidents d'energie 25 MeV, pour differentes energies de photons, et a differents angles. (auteur)

  10. Erika: evaluation of residual sanitary risks linked to the beaches-going after cleaning-up; Erika: evaluation des risques sanitaires residuels lies a la frequentation des plages apres depollution

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The aim of this study is to evaluate the sanitary risks for the populations frequenting the coast beaches affected by the fuel oils of the tanker Erika, after their cleaning up. This quantitative evaluation of sanitary risks is led according to a protocol developed jointly between the two institutes ( the national institute of industrial environment and risks, I.N.E.R.I.S., and the national institute of sanitary watch I.n.V.S.). It does not give the risks in function the residual pollution level of concerned beaches but supplies to the authorities elements of scientific information in order to allow them to choose criteria appropriate for the management of eventual residual risks. (N.C.)

  11. 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.

  12. 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

  13. 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.

  14. 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

  15. Study of {gamma} radiation from uranium rods during deactivation; Etude du rayonnement {gamma} des barres d'uranium en court de desactivation

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

    The classical formulae giving the {gamma} activities of the fission products contained in a uranium rod after unloading from the pile are reviewed without being proved. The knowledge of these activities makes it possible, by means of the method proposed here, to determine the intensities of ionisation at a point outside the rod, and thus to establish {gamma} radiation diagrams. The different parameters introduced in the calculation are geometric (dimensions of the bars and coordinates of the point considered), energetic (power at which the bar has been irradiated) and temporal (duration of the irradiation and deactivation). A numerical example follows the demonstration of the general formulae, {gamma} flux measurements carried out in the deactivation well of P2 (Saclay pile) define the accuracy of the method. In conclusion, it is suggested that radiation diagrams be used in (planning the use of) industrial irradiators for radiochemical polymerisation or the preservation of food products. (author) [French] On rappelle sans demonstration les formules classiques donnant les activites {gamma} des produits de fission contenus dans une barre d'uranium apres defournement. La connaissance de ces activites permet par la methode proposee de passer aux intensites d'ionisation en un point exterieur a la barre et d'etablir ainsi des diagrammes de rayonnement {gamma}. Les differents parametres introduits dans le calcul sont d'ordre geometrique (dimensions des barres et coordonnees du point considere), d'ordre energetique (puissance a laquelle la barre a ete irradiee) et fonction du temps (duree d'irradiation et de desactivation). Un exemple numerique fait suite a la demonstration des formules generales. Des mesures de flux {gamma} effectuees au puits de desactivation de P2 (pile de Saclay) fixent le degre d'approximation de la methode. En conclusion, on suggere l'utilisation des diagrammes de rayonnement dans l'etablissement de projets d'irradiateurs industriels pour les

  16. 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)

  17. Agent principal de rayonnement et de mobilisation stratégiques (h/f ...

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

    Dans ce contexte, l'agent principal de rayonnement et de mobilisation stratégiques élabore des démarches qui permettent de mobiliser les chercheurs et les principaux utilisateurs de la recherche dans les régions visées, afin de faire en sorte qu'ils aient l'occasion de participer à la définition des besoins de recherche dans ...

  18. Coincidence measurements with the use of detectors measuring the energy of the radiances (proportional meters and scintillation counter); Mesures de coincidences avec utilisation de detecteurs mesurant l'energie des rayonnements (compteurs proportionnels et compteur a scintillations)

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-07-01

    In the setting of the realization of a set of installations permitting of the measures of coincidences between sorted radiances according to their energies, an installation understanding a proportional counter and a scintillation counter has been constructed and optimized. It has been used to do some measures of coincidences between X{sub K} photons and photons {gamma} issued at the time of the radioactive transformation of the selenium 75 (electronic capture). The efficiency of the proportional meter has been determined roughly. Besides, a proportional counter of solid angle neighboring of 4{pi} was able to achieve measures of coincidences while only doing one selection of amplitudes: indeed, the simultaneity of the detection of two radiances appear by an impulse whose amplitude is the sum of the amplitudes of the impulses resulting from each of the studied radiations. This method, applied to the coincidences between X-rays, permitted to bring the information on the diagram of decay of the arsenic 73. Besides, the coefficient of internal conversion of a consecutive transition to this decay has been valued. (author) [French] Dans le cadre de la realisation d'une serie de montages permettant des mesures de coincidences entre rayonnements tries d'apres leurs energies, un montage comprenant un compteur proportionnel et un compteur a scintillations a ete construit et mis au point. Il a ete utilise pour effectuer quelques mesures de coincidences entre photons X{sub K} et photons {gamma} emis lors de la transformation radioactive du selenium 75 (capture electronique). L'efficacite du compteur proportionnel a ete approximativement determinee. De plus, un compteur proportionnel d'angle solide voisin de 4{pi} a pu etre utilise pour realiser des mesures de coincidences en n'effectuant qu'une selection d'amplitudes: en effet, la simultaneite de la detection de deux rayonnements se manifeste par une impulsion dont l'amplitude est la somme des amplitudes des impulsions

  19. 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

  20. 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

  1. The radiance of France; nuclear power and national identity after world war 2; Le rayonnement de la France; energie nucleaire et edentite nationale apres la seconde guerre mondiale

    Energy Technology Data Exchange (ETDEWEB)

    Hecht, G. [Michigan Univ., Ann Arbor, MI (United States)

    2004-07-01

    This book discusses the early history of French nuclear power within its social and political context from the end of world war 2 to 1970. The author describes the creation of the nuclear reactors, the work at the reactor sites, and the impact of nuclear power on local communities. Information on the French atomic bomb program is also included. The conflicts and negotiations surrounding the nuclear programs are detailed, and the importance of the programs to French national identity is made clear. An excellent bibliography and extensive footnotes are provided.

  2. 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.

  3. 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.

  4. 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...

  5. 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.

  6. Uses of radioactive isotopes and radiation sources in biological studies in U. A. R; Utilisation des radioisotopes et des sources de rayonnement dans les etudes biologiques en RAU

    Energy Technology Data Exchange (ETDEWEB)

    Hashish, S. E. [Radiobiology Department, U. A. R. Atomic Energy Establishment, Cairo, United Arab Republic (Egypt)

    1970-01-15

    An attempt is made to give examples rather than a review of the uses of radioactive isotopes and radiation sources in biological studies in U.A.R. Studies along these lines started early in 1955 and are still progressing. The prospects of future developments and improvements are unlimited. The studies are classified according to the radio technique adopted. The techniques so far used in U.A.R. include all the techniques known elsewhere. Some detailed modifications and combinations of more than one technique have been successfully introduced. Both in basic and applied biological studies, one or more of the following techniques have been applied, namely tracer technique, isotopic dilution analysis, autoradiography, radiochromatography and electrophoresis, double or multi-bioassays, radioactivation analysis, neutron absorption analysis, and use of different radiation source for somatic and/or genetic effect studies. Mass spectrometry for stable isotopic studies in the field of biology has been recently used. Studies undertaken in the applied fields of biology e. g, in medicine (diagnosis and therapy) and agriculture (soil, plant and animal) have proved extremely valuable from the practical and developmental points of view. (author) [French] Le mémoire a pour objet d'illustrer plutôt que d'exposer systématiquement les utilisations des radioisotopes et des sources de rayonnement dans des études biologiques en République Arabe Unie. Ces études, entreprises au début de 1955, se poursuivent. Les possibilités de développement et de perfectionnement sont illimitées. Les études sont classées d'après la radiotechnique adoptée. Les techniques régulièrement utilisées jusqu' à présent en République Arabe Unie couvrent toute la gamme des techniques connues ailleurs. On a réussi à apporter des modifications de détail et à combiner plusieurs techniques. Dans les études de biologie tant fondamentale qu' appliquée, une ou plusieurs des techniques suivantes

  7. 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.

  8. 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

  9. On the honeybee resistance to gamma radiation; Sur la resistance au rayonnement gamma de l'abeille ouvriere

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G.; Lecomte, J. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Section des Applications des Radioelements, Centre d' Etudes Nucleaires, Saclay, Station de Recherches Apicoles, Bures-sur-Yvette (France)

    1960-07-01

    The honeybee, when irradiated by gamma radiations from a cobalt-60 source can stand a 18000 r dose without any apparent harm. Noticeable harm is observed for 90000 r. while immediate death of 100% of the individuals is obtained with a 200000 r dose. The physiological condition of the honeybee plays an important role in its resistance to gamma radiation. Reprint of a paper published in Annales de l'abeille, IV, 1959, p. 285-290 [French] L'Abeille butineuse irradiee par le rayonnement gamma issu d'une source de Cobalt 60 supporte sans dommages apparents une dose de 18000 r. Des dommages tres appreciables sont observes pour 90000 r. Une dose de 200000 r entraine la mort immediate de 100% des individus. L'etat physiologique de l'Abeille joue un role important dans la resistance au rayonnement gamma. Reproduction d'un article publie dans Annales de l'abeille, IV, 1959, p. 285-290.

  10. Evaluation of the residual sanitary risk for people spending time on the beaches polluted by the Erika fuel, after the depollution; Evaluation du risque sanitaire residuel pour les populations frequentant les plages polluees par le fioul rejete par l'ERIKA, apres depollution

    Energy Technology Data Exchange (ETDEWEB)

    Dor, F.; Gourier-Frery, C.; Zmirou, D. [Institut de veille sanitaire, 94 - Saint-Maurice (France); Cicolella, A.; Bonnard, R.; Dujardin, R. [Institut National de l' Environnement Industriel et des Risques, 60 - Verneuil en Halatte (INERIS) (France)

    2004-07-01

    This study aims to evaluate the short dated and long dated sanitary risks for adults and children who are going to spend time on the beach affected by the Erika fuel, after the depollution. 36 beaches were selected and 7 beaches which were not polluted, were taking as a reference. The methodology, the analysis of the data and the results are described. (A.L.B.)

  11. 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.

  12. 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.

  13. 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

  14. 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

  15. 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.

  16. Study of cerenkov radiation. Production of {gamma} rays by electron accelerators; Etude du rayonnement de freinage. Production de rayons {gamma} par des accelerateurs d'electrons

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    This study is a critical comparison of the theories of Bremsstrahlung. Experimental results obtained by the production of {gamma} radiation with electron accelerators are compared to the theoretical results in order to estimate the extent to which the various theories are valid. (author) [French] Cette etude est une synthese des theories du rayonnement de freinage. Des resultats experimentaux, obtenus par la production de rayonnements {gamma} avec des accelerateurs d'electrons, sont compares aux resultats theoriques afin d'evaluer les domaines de validite des diverses theories. (auteur)

  17. 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.

  18. 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

  19. 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.

  20. 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

  1. 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.

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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 ...

  7. 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.

  8. 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 ...

  9. 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.

  10. The study of some thiazinic and indaminic dye syntheses induced by ionising radiation; Etude de quelques syntheses de colorants thianziniques et indaminiques amorcees par les rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-03-15

    grace a leur spectre d'absorption apres qu'ils aient ete separes du milieu reactionnel par chromatographie d'adsorption ou d'echange d'ions; d'autres produits de la radiolyse, chlorure d'ammonium et eau oxygenee, ont ete egalement caracterises. Au cours d'une etape ulterieure, une variation systematique des parametres physico-chimiques a permis de determiner les conditions les plus favorables a la radiosynthese; les rendements radiochimiques maximum obtenus ont pour valeurs respectives: G (Violet de Lauth) = 1,65; G (Bleu de Methylene) = 1,75. En outre, l'etude de l'influence sur le rendement radiochimique des reactifs amines differemment substitues a fait apparaitre la possibilite de synthetiser par voie radiochimique le Vert de Bindschedler et le Bleu de Wurster. Enfin la decouverte d'un compose intermediaire fondamental, le Rouge de Wurster, ainsi que l'etude cinetique de la synthese chimique du Bleu de Methylene ont permis de determiner les principales etapes du Bleu de Methylene reactionnel et de preciser la part qui revenait aux rayonnements ionisants dans le cas de la synthese par voie radiochimique. (auteur)

  11. 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)

  12. 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

  13. 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

  14. 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)

  15. 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 ...

  16. 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)

  17. 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 ...

  18. 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...

  19. Experimental studies on the X-radiation from a high-intensity annular discharge; Etudes experimentales sur le rayonnement X d'une decharge annulaire a forte intensite

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    Under certain conditions, a very penetrating X-radiation is emitted at the start of a stabilised annular discharge. A number of experimental observations have been made using a pyrex toroid filled with deuterium or argon. The value of the stabilising magnetic field and the pressure have a very important influence on the intensity of the X-radiation emitted. The placing of an obstacle such as a magnetic mirror at a point of the torus can prevent the acceleration of runaway electrons during successive revolutions, and X-ray emission disappears. (author) [French] Un rayonnement X tres penetrant est emis dans certaines conditions au debut d'une decharge annulaire stabilisee. Un certain nombre d'observations experimentales ont ete faites a l'aide d'un tore en pyrex rempli de deuterium ou d'argon. La valeur du champ magnetique stabilisateur et la pression jouent un role tres important sur l'intensite du rayonnement X emis. La disposition d'un obstacle tel qu'un miroir magnetique en un point du tore peut empecher l'acceleration d'electrons decouples au cours de revolutions successives et l'emission de rayonnement X disparait. (auteur)

  20. Dosimetry techniques of thermal neutrons and {gamma} radiation in reactor cores; Techniques de dosimetrie des neutrons thermiques et du rayonnement {gamma} dans les piles

    Energy Technology Data Exchange (ETDEWEB)

    Sutton, J; Draganic, I; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    Chemical studies under radiation done in the reactor cores require to be followed by dosimetry. When the irradiations are done in the reflector, one can limit to the measure of the {gamma} and the neutron radiation. For the dosimetry of the {gamma} radiation, a dosimeter of ferrous sulfate is convenient until doses of about 10{sup 6} rep. The use of aired oxalic acid solutions permits to reach 10{sup 7} rep. The dosimetry of thermal neutrons has been made with solutions of cobalt sulphate or paper filter impregnated with this salt. The total chemical effect of the {gamma} and of the slow neutrons radiation is obtained with solutions of ferrous sulfate added with lithium sulphate. (M.B.) [French] Les etudes de chimie sous radiation faites dans les piles exigent d'etre suivies par dosimetrie. Lorsque les irradiations sont effectues dans le reflecteur, on peut se limiter a doser le rayonnement {gamma} et les neutrons. Pour la dosimetrie du rayonnement {gamma}, un dosimetre a sulfate ferreux convient jusqu'a des doses d'environ 10{sup 6} rep. L'emploi de solutions aerees d'acide oxalique permet d'atteindre 10{sup 7} rep. La dosimetrie des neutrons thermiques a ete faite avec des solutions de sulfate de cotalt ou du papier filtre impregne de ce sel. L'effet chimique total du rayonnement {gamma} et des neutrons lents est obtenu avec des solutions de sulfate ferreux additionne de sulfate de lithium. (M.B.)

  1. 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

  2. Installation for analytic chemistry under irradiation; Installation de chimie analytique sous rayonnement

    Energy Technology Data Exchange (ETDEWEB)

    Fradin, J; Azoeuf, P; Guillon, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-07-01

    An installation has been set up for carrying out manipulations and chemical analyses on radioactive products. It is completely remote-controlled and is of linear shape, 15 metres long; it is made up of three zones: - an active zone containing the apparatus, - a rear zone giving access to the active zone, - a forward zone independent of the two others and completely protected from which the remote-control of the apparatus is effected. The whole assembly has been designed so that each apparatus corresponding to an analytical technique is set up in a sealed enclosure. The sealed enclosures are interconnected by a conveyor. After three years operation, a critical review is now made of the installation. (authors) [French] L'installation a ete realisee pour effectuer des manipulations et des analyses chimiques sur des produits radioactifs. Elle est totalement telecommandee et se presente sous une forme lineaire de 15 metres de longueur et comporte trois zones: - une zone active d'appareillage, - une zone arriere d'intervention, - une zone avant independante des deux premieres et totalement protegee, ou s'operent les telecommandes de l'appareillage. L'ensemble a ete concu de facon a ce que chaque appareillage correspondant a une technique d'analyse soit implante dans une enceinte etanche. Les enceintes etanches sont reliees entre elles par un convoyeur. Apres trois annees de fonctionnement nous faisons le bilan et les critiques de l'installation. (auteurs)

  3. 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

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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.

  9. 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

  10. Effects of Ionizing Radiation on Insects and Other Arthropods; Effet des rayonnements ionisants sur les insectes et autres arthropodes; Vozdejstvie ioniziruntsej radiatsii na nasekomykh i drugikh chlenistonogikh; Efectos de las radiaciones ionizantes sobre los insectos y otros artropodos

    Energy Technology Data Exchange (ETDEWEB)

    Stone, William E. [United States Department of Agriculture Laboratories, Mexico City, D.F (Mexico)

    1963-09-15

    'eradication des insectes. L'auteur analyse les resultats obtenus dans la campagne d'eradication de la lucilie bouchere Cochliomyia hominivorax Cqrl. aux Etats-Unis, ainsi que dans des etudes visant a produire des souches vigoureuses, marquees genetiquement en vue d'identifier facilement les mouches steriles apres leur lacher. Il etudie aussi les resultats de recherches sur differents sujets: effets des rayonnements sur six autres especes nuisibles aux fruits, aux legumes, aux cultures et aux forets, sur trois especes qui s'attaquent au cheptel et sur trois especes qui sont particulierement nuisibles a l'homme; effets des rayonnements sur le scorpion Centruroides limpidus Karsch et sur la tique Amblyomma americanium L.; possibilite d'utiliser les rayonnements ionisants pour traiter - comme mesure de quarantaine - les fruits et legumes attaques par les mouches des fruits et les mangues attaquees par le charancon de la mangue Sternochetus mangiferae Fabricius. (author) [Spanish] Actualmente se estudia la posibilidad de recurrir a la radioesterilizacion para exterminar a diversos insectos que atacan al hombre, a los animales y a las plantas. Las primeras investigaciones han demostrado que las radiaciones ionizantes producen esterilidad, y que las dosis necesarias varian considerablemente. Tambien hacen pensar que los daflos producidos por las radiaciones pudieran en algunos casos impedir que se aplique el metodo a ciertos insectos. Con frecuencia, el obstaculo principal es la falta de metodos de cria de los insectos en gran escala. En otros casos, el insecto se da con tal abundancia que no es posible aplicar esta tecnica sin antes tratar por otros medios la zona infestada a fin de reducir el numero de insectos. A pesar de todas las dificultades, el metodo de la radioesterilizacion es uno de los mejores, cuando las condiciones son favorables. Tambien se puede utilizar para retrasar el desarrollo de la plaga hasta despues de la cosecha. La memoria informa sobre la influencia de las

  11. 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...

  12. 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...

  13. 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

  14. 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.

  15. Modelling solar radiation interception in row plantation. 3. Application to a traditional vineyard; Modélisation de l’interception des rayonnements solaires dans une culture en rangs. 3. Application à une vigne traditionnelle

    Energy Technology Data Exchange (ETDEWEB)

    Sinoquet, H. [Institut National de la Recherche Agronomique, Pointe a Pitre (France); Valancogne, C.; Lescure, A.; Bonhomme, R.

    1992-07-01

    A previously described model of solar radiation interception was applied to a spatially discontinuous canopy: that of a traditional vineyard in which the classical terms of the radiative balance and the spatial distribution of the radiation transmitted to the soil were measured. Comparison of measured and simulated data gave satisfactory agreement for reflected radiation (fig 4), but major discrepancies appeared for mean transmitted radiation (fig 5). The use of small stationary sensors for measuring the transmitted radiation explains the latter observation, since most of the time they measured radiation received on the ground in the sunflecks or in the shaded area rather than mean radiation. This was verified by comparing the measured and simulated spatial distribution of transmitted radiation (figs 7, 8). Finally, the influence of the woody parts which were not taken into consideration in the model was clearly identified : it significantly reduced the transmission of incident radiation (fig 9), and to a greater degrees the closer the sensor was to the vegetation row. (author) [French] Un modèle d’interception du rayonnement solaire décrit précédemment est appliqué à un couvert spatialement discontinu : une vigne traditionnelle sur laquelle ont été mesurés les termes classiques du bilan radiatif et la distribution spatiale du rayonnement transmis au sol. La comparaison des mesures au modèle révèle un ajustement satisfaisant pour le rayonnement réfléchi (fig 4), mais assez médiocre pour le rayonnement transmis moyen (fig 5). Ceci est expliqué par l’utilisation de capteurs ponctuels qui, en raison de leur taille, mesurent plus souvent le rayonnement reçu au sol dans les taches de soleil ou les zones d’ombre qu’un rayonnement moyen. Ceci est vérifié en comparant les distributions mesurées et calculées du rayonnement transmis au sol (figs 7 et 8). Enfin, l’influence des parties ligneuses, non prise en compte dans le modèle, est

  16. 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

  17. 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

  18. 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...

  19. Gamma radiation in space and in the atmosphere; Rayonnement gamma dans l'espace et dans l'atmosphere

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-07-01

    We have shown that the {gamma} radiation existing in the atmosphere is caused mainly by the Bremsstrahlung of the electrons of the electromagnetic cascades ({approx} 50 per cent of the measured radiation), by the 511 keV radiation produced by the annihilation of positrons created in cascades (8 per cent of the measured intensity) and by the Compton {gamma} degradation of this line (30 per cent of the measured intensity). The rest, slightly over 10 per cent, must be attributed to secondary causes such as the nuclear de-excitation {gamma} to the internal Bremsstrahlung of charged particles created in nuclear stars, and to charged particles crossing our detector, since the latter was not fitted with a device for rejecting these particles. Experiments carried out in rockets at Colomb-Bechar confirm these results and have made it possible to detect and measure a primary {gamma} radiation having an intensity of {approx} 2 {gamma} cm{sup 2} s{sup -1} above 100 keV. The primary spectrum obeys an approximate E{sup -2} law. (author) [French] Nous avons montre que le rayonnement {gamma} existant dans l'atmosphere est provoque principalement por le bremsstrohlung des electrons des cascades electromagnetiques ({approx} 50 pour cent du rayonnement mesure), au rayonnement 511 keV provoque par l'annihilation des positrons crees dans les cascades (8 pour cent de l'intensite mesuree) et aux {gamma} de degradation Compton de cette raie (30 pour cent de l'intensite mesuree). Le reste, soit un peu plus de 10 pour cent, doit etre attribue a des causes secondaires telles que les {gamma} de desexcitation nucleaire, le bremsstrahlung interne des particules chargees creees dans les etoiles nucleaires, et aux particules chargees traversant notre detecteur car celui-ci ne comportait pas de dispositif de rejet de ces particules. Les experiences faites en fusees a Colomb-Bechar ont confirme ces resultats et permis de detecter et mesurer un rayonnement {gamma} primaire dont l

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. 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)

  8. Calculs de doses générées par les rayonnements ionisants principes physiques et codes de calcul

    CERN Document Server

    Vivier, Alain

    2016-01-01

    Cet ouvrage et les codes associés s’adressent aux utilisateurs de sources de rayonnements ionisants : techniciens, ingénieurs de sécurité, personnes compétentes en radioprotection, mais aussi médecins, chercheurs, concepteurs, décideurs… Les contraintes croissantes liées à la radioprotection rendent indispensables l’utilisation de codes de calcul permettant d’évaluer les débits de doses générées par ces sources et la façon dont on peut s’en protéger au mieux. De nombreux codes existent, dont certains restent des références incontournables, mais ils sont relativement complexes à mettre en oeuvre et restent en général réservés aux bureaux d’études. En outre, ces codes sont souvent des « boîtes noires » qui ne permettent pas de comprendre la physique sous-jacente. L’objectif de cet ouvrage est double : - Exposer les principes physiques permettant de comprendre les phénomènes à l’oeuvre lorsque la matière est irradiée par des rayonnements ionisants. Il devient al...

  9. 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...

  10. 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

  11. 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

  12. 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.

  13. 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...

  14. 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...

  15. 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)

  16. Assessment of risks associated to ionizing radiations: lung cancers after domestic radon exposure and thyroid cancers after accidental exposure to radioactive iodines; Evaluation des risques associes aux rayonnements ionisants: cancers du poumon apres exposition domestique au radon et cancers de la thyroide apres exposition accidentelle aux iodes radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Catelinois, O

    2004-09-15

    The aim of this work is to develop a critical analysis of quantitative risk assessment in the field of ionizing radiation and to provide new estimates of attributable risks for particular situations of environmental exposure to ionizing radiation. This work is based on knowledge about dose-response relationships and ionizing radiation exposure of the general population. The work focuses on two different situations that both present an important interest for public health: lung cancer associated with domestic radon exposures (natural situation) and thyroid cancer associated with the Chernobyl accident fallout (accidental situation). The assessment of lung cancer risk associated with domestic radon exposure considers 10 dose-response relationships resulting from miner cohorts and case-control studies in the general population. A critical review of available data on smoking habits has been performed and allowed to consider the interactions between radon and tobacco. The exposure data come from measurements campaigns carried out since the beginning of the 1980 by the Institute for Radiation protection and Nuclear Safety and the Health General Directory in France. The French lung cancer mortality data are provided by the I.N.S.E.R.M.. Estimates of the number of attributable cancers are carried out for the whole country, stratified by 8 large regions (Z.E.A.T.) and by 96 departments for the year 1999 allowing to perform a sensibility analysis according to the geographical level of calculation. Uncertainties associated to risk coefficients and exposures have been quantified and it's impact on risk estimates is calculated. The estimated number of deaths attributable to domestic radon exposure ranges from 543 (90% uncertainty interval (U.I.): 75-1,097) to 3,108 (90% U.I.: 2,996-3,221). The corresponding risk fractions range from 2.2% (90% U.I.: 0.3%-4.4%) to 12.4% (90% U.I.: 11.9%-12.8%). The assessment of thyroid cancer risk in the most exposed area of France due to the Chernobyl nuclear power plant accident fallout, is based on the excess relative risk model published by E. Ron et al. in 1995. The target population is composed of all children younger than 15 years and living in the eastern part of France at the time of the accident (26 April 1986). The incidence rates between 1978 and 1997 are analysed and forecasted up to 2007 using age-period-cohort models. Thyroid doses are estimated from all available data about the contamination in France from the Chernobyl fallout/ The risks characterization is carried out by considering various scenarios on the projection of spontaneous incidence rates, the effectiveness of internal exposures compared to external ones and the levels of radioactive deposits. Uncertainties to the risk coefficient, the expected spontaneous incidence rates and the thyroid dose are considered. The estimated number of thyroid cancer cases in excess between 1991 and 2007 for the target population ranges from 5 (90% U.I.: 1-15) to 63 (90% U.I. 12-180). In comparison, depending on the scenario of spontaneous rate projection, the number of spontaneous cancer cases should range from 894 (90% U.I.: 869-920) to 1,716 (90% U.I.:1,691-1,741) between 1991 and 2007. The results show that the thyroid cancer incident rate increase observed in France during last 20 years cannot be explained by the Chernobyl fallout. The work provides an adaptation of the classical risk assessment method integrating each of its step such as a discussion about the choice of the dose-response relationship. The data analysis considers the interaction between ionizing radiation and other risk factors, a spontaneous incidence rate projection and a quantification of uncertainties. This work provides new results showing the importance of the choice of the dose-response relationship, of the consideration of the spontaneous incidence trend and of the quantification of uncertainties in risk assessment. In conclusion, this work provides new knowledge for public health by the analysis of enlarged epidemiological data. (author)

  17. Assessment of risks associated to ionizing radiations: lung cancers after domestic radon exposure and thyroid cancers after accidental exposure to radioactive iodines; Evaluation des risques associes aux rayonnements ionisants: cancers du poumon apres exposition domestique au radon et cancers de la thyroide apres exposition accidentelle aux iodes radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Catelinois, O

    2004-09-15

    The aim of this work is to develop a critical analysis of quantitative risk assessment in the field of ionizing radiation and to provide new estimates of attributable risks for particular situations of environmental exposure to ionizing radiation. This work is based on knowledge about dose-response relationships and ionizing radiation exposure of the general population. The work focuses on two different situations that both present an important interest for public health: lung cancer associated with domestic radon exposures (natural situation) and thyroid cancer associated with the Chernobyl accident fallout (accidental situation). The assessment of lung cancer risk associated with domestic radon exposure considers 10 dose-response relationships resulting from miner cohorts and case-control studies in the general population. A critical review of available data on smoking habits has been performed and allowed to consider the interactions between radon and tobacco. The exposure data come from measurements campaigns carried out since the beginning of the 1980 by the Institute for Radiation protection and Nuclear Safety and the Health General Directory in France. The French lung cancer mortality data are provided by the I.N.S.E.R.M.. Estimates of the number of attributable cancers are carried out for the whole country, stratified by 8 large regions (Z.E.A.T.) and by 96 departments for the year 1999 allowing to perform a sensibility analysis according to the geographical level of calculation. Uncertainties associated to risk coefficients and exposures have been quantified and it's impact on risk estimates is calculated. The estimated number of deaths attributable to domestic radon exposure ranges from 543 (90% uncertainty interval (U.I.): 75-1,097) to 3,108 (90% U.I.: 2,996-3,221). The corresponding risk fractions range from 2.2% (90% U.I.: 0.3%-4.4%) to 12.4% (90% U.I.: 11.9%-12.8%). The assessment of thyroid cancer risk in the most exposed area of France due to the Chernobyl nuclear power plant accident fallout, is based on the excess relative risk model published by E. Ron et al. in 1995. The target population is composed of all children younger than 15 years and living in the eastern part of France at the time of the accident (26 April 1986). The incidence rates between 1978 and 1997 are analysed and forecasted up to 2007 using age-period-cohort models. Thyroid doses are estimated from all available data about the contamination in France from the Chernobyl fallout/ The risks characterization is carried out by considering various scenarios on the projection of spontaneous incidence rates, the effectiveness of internal exposures compared to external ones and the levels of radioactive deposits. Uncertainties to the risk coefficient, the expected spontaneous incidence rates and the thyroid dose are considered. The estimated number of thyroid cancer cases in excess between 1991 and 2007 for the target population ranges from 5 (90% U.I.: 1-15) to 63 (90% U.I. 12-180). In comparison, depending on the scenario of spontaneous rate projection, the number of spontaneous cancer cases should range from 894 (90% U.I.: 869-920) to 1,716 (90% U.I.:1,691-1,741) between 1991 and 2007. The results show that the thyroid cancer incident rate increase observed in France during last 20 years cannot be explained by the Chernobyl fallout. The work provides an adaptation of the classical risk assessment method integrating each of its step such as a discussion about the choice of the dose-response relationship. The data analysis considers the interaction between ionizing radiation and other risk factors, a spontaneous incidence rate projection and a quantification of uncertainties. This work provides new results showing the importance of the choice of the dose-response relationship, of the consideration of the spontaneous incidence trend and of the quantification of uncertainties in risk assessment. In conclusion, this work provides new knowledge for public health by the analysis of enlarged epidemiological data. (author)

  18. Study of the texture of porous solids using a technique of {gamma} ray absorption; Application de l'absorption du rayonnement {gamma} a l'etude de la texture des solides poreux

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-01-01

    A technique, which enables us to measure locally total porosity, open porosity and pore size distribution is developed. The total porosity is calculated from the bulk density. A gamma absorption gauge is set up fitted with a Cs137 source. This enables the determination of the density by layers of carbonaceous samples in a practically automatic way. By taking adequate precautions it is possible to obtain the density with a maximum error {delta}{rho} {<=} 0,005 g/cm{sup 3}. The open porosity is evaluated by the absorption method after impregnation with bromoform. A new mercury porosimeter is developed using the absorption probe for the measurement of mercury infiltrated into the porous sample. Due to the localized character of exploration by this technique, the variations of porous texture in a heterogeneous sample can be studied. Used as a classical porosimeter, in the case of homogeneous samples, this apparatus is capable of exploring the equivalent diameters of pores between 500 {mu} and 0.14 {mu} with a maximum error {delta}P {<=} 0.002. The possibility of exploration of heterogeneous samples, with the facility of determination of porosities due to macro-pores combined with the non-limiting character of the method in the field of high pressures differentiates this apparatus from all the porosimeters of former conception. Examples of utilization of this technique in the case of graphite-gas reactions are presented. (author) [French] On a developpe une technique permettant la mesure localisee de la porosite totale, de la porosite ouverte et de la repartition de la taille de pores. La porosite totale est calculee a partir de la densite apparente. On a mis au point une jauge d'absorption du rayonnement gamma munie d'une source de Cs137. Celle-ci nous a permis de determiner la densite par couches d'echantillons cylindriques carbones d'une facon pratiquement automatique. En prenant les precautions adequates, il est possible d'obtenir la densite

  19. Study of the texture of porous solids using a technique of {gamma} ray absorption; Application de l'absorption du rayonnement {gamma} a l'etude de la texture des solides poreux

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-01-01

    A technique, which enables us to measure locally total porosity, open porosity and pore size distribution is developed. The total porosity is calculated from the bulk density. A gamma absorption gauge is set up fitted with a Cs137 source. This enables the determination of the density by layers of carbonaceous samples in a practically automatic way. By taking adequate precautions it is possible to obtain the density with a maximum error {delta}{rho} {<=} 0,005 g/cm{sup 3}. The open porosity is evaluated by the absorption method after impregnation with bromoform. A new mercury porosimeter is developed using the absorption probe for the measurement of mercury infiltrated into the porous sample. Due to the localized character of exploration by this technique, the variations of porous texture in a heterogeneous sample can be studied. Used as a classical porosimeter, in the case of homogeneous samples, this apparatus is capable of exploring the equivalent diameters of pores between 500 {mu} and 0.14 {mu} with a maximum error {delta}P {<=} 0.002. The possibility of exploration of heterogeneous samples, with the facility of determination of porosities due to macro-pores combined with the non-limiting character of the method in the field of high pressures differentiates this apparatus from all the porosimeters of former conception. Examples of utilization of this technique in the case of graphite-gas reactions are presented. (author) [French] On a developpe une technique permettant la mesure localisee de la porosite totale, de la porosite ouverte et de la repartition de la taille de pores. La porosite totale est calculee a partir de la densite apparente. On a mis au point une jauge d'absorption du rayonnement gamma munie d'une source de Cs137. Celle-ci nous a permis de determiner la densite par couches d'echantillons cylindriques carbones d'une facon pratiquement automatique. En prenant les precautions adequates, il est possible d'obtenir la densite avec une erreur maximale

  20. Research trends in radiobiology since 40 years. a new approach: the enzymatic repair function of DNA, internal factor in evolution of biological systems under irradiation; Etude des tendances des recherches en radiologie depuis 40 ans. Une nouvelle voie de recherche: la fonction de reparation enzymatique de l'ADN, facteur interne d'evolution des systemes biologiques sous rayonnement

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    'on croyait encore que les effets des rayonnements sur les systemes vivants etaient des effets directs, immediats, irreparables et definitifs. Depuis lors, on s'est rendu compte que les radiolesions pouvaient resulter d'effets indirects, etre tardives, reparables, et le plus souvent modifiables par des traitements chimiques ou biochimiques ad hoc. Cependant, la percee decisive en radiobiologie se situe entre 1962 et 1964, avec la decouverte que la cellule possede un mecanisme de defense active vis-a-vis de tout ce qui peut porter atteinte a l'integrite du patrimoine genetique inscrit dans la structure meme de l'ADN. L'existence d'une quatrieme fonction de l'ADN, celle d'auto-reparation, par voie enzymatique sous controle genetique, apporte enfin a la radiobiologie la base biologique moleculaire qui lui manquait pour sortir de la nuit 'phenomenologique' ou elle s'etait enfoncee apres l'abandon de la generalisation de la theorie de Lea, faute de preuve experimentale. Dans la seconde partie, cette fois prospective, de l'etude l'auteur tente une synthese elargie en considerant le role que peut jouer cette fonction de reparation de l'ADN non seulement du point de vue de la survie des systemes biologiques irradies en presence ou non d'agents modificateurs de dose ou mutagenes, mais aussi de celui de l'evolution naturelle ou artificielle de ces systemes sous rayonnement. Les donnees les plus recentes de la litterature sont en accord avec ce qui ne constitue encore qu'une hypothese generale de recherche. Des travaux portant sur les caracteres phenotypiques et genotypiques lies a l'acquisition de radioresistance gamma et UV, chez 'Escherichia coli K12', ont ete entrepris par l'auteur, en collaboration avec O. Tremeau en vue d'apporter une contribution experimentale nouvelle a cet egard. (auteur)

  1. 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)

  2. 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

  3. 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.

  4. 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.

  5. 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

  6. 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

  7. 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.

  8. 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…

  9. 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)

  10. 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)

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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).

  16. 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.

  17. 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

  18. 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...

  19. 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...

  20. 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

  1. [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.

  2. 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.

  3. 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

  4. 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.

  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. Study of gamma radiation between 0.1 and 1.0 MeV in the earth's atmosphere; Etude du rayonnement gamma entre 0,1 et 1 Mev dans l'atmosphere terrestre

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-01-01

    The present work is devoted to some of the particular problems arising in the detection and localisation of sources of gamma radiation situated outside the earth's atmosphere. These weak sources can only be detected and localized if care is taken to eliminate gamma and particle radiations coming from other sources in the earth's atmosphere and in space. In order to separate the various sources of background noise, generally much stronger than the radiation under study, use is made of a directional detector whose characteristics are determined as described in the first part of the following report. The closest diffuse source considered is that constituted by the earth's atmosphere. Its detailed study will make it possible both to eliminate its effect when sources outside the earth are to be measured, and to predict the amount of secondary gamma radiation emitted by the same process in other celestial bodies, the moon in particular. This work considered in the 2. and 3. parts of the report. (author) [French] La presente etude est consacree a certains des problemes particuliers poses par la detection et la localisation des sources de rayonnement gamma situees hors de l'atmosphere terrestre. Ces sources faibles ne peuvent etre detectees et localisees que si l'on se protege des rayonnements gamma et particulaires provenant d'autres sources situees dans l'atmosphere terrestre et dans l'espace. Pour separer ces divers composants parasites, en general beaucoup plus intenses que le rayonnement a etudier, nous emploierons un detecteur directif dont nous determinons les caracteristiques dans la premiere partie de l'expose qui suit. La source diffuse la plus proche que nous considerons comme parasite est constituee par l'atmosphere terrestre. Son etude detaillee nous permettra d'une part de nous en proteger lorsque nous voudrons etudier les sources {gamma} extra-terrestres, d'autre part de prevoir le rayonnement gamma secondaire emis par le meme processus pour les autres corps

  6. Amorphous silicon cells for the measurement of photosynthetically active radiation; Utilisation des cellules au silicium amorphe pour la mesure du rayonnement photosynthétiquement actif (400-700 nm)

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M. [Institut National de la Recherche Agronomique, Thiverval-Grignon (France); Bonchretien, P.; Allirand, J. M.; Gosse, G.

    1989-07-01

    Numerical simulation and experimental measurements from amorphous silicon cells in comparison with these now used in ecophysiology illustrate the interest of amorphous silicon cells for the measurement of PAR incident, reflected, and transmitted below the canopy [French] La simulation et la confrontation expérimentale ces réponses des cellules au silicium amorphe par rapport à celles des capteurs existants montrent l’intérêt des cellules au silicium amorphe pour la mesure du rayonnement PAR (exprimé en densité de flux de photons) incident, réfléchi et transmis sous un couvert végétal.

  7. Study of gamma radiation between 0.1 and 1.0 MeV in the earth's atmosphere; Etude du rayonnement gamma entre 0,1 et 1 Mev dans l'atmosphere terrestre

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-01-01

    The present work is devoted to some of the particular problems arising in the detection and localisation of sources of gamma radiation situated outside the earth's atmosphere. These weak sources can only be detected and localized if care is taken to eliminate gamma and particle radiations coming from other sources in the earth's atmosphere and in space. In order to separate the various sources of background noise, generally much stronger than the radiation under study, use is made of a directional detector whose characteristics are determined as described in the first part of the following report. The closest diffuse source considered is that constituted by the earth's atmosphere. Its detailed study will make it possible both to eliminate its effect when sources outside the earth are to be measured, and to predict the amount of secondary gamma radiation emitted by the same process in other celestial bodies, the moon in particular. This work considered in the 2. and 3. parts of the report. (author) [French] La presente etude est consacree a certains des problemes particuliers poses par la detection et la localisation des sources de rayonnement gamma situees hors de l'atmosphere terrestre. Ces sources faibles ne peuvent etre detectees et localisees que si l'on se protege des rayonnements gamma et particulaires provenant d'autres sources situees dans l'atmosphere terrestre et dans l'espace. Pour separer ces divers composants parasites, en general beaucoup plus intenses que le rayonnement a etudier, nous emploierons un detecteur directif dont nous determinons les caracteristiques dans la premiere partie de l'expose qui suit. La source diffuse la plus proche que nous considerons comme parasite est constituee par l'atmosphere terrestre. Son etude detaillee nous permettra d'une part de nous en proteger lorsque nous voudrons etudier les sources {gamma} extra-terrestres, d'autre part de prevoir le rayonnement gamma

  8. 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

  9. 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

  10. 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

  11. Pulsed Irradiation Studies in Mice, Rats and Dogs; Etudes sur l'Exposition de la Souris, du Rat et du Chien a des Rayonnements Pulses; Impul'snoe obluchenie myshej, krys i sobak; Estudios sobre la Irradiacion Pulsante de Ratones, Ratas y Perros

    Energy Technology Data Exchange (ETDEWEB)

    Ainsworth, E. J.; Leong, G. F.; Kendall, K.; Alpen, E. L.; Albright, M. L. [US Naval Radiological Defense Laboratory. San Francisco, CA (United States)

    1964-05-15

    rayonnements emis par un reacteur TRIGA pour une etude comparative des taux de mortalite (DL{sup 30}{sub 50}) chez la souris et chez le chien exposes a des debits de dose moderes (40 ou 100 rad/min pour la souris et 23 rad/min pour le chien) ou a un rayonnement puise avec un debit de dose eleve ( Tilde-Operator 10{sup 6} rad/min pour la souris et Tilde-Operator 2,0 * 10{sup 5} rad/min pour le chien). Chez la souris, la DL{sup 30}{sub 50} pour des animaux exposes a des debits moderes de 40 rad/min (neutrons) ou de 100 rad/min (rayons gamma) n'etait pas significativement differente de la DL{sup 30}{sub 50} dans le cas d'une exposition au meme rayonnement puise. De meme, chez le chien, a la suite d'expositions aux neutrons seulement, on n'a pas constate de difference significative entre la DL{sup 30}{sub 50} pour les groupes exposes a 23 rad/min et la DL{sup 30}{sub 50} pour ceux qui avaient ete exposes a un rayonnement puise avec des debits de dose superieurs a 1,5 x 10{sup 5} rad/min. Les auteurs ont effectue d'autres etudes pour determiner si la guerison des radiolesions chez la souris, evaluee par la methode, est influencee par le debit de dose qui provoque la lesion subletale initiale. Ils ont compare les guerisons constatees 5 j et 14 j apres irradiation chez des groupes d'animaux exposes a des debits de 40 rad/min et de 9 x 10{sup 4} rad/min; ils ont constate que le degre de guerison ne dependait pas du debit de dose. (author) [Spanish] La radioletalidad en funcion de la dosis ha sido objeto de muchos estudios en el intervalo comprendido entre 1 rad/min hasta algunos centenares de rad/min, pero se poseen relativamente pocos datos acerca de las consecuencias biologicas de la exposicion a intensidades del orden de 10{sup 5} a 10{sup 6} rad/min. Los autores emplearon radiaciones emitidas por un reactor TRIGA para efectuar un estudio comparado de las reacciones de mortalidad aguda (DL{sup 30}{sub 50}) en ratones y perros irradiados con intensidades moderadas (40 o 100 rad

  12. 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

  13. 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.

  14. 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.

  15. Thermal and radiation induced polymerisation of carbon sub-oxide; Polymerisation thermique et sous rayonnement du sous-oxyde de carbone

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, Michel

    1964-03-15

    This research thesis addresses the study of the polymerisation of carbon sub-oxide (C{sub 3}O{sub 2}) in gaseous phase. As this work is related to other researches dealing with the reactions of the graphite-CO{sub 2} system which occur in graphite-moderated nuclear reactors, a first intention was to study the behaviour of C{sub 3}O{sub 2} when submitted to radiations. Preliminary tests showed that the most remarkable result of this action was the formation of a polymer. It was also noticed that the polymerisation of this gas was spontaneous however slower at room temperature. The research thus focused on this polymerisation, and on the formula of the obtained polymer. After some generalities, the author reports the preparation, purification and storage and conservation of the carbon sub-oxide. The next parts report the kinetic study of thermal polymerisation, the study of polymerisation under γ rays, the study of the obtained polymer by using visible, UV and infrared spectroscopy, electronic paramagnetic resonance, and semi-conductivity measurements [French] Le but de ce travail est l'etude de la polymerisation du sous-oxyde de carbone, C{sub 3}O{sub 2}, en phase gazeuse. Ce travail est en relation avec d'autres recherches concernant les reactions du systeme graphite-CO{sub 2} qui se produisent dans les reacteurs nucleaires de la filiere moderee au graphite. Notre premiere intention etait donc d'etudier le comportement de C{sub 3}O{sub 2} sous l'action des rayonnements. Or des essais preliminaires nous ont rapidement montre que le resultat le plus marquant de cette action etait l'obtention d'un polymere. On a egalement remarque que ce gaz polymerisait spontanement - quoique moins rapidement - a la temperature ambiante. Notre etude s'est donc circonscrite a cette polymerisation, avec ou sans rayonnements, ainsi qu'a son aboutissement: le polymere, dont nous avons tente d'eclaircir la formule. Au terme de cette etude, bien que certains points ne soient pas encore

  16. Studies on radiation-image detectors; Etudes sur les detecteurs a images de rayonnements; Izuchenie detektorov izobrazheniya radiatsii; Estudios sobre detectores de radiaciones productores de imagenes

    Energy Technology Data Exchange (ETDEWEB)

    Reiffel, L [Armour Research Foundation, Chicago, IL (United States)

    1962-04-15

    data also germane to scintillation-chamber technology. Possible imaging detectors using thick blocks of material which are capable of significant energy storage and stimulated phosphorescence upon irradiation are discussed briefly along with read-out methods using optical scanning beams to eliminate resolution loss due to finite phosphor thickness. (author) [French] Le memoire decrit les travaux qui ont ete entrepris sur des detecteurs de rayonnements capables de fournir des informations tout a fait exactes sur la distribution spatiale. Il s'agit avant tout de determiner des distributions d'intensites dans un plan, ou eventuellement sur un cylindre. Cette categorie de problemes comprend la diffraction des neutrons, la radiographie des neutrons, ainsi que la radiographie aux rayons X ou {gamma} ou les etudes de diffusion avec ces rayons. L'auteur s'occupe surtout des detecteurs a images de rayonnements, fondes sur la distribution des etincelles et sur la luminescence Ou la phosphorescence stimulee. Le laboratoire de Armour Research a mis au point de tres grands compteurs a etincelles, pesant plus de 100 livres et comportant des zones sensibles de l'ordre de 2000 cm{sup 2}, definies par des assemblages de plans comprenant chacun jusqu'a 400 fils d'anode et de cathode, les anodes et les cathodes etant respectivement disposees en quinconce. Un compteur a courant gazeux contenant de l'air ou un melange d'argon et de methane constitue un systeme sensible aux rayonnements alpha; la detection des neutrons lents se fait avec des plaques en {sup 10}B enrichi. Avec d'autres gaz de remplissage l'appareil est sensible aux protons et aux electrons. La lecture de la distribution d'intensite se fait par enregistrement photographique de la distribution des etincelles. Des diagrammes de taches de Laue ont pu etre enregistres en dix minutes a l'aide du reacteur d'Armour Research fonctionnant a faible puissance; le flux de crete dans le coeur etait de 10{sup 11} n/cm{sup 2} s et le

  17. Modification of non metallic materials under the influence of the radiation and thermal retrogradation of these modifications; Modification de materiaux non metalliques sous l'influence des rayonnements et retrogradation thermique de ces modifications

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, G; Perio, P; Gigon, J; Tournarie, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The action of the radiation on solids constitute an extremely vast domain of study, which the CEA hardly begins. There is not a very long time, indeed, that we have relatively intense fluxes (6.10{sup 12} thermal neutrons by cm{sup 2}.s{sup -} {sup 1} in the center of the reactor core of Saclay). Materials submitted to radiations, were followed by the evolution of a certain number of physical properties. The study of thermal retrogradation, at moderate temperature, of the modifications provoked by the irradiation were also followed. We will limit, in this report, to expose our experiences on graphite and lithium fluoride. (M.B.) [French] L'action des rayonnements sur les solides constitue un domaine extremement vaste dont l'etude, au Commissariat a l'Energie Atomique, commence a peine. Il n'y a pas tres longtemps, en effet, que nous disposons de flux relativement intenses (6.10{sup 12} neutrons thermiques par cm{sup 2}.s{sup -1} au centre de la pile de Saclay). Dans les materiaux soumis au rayonnement nous suivons l'evolution d'un certain nombre de proprietes physiques et nous etudions la retrogradation thermique, a temperature moderee, des modifications provoquees par l'irradiation. Nous nous bornerons ici a exposer nos experiences sur le graphite et le fluorure de lithium. (M.B.)

  18. Study and industrial applications of the external slowing-down {beta}{sup -} radiation of the yttrium - 90; Etude et applications industrielles du rayonnement de freinage externe des {beta}{sup -} de l'yttrium - 90

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    Inelastic scattering of the {beta}{sup -} particles on the nucleus gives place to the emission of a X-ray Bremsstrahlung radiation. In view of possible industrial applications, we studied the slowing-down radiation of {sup 90}(Sr + Y) sources in various materials. This pure {beta}{sup -} emitter of long period is in the fission products of uranium. Among of the industrial applications, these sources of weak X-rays energy can be used for the radiography of thin pieces, for measuring the thickness, or for the analysis by fluorescence. (M.B.) [French] La diffusion inelastique des particules {beta}{sup -} sur les noyaux donne lieu a l'emission d'un rayonnement X de freinage. En vue de possibles applications industrielles, nous avons etudie le rayonnement de freinage des sources {sup 90}(Sr + Y) dans divers materiaux. Cet emetteur {beta}{sup -} pur a longue periode se trouve dans les produits de fission de l'uranium. Parmi les applications industrielles a l'etude, ces sources de rayons X de faible energie peuvent etre utilisees pour la radiographie de pieces minces, la mesure d'epaisseurs, ou encore pour l'analyse par fluorescence. (M.B.)

  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. Research trends in radiobiology since 40 years. a new approach: the enzymatic repair function of DNA, internal factor in evolution of biological systems under irradiation; Etude des tendances des recherches en radiologie depuis 40 ans. Une nouvelle voie de recherche: la fonction de reparation enzymatique de l'ADN, facteur interne d'evolution des systemes biologiques sous rayonnement

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    . Il y a moins d'une generation, l'on croyait encore que les effets des rayonnements sur les systemes vivants etaient des effets directs, immediats, irreparables et definitifs. Depuis lors, on s'est rendu compte que les radiolesions pouvaient resulter d'effets indirects, etre tardives, reparables, et le plus souvent modifiables par des traitements chimiques ou biochimiques ad hoc. Cependant, la percee decisive en radiobiologie se situe entre 1962 et 1964, avec la decouverte que la cellule possede un mecanisme de defense active vis-a-vis de tout ce qui peut porter atteinte a l'integrite du patrimoine genetique inscrit dans la structure meme de l'ADN. L'existence d'une quatrieme fonction de l'ADN, celle d'auto-reparation, par voie enzymatique sous controle genetique, apporte enfin a la radiobiologie la base biologique moleculaire qui lui manquait pour sortir de la nuit 'phenomenologique' ou elle s'etait enfoncee apres l'abandon de la generalisation de la theorie de Lea, faute de preuve experimentale. Dans la seconde partie, cette fois prospective, de l'etude l'auteur tente une synthese elargie en considerant le role que peut jouer cette fonction de reparation de l'ADN non seulement du point de vue de la survie des systemes biologiques irradies en presence ou non d'agents modificateurs de dose ou mutagenes, mais aussi de celui de l'evolution naturelle ou artificielle de ces systemes sous rayonnement. Les donnees les plus recentes de la litterature sont en accord avec ce qui ne constitue encore qu'une hypothese generale de recherche. Des travaux portant sur les caracteres phenotypiques et genotypiques lies a l'acquisition de radioresistance gamma et UV, chez 'Escherichia coli K12', ont ete entrepris par l'auteur, en collaboration avec O. Tremeau en vue d'apporter une contribution experimentale nouvelle a cet egard. (auteur)

  2. The Use of Ionizing Radiation as a Means of Processing Foodstuffs for Storage: Present Status and Future Prospects; Utilisation des Rayonnements Ionisants pour la Conservation de Produits Alimentaires: Situation Actuelle et Perspectives; Sostoyanie i perspektivy primeneniya ioniziruyushchikh izluchenij dlya obrabotki pishchevykh produktov v svyazi s ikh khraneniem; Estado Actual y Perspectivas del Empleo de las Radiaciones Ionizantes para la Conservacion de los Productos Alimenticios

    Energy Technology Data Exchange (ETDEWEB)

    Rogachev, V. I. [Vsesojuznyj Nauchno-Issledovatel' skij Institut Konservnoj i Ovoshesushil' noj Promyshlennosti Moskva, SSSR (Russian Federation)

    1966-11-15

    The use of ionizing radiation for processing foodstuffs is being studied in the USSR, particularly in connection with the following: (a) prevention of sprouting in potatoes and onions; (b) disinfestation of foodstuffs; (c) suppression of microbe activity; either sterilization or partial inhibition of microflora activity to prolong the shelf life of various foodstuffs; and (d) alterations in the ripening time of fruits and vegetables after picking and/or harvesting. The paper reports the status of work performed in the USSR during recent years on each of these general topics and the prospects for the practical application of irradiation to a number of products are considered. Among the products in question are meat and meat products (raw and cooked semi-finished products, sausage products), domestic poultry, various fruits and vegetables, potatoes, grain, dehydrated products (dried fruits and vegetables, dried food concentrates). Practical methods of irradiating potatoes and onions to prevent sprouting during storage have already been developed, and very soon it will be possible to use radiation for the disinfestation of foodstuffs on an industrial scale. (author) [French] Les etudes sur l'utilisation des rayonnements ionisants pour la conservation des produits alimentaires se poursuivent en URSS.dans les domaines suivants: a) prevention de la germination des pommes de terre et des oignons; b) desinsection des produits alimentaires; c) elimination de l'activite biologique des micro-organismes en vue de la sterilisation ou de l'elimination partielle de l'activite biologique de la microflore en vue de prolonger les delais de conservation de divers produits alimentaires; et d) modifications des delais de maturite apres recolte des fruits et legumes. Pour chacun de ces domaines, l'auteur indique l'etat des travaux effectues en URSS pendant ces dernieres annees et examine les perspectives d'utilisation des rayonnements pour un certain nombre de produits. Au nombre de ces

  3. 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.

  4. 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

  5. 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

  6. 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

  7. 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.

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. 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.

  15. 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.

  16. Contribution to the detection of radioactivity as applied to regular testing and to protection; Contribution a la detection des rayonnements en vue du controle et de la protection

    Energy Technology Data Exchange (ETDEWEB)

    Fuhrmann,; Joffre,; Savouyaud, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    problemes les plus urgents concernaient la dosimetrie des rayonnements et la constitution d'un materiel electronique nombreux, donc assez bon marche, autant que possible. 3. Danspresente communication, nous exposerons sommairement notre contribution dans ce domaine et particulierement: - l'amelioration des methodes de dosimetrie {gamma} par films photographiques, - l'essai d'une technique simple et peu couteuse pour la dosimetrie et la spectrometrie {alpha}, - l'orientation donnee aux nouveaux materiels electroniques: chambre d'ionisation, compteurs, scintillateurs, - la mise au point d'un materiel special permettant de mesurer la valeur moyenne d'un flux de particules emis periodiquement pendant un temps tres court. (auteur)

  17. La diaspora, instrument de la politique de puissance et de rayonnement de l’Inde à l’île Maurice et dans le monde

    Directory of Open Access Journals (Sweden)

    Anouck Carsignol-Singh

    2009-11-01

    Full Text Available Les Persons of Indian Origin (PIO ont depuis le début du XXe siècle servi de levier à l’intelligentsia indienne pour rehausser l’image du pays et contribuer à son rayonnement culturel sur la scène internationale, en tant qu’ambassadeurs culturels de l’Inde dans leur pays de résidence. Aujourd’hui, les nouveaux liens établis entre New Delhi et les Non Resident Indians (NRI dépassent largement le cadre de la diplomatie culturelle, et leur mobilisation économique ou politique en faveur du traité nucléaire contribuent à l’affirmation de la puissance de l’Inde. Une analyse de la mobilisation des Indo-Mauriciens permet de mettre en lumière le double rôle du facteur diasporique dans l’émergence de l’Inde comme grande puissance régionale et internationale, en tant qu’instrument à la fois du Soft Power et de la Realpolitik de New Delhi.People of Indian Origin (PIOs have, since the beginning of the XXth century, been used by the Indian intelligentsia to promote the image of the sub-continent and diffuse India’s cultural values on the international stage, as cultural ambassadors of India in their host countries. Today, the new partnership between New Delhi and the Non Resident Indians (NRIs go beyond India’s cultural diplomacy, and the support of the Diaspora in favour of the nuclear deal plays a strategic part in the affirmation of India as an emerging power. An analysis of the mobilisation of Indo-Mauritians in line with the interests and values of India illustrates the double role of the diasporic factor in the emergence of India as a regional and global power, as a tool of New Delhi’s soft power and Realpolitik.

  18. Detection of high energy gamma radiations with liquid rare gases as scintillators; Detection des rayonnements Gamma de grande energie avec les gaz rares liquides comme scintillateurs

    Energy Technology Data Exchange (ETDEWEB)

    Ho, Phan Xuan

    1965-11-25

    This research thesis reports the study of a sensor based on a liquid scintillator for the detection of high energy (10 to 30 MeV) gamma radiations. The scintillator is a liquefied argon or xenon rare gas. The author first studies the process of energy transfer from the particle to the sensing medium. He addresses the different involved elements and phenomena: electromagnetic radiations (Compton Effect, photoelectric effect, pair production, and total gamma absorption), charged particles (braking radiation, collisions) and application to gamma spectrometry. He describes and discusses the scintillation mechanisms (scintillation of organic and inorganic materials), the general characteristics of scintillators (impurities, converters), and then reports the practical realisation of the sensor. Results are presented and discussed [French] Dans ce travail, nous nous proposons d'etudier une technique. Il s'agit d'un detecteur a scintillateur liquide pour la detection des rayonnements gamma energiques (10 a 30 MeV). Le scintillateur utilise est un gaz rare liquefie argon ou xenon. Nous examinerons d'abord les processus de transfert de l'energie de la particule au milieu detecteur puis les mecanismes de scintillation en general pour pouvoir exploiter au mieux les phenomenes favorables. Nous presenterons ensuite la realisation pratique du detecteur. Ses qualites (et defauts) trouveront leur place dans la fin de ce memoire. Bien qu'a l'heure actuelle, par la methode de Kyropoulos, on puisse faire pousser des gros cristaux d'iodure de sodium, l'utilisation des 'gaz rares' liquefies comme scintillateurs est, grace a la brievete de la scintillation, tres utile lorsqu'on recherche un fort taux de comptage (jusqu'a 10 impulsions par seconde) ou lorsqu'on veut resoudre certains problemes de coincidence. Les cristaux NaI(Tl) de grandes dimensions sont d'un montage facile mais leur manipulation requiert beaucoup de precautions du fait qu'ils supportent tres mal les chocs thermiques

  19. 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.

  20. Radioinitiation of Chain Branched Reactions and its Sensitization; Amorcage sous rayonnement des reactions par ramification en chaine; sensibilisation du processus; Radiatsionnoe initsiirovanie tsennykh razvetvlennykh reaktsij i ego sensibilizatsiya; Radioiniciacion de reacciones en cadena ramificadas y medios para aumentar su sensibilidad

    Energy Technology Data Exchange (ETDEWEB)

    Barelko, E V; Kartashova, L I; Komarov, P N; Proskurnin, M A [Karpov Physico-Chemical Institute, Moscow, Union of Soviet Socialist Republics (Russian Federation)

    1960-07-15

    This paper describes the results of experiments by the writers with radioinitiation of chain branched reactions of the oxidation of organic compounds. The function of radiation as an initiating agent is described with reference to the oxidation of several unsaturated hydrocarbons and butanol. The reaction is self-accelerating and proceeds spontaneously after radiation has ceased. A detailed investigation was made of a process from oxidizing benzene, which has a high radiation resistance. The writers devised a method of sensitizing the radioinitiation of the oxidation of radiation-resistant substances by chemically inert but non-radiation-resistant substances. The main quantitative features of the process for the radiooxidation of benzene are stated to be the accumulation of various reaction products, and the effect of temperature, pressure, power and radiation dosage on the process of such accumulation. Information was obtained about the mechanism of the process. The design of circulating equipment is described. (author) [French] Dans ce memoire, les auteurs presentent les resultats d'une etude consacree a l'amorcage sous rayonnement de reactions, d'oxydation des composes organiques, par ramification en chaine. Ils montrent le role des rayonnements en tant qu'agents d'amorcage de la reaction, en citant comme exemples l'oxydation de certains hydrocarbures non satures et du butanol. La reaction possede un caractere d'auto-acceleration et continue spontanement lorsque l'action des rayonnements a cesse. La reaction d'oxydation du benzene a ete etudiee en detail; elle est caracterisee par la haute stabilite de la substance vis-a-vis de l'action des rayonnements. Les auteurs formulent les principes de la sensibilisation, par l'action de substances instables vis-a-vis des rayonnements de l'amorcage sous rayonnement de la reaction d'oxydation de substances stables vis-a-vis des rayonnements et chimiquement inertes. Le memoire fournit les caracteristiques quantitatives

  1. Simplified Procedures for Obtaining Clearances of Foods Preserved by Ionizing Energy; Procedures Simplifiees pour Obtenir l'Autorisation de Produire des Denrees Alimentaires Conservees par les Rayonnements Ionisants; Uproshennaya protsedura polucheniya razreshenij na prodazhu obluchennk pishchevykh produktov; Simplificacion de los Procedimientos para la Obtencion de Autorizaciones de Venta de Alimentos Conservados Mediante Radiaciones Ionizantes

    Energy Technology Data Exchange (ETDEWEB)

    Josephson, E. S. [United States Army Natick Laboratories, Natick, MA (United States)

    1966-11-15

    After thirteen years of intensive research, using high doses of ionizing energy, highly acceptable wholesome shelf-stable bacon, ham, pork, beef, chicken and shrimp can be produced in the laboratory. Using doses below 1 Mrad, the shelf life of highly acceptable wholesome fish, wheat and wheat products, oranges, and white potatoes can be extended. Before production in the United States can be scaled up to commercial quantities for the broad consumer market, approvals are required from the United States Food and Drug Administration (USFDA) and, for meats from mammals and birds, from the United States Department of Agriculture (USDA). These agencies have approved bacon, wheat and wheat products, and white potatoes, following receipt and evaluation of petitions containing all pertinent information including description of the process to be used and the food-package combination to be cleared, the proposed radiation source, the dose range, dosimetry methods, wholesomeness and nutritional data, positive proof of microbiological safety, absence of measurable induced radioactivity, acceptance data from taste panelists, and storage and shipping data where applicable. Collecting the data required for successful petitions has proved to be both time-consuming and expensive. To improve this situation, the whole process of data collection and of writing the petitions is being reexamined in the interest of streamlining and expediting the process. Recommendations are offered relative to some of the means helpful in achieving this end. (author) [French] Apres treize ans de recherches intensives au moyen de fortes doses de rayonnements ionisants, il est maintenant possible de produire en laboratoire. des denrees - lard, jambon, viande de porc etdeboeuf, poulet, crevettes - se conservant bien et de comestibilite tout a fait satisfaisante. En utilisant des doses inferieures a 1 Mrad, il est possible de prolonger la duree de conservation du poisson, du ble et derives, des oranges et des

  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. 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.

  4. 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 ...

  5. 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

  6. 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

  7. 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...

  8. 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

  9. 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

  10. 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

  11. 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)

  12. 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)

  13. 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.

  14. 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.

  15. 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

  16. 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)

  17. 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

  18. The reactor Melusine - radiation measurements carried out at the start of operation and during the first ascents to power; Pile Melusine - mesures de rayonnement effectuees au demarrage et pendant les premieres montees en puissance

    Energy Technology Data Exchange (ETDEWEB)

    Coutrot, V; Delpuech, J; Fitoussi, L [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    This report gives the results of radiation measurements carried out on the first C.E.A. swimming-pool pile, Melusine. The purpose of these measurements, which were carried out during the starting-up period and the first ascents to 1 MW power, is to check the radiation intensity levels near the pile and from this to verify the safety calculation methods used. In addition certain special measurements, such as those performed in and above the water of the swimming-pool, in the channels and outside them etc..., should make it possible eventually to define the conditions under which the pile may be used for special jobs with less protection. In the first part of the report are given the results of radiation measurements carried out during runs at low power plateaux not exceeding 500 W: in particular measurements at variable water levels in the water of the swimming-pool and on the axis of the open channels. The results given in the second part deal with radiation measurements performed in various parts of the premises, studies on the activation of the plugs in the experimental channels and of the materials in the forward compartment, and also of the radioactivity of the swimming-pool water and the air used to cool the channels. (author) [French] Le present rapport a pour but de donner les resultats des mesures de rayonnement effectuees aupres de la premiere pile piscine du C.E.A.: la pile Melusine. Le but de ces mesures, effectuees pendant la periode de demarrage et les premieres montees a la puissance de 1 MW, est de controler les niveaux d'intensite de rayonnement aupres de la pile et par la de juger des methodes de calculs de protection utilisees. D'autre part, certaines mesures plus particulieres, telles que celles effectuees dans l'eau et au-dessus de l'eau de la piscine, dans les canaux et a l'exterieur de ceux-ci, etc..., doivent permettre de definir ulterieurement les conditions d'utilisation de la pile pour des fonctionnements particuliers avec des protections

  19. 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

  20. Contribution to the study of the ionization and heating of gases by laser radiation; Contribution a l'etude de l'ionisation et du chauffage des gaz par le rayonnement d'un laser declenche

    Energy Technology Data Exchange (ETDEWEB)

    Veyrie, P [Commissariat a l' Energie Atomique, Limeil-Brevannes (France). Centre d' Etudes

    1968-01-01

    The ionization and heating of gases by the concentrated radiation of a neodymium laser is studied. The power is 300 MW, the gas studied is primarily deuterium between 300 mm and 2280 mm. The first part concerns a certain number of experimental results on the absorption of the radiation and on changes produced in the plasma as a function of time. From these results are deduced a certain number of consequences, amongst which may be mentioned the definition of a pre-ionization threshold. These experimental results are interpreted in the second part. A calculation is made of the length of the period during which the electrons multiply up to when the absorption becomes measurable. The last phase corresponds to the hydrodynamics evolution, the calculations are compared with the experiments. The agreement between theory and experiment is satisfactory for the different phases. (author) [French] On etudie l'ionisation et le chauffage des gaz par le rayonnement concentre d'un laser au neodyme. La puissance est de 300 MW, le gaz etudie est principalement le deuterium entre 300 mm et 2280 mm. La premiere partie concerne un certain nombre de resultats experimentaux. Il s'agit de l'absorption du rayonnement et de l'evolution chronologique du plasma. De ces resultats on deduit un certain nombre de consequences parmi lesquelles il faut citer la definition d'un seuil de preionisation. Ces resultats experimentaux sont interpretes dans la deuxieme partie. On calcule la duree de la phase pendant laquelle se multiplient les electrons jusqu'a ce que l'absorption soit mesurable. La derniere phase correspond a l'evolution hydrodynamique. Les calculs sont confrontes avec l'experience. L'accord entre theorie et experience est satisfaisant pour les differentes phases. (auteur)

  1. Contribution to the study of the ionization and heating of gases by laser radiation; Contribution a l'etude de l'ionisation et du chauffage des gaz par le rayonnement d'un laser declenche

    Energy Technology Data Exchange (ETDEWEB)

    Veyrie, P. [Commissariat a l' Energie Atomique, Limeil-Brevannes (France). Centre d' Etudes

    1968-01-01

    The ionization and heating of gases by the concentrated radiation of a neodymium laser is studied. The power is 300 MW, the gas studied is primarily deuterium between 300 mm and 2280 mm. The first part concerns a certain number of experimental results on the absorption of the radiation and on changes produced in the plasma as a function of time. From these results are deduced a certain number of consequences, amongst which may be mentioned the definition of a pre-ionization threshold. These experimental results are interpreted in the second part. A calculation is made of the length of the period during which the electrons multiply up to when the absorption becomes measurable. The last phase corresponds to the hydrodynamics evolution, the calculations are compared with the experiments. The agreement between theory and experiment is satisfactory for the different phases. (author) [French] On etudie l'ionisation et le chauffage des gaz par le rayonnement concentre d'un laser au neodyme. La puissance est de 300 MW, le gaz etudie est principalement le deuterium entre 300 mm et 2280 mm. La premiere partie concerne un certain nombre de resultats experimentaux. Il s'agit de l'absorption du rayonnement et de l'evolution chronologique du plasma. De ces resultats on deduit un certain nombre de consequences parmi lesquelles il faut citer la definition d'un seuil de preionisation. Ces resultats experimentaux sont interpretes dans la deuxieme partie. On calcule la duree de la phase pendant laquelle se multiplient les electrons jusqu'a ce que l'absorption soit mesurable. La derniere phase correspond a l'evolution hydrodynamique. Les calculs sont confrontes avec l'experience. L'accord entre theorie et experience est satisfaisant pour les differentes phases. (auteur)

  2. 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…

  3. 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

  4. 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

  5. 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

  6. Appraisal of alternative skin model for the study of epidermal restoration following exposure to various environmental stress agents: ionising radiation and UV B; Evaluation d'un modele alternatif de peau dans l'etude de l'atteinte epidermique apres exposition a differents agents de stress environnementaux: rayonnements ionisants (RI) et ultra-violets B (UVB)

    Energy Technology Data Exchange (ETDEWEB)

    Isoir, M

    2006-06-15

    Human skin is a major target tissue for ionising radiation (IR) and UV B. We developed a skin explant model and used 2 types of keratinocytes to study survival and oxidative stress induced by these radiations. We examined oxidative damages by measuring R.O.S. produced and cellular anti-oxidant defenses induced. We observed into skin exposed to IR a modulation of genes expression implied in the control of oxidative stress, confirmed by the decrease of catalase, glutathione peroxidase and superoxide dismutase enzymatic activities. The imbalance observed between anti- and pro-apoptotic genes expression shows that keratinocytes apoptosis may be partly dependent on radio-induced R.O.S. production. We showed the difference of radiosensitivity between N.H.E.K. and Ha Ca.T., which may be linked to their differential oxidative responses. In addition, during re-epithelialising, we demonstrated that activated N.H.E.K. after IR express keratin 6, release pro-inflammatory cytokines and proliferate, without modification of their differentiation. Treatment of N.H.E.K. with geranyl geranylacetone (G.G.A.) has a beneficial effect on their radio-induced activation by increasing IL-1 release, their migration in scrapped area and their survival. G.G.A. has an anti apoptotic ability (induction of Hsp70- caspase-3 pathway) and migratory properties (P38/RhoA activation) on N.H.E.K., but after IR, only caspase-3 pathway is induced. This work thus contributes to the understanding of cutaneous damages after IR and G.G.A. mechanism of action which accelerates re-epithelialising. (author)

  7. Appraisal of alternative skin model for the study of epidermal restoration following exposure to various environmental stress agents: ionising radiation and UV B; Evaluation d'un modele alternatif de peau dans l'etude de l'atteinte epidermique apres exposition a differents agents de stress environnementaux: rayonnements ionisants (RI) et ultra-violets B (UVB)

    Energy Technology Data Exchange (ETDEWEB)

    Isoir, M

    2006-06-15

    Human skin is a major target tissue for ionising radiation (IR) and UV B. We developed a skin explant model and used 2 types of keratinocytes to study survival and oxidative stress induced by these radiations. We examined oxidative damages by measuring R.O.S. produced and cellular anti-oxidant defenses induced. We observed into skin exposed to IR a modulation of genes expression implied in the control of oxidative stress, confirmed by the decrease of catalase, glutathione peroxidase and superoxide dismutase enzymatic activities. The imbalance observed between anti- and pro-apoptotic genes expression shows that keratinocytes apoptosis may be partly dependent on radio-induced R.O.S. production. We showed the difference of radiosensitivity between N.H.E.K. and Ha Ca.T., which may be linked to their differential oxidative responses. In addition, during re-epithelialising, we demonstrated that activated N.H.E.K. after IR express keratin 6, release pro-inflammatory cytokines and proliferate, without modification of their differentiation. Treatment of N.H.E.K. with geranyl geranylacetone (G.G.A.) has a beneficial effect on their radio-induced activation by increasing IL-1 release, their migration in scrapped area and their survival. G.G.A. has an anti apoptotic ability (induction of Hsp70- caspase-3 pathway) and migratory properties (P38/RhoA activation) on N.H.E.K., but after IR, only caspase-3 pathway is induced. This work thus contributes to the understanding of cutaneous damages after IR and G.G.A. mechanism of action which accelerates re-epithelialising. (author)

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. Contribution to the study of the inelastic scattering of neutrons from a to 5 MeV (1961); Contribution a l'etude de la diffusion inelastique des neutrons de 1 a 5 MeV (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Abramson - Szteinsznaider, D [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    - The aim of this work is to see if this reaction occurs only by compound nucleus formation or involves some contribution of direct interaction. In the first case, the angular distribution of inelastic neutrons is symmetric about 90 degree. In the second case, this distribution must be asymmetric and must change slowly with energy of incident neutrons. The neutrons corresponding at the excitation of a given level of the residual nucleus are selected by their coincidence with the {gamma} rays of deexcitation of this level. From the results of our measurements on iron, iodine and bismuth and of other laboratories on different elements, we can conclude that generally, the inelastic scattering of neutrons of some MeV occurs only by compound nucleus. (author) [French] - Le but de ce travail est de determiner si cette reaction s'effectue uniquement par passage par un noyau compose ou fait intervenir un processus d'interaction directe. Dans le premier cas, la distribution angulaire des neutrons inelastiques est symetrique par rapport a 90 degree. Dans le deuxieme cas, cette distribution doit etre asymetrique et doit varier lentement avec l'energie des neutrons incidents. Les neutrons correspondant a l'excitation d'un niveau determine du residuel sont selectionnes par leur cofncidence avec les rayonnements {gamma} de desexcitation de ce niveau. D'apres les resultats de nos mesures sur le fer, l'iode et le bismuth et de celles des autres laboratoires sur differents elements, nous pouvons conclure que, en general, la diffusion inelastique des neutrons de quelques MeV s'effectue uniquement par noyau compose. (auteur)

  17. 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)

  18. 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)

  19. 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

  20. 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.

  1. 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.

  2. 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)

  3. 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

  4. 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

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. Regulations concerning radiation protection and survey; Donnees de la surveillance et regles qui en resultent en matiere de protection contre les rayonnements

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel,; Lavie,; Fitoussi, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    will only be considered with regard to recuperation of uranium after simple machining. (author) [French] 1. L'utilisation croissante de l'energie nucleaire sous toutes ses formes a des fins pacifiques pose des problemes de securite vis-a-vis des travailleurs, des populations et des sites en general. Une etude comparee des risques d'irradiation auxquels le personnel du Commissariat a l'Energie atomique (CEA) a ete expose au cours de l'annee 1957 et des resultats du controle des radiations par les moyens de detection collectifs ou individuels montre que les installations du CEA ont une influence negligeable sur la sante, en raison de la surveillance exercee. 2. Cependant, quelques incidents de contamination et d'irradiation - sommairement indiques ainsi que la maniere dont ils ont ete regles - rendent necessaire l'elaboration d'une reglementation precise definissant les responsabilites respectives, au sein d'un etablissement nucleaire, des services utilisateurs et du Service charge de la Protection contre les Radiations, en matiere de prevention de la contamination. 3. Un ensemble coherent de regles pratiques de prevention et de protection relatives a la detention, la manipulation, le transport et le stockage de sources radioactives scellees ou non scellees, est presente. A cette fin, a partir des recommandations de la Commission Internationale de Protection Radiologique et compte tenu: - de leur nocivite radioactive; de leur activite specifique par unite de masse et du risque de contamination; les radioelements ont ete classes suivant le danger qu'ils presentent par rapport au plutonium. 4. Le Service charge de la Protection contre les Radiations intervient comme conseiller des la conception des laboratoires specialises et veille ensuite a ce que les prescriptions reglementaires de securite soient observees. 5. Des donnees elaborees, indispensables a la protection contre les rayonnements, sont mises a la disposition des utilisateurs en particulier: - table des radio

  11. 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 ...

  12. 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 ...

  13. 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.

  14. 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.

  15. 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.

  16. 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)

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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.

  4. 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

  5. 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

  6. 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

  7. Applications of electron spin resonance to some problems of radiation chemistry; Applications de la resonance paramagnetique electronique a quelques problemes de chimie sous rayonnements

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-01

    The electron spin resonance (E.S.R.) spectra of gamma irradiated polar organic glasses, at 77 K, shows a single line centered at g {approx} 2, attributed to solvated electrons. The radicals produced on scavenging this species by electron acceptors, such as aromatic hydrocarbons, nitro-compounds and azines have been studied by E.S.R. In most cases, the radicals from these solutes, the spectra of which are observed after elimination by warming of the radicals from the matrices, are produced by protonation of the anions formed by scavenging of electrons at 77 K. Thus, in the case of glassy solutions of nitro-compounds, the radicals R NO{sub 2}H are formed. They are characterized by a{sub N} = 15 G (nitrobenzene) or a{sub N} = 28 G (nitro-alkane). These radicals are also generated by U.V, photolysis at room temperature of solutions of nitro-compounds in alcohols and are shown to be the precursors of nitroxide radicals R - N - R (with N - O) observed simultaneously. Gamma irradiation of solutions of pyridine and of the three diazines, in alcohol glasses at 77 K, produces the radical formed by hydrogen addition to these compounds. The value of the coupling constant of the additional proton (7-10 G) indicates that it is bound to a nitrogen in the sp{sup 2} hydridation state. One has shown, taking pyridine as an example, that the addition to a carbon gives a much greater value of the coupling constant, of the order of 50-60 G. (author) [French] Les spectres de resonance paramagnetique electronique (R.P.E.) obtenus apres irradiation gamma, a 77 K, de verres organiques polaires tels que les alcools, comportent une bande unique centree a g {approx} 2, attribuable aux electrons solvates. On etudie par R.P.E. les radicaux provenant de leur capture par des solutes ayant une affinite electronique, en particulier les hydrocarbures aromatiques, les composes nitres et les azines. En general, les radicaux provenant de ces solutes, dont on observe les spectres apres elimination

  8. 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.

  9. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-01-15

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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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 ...

  1. 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...

  2. 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

  3. 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)

  4. 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.

  5. 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

  6. 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.

  7. Beta-Excited Sources of Electromagnetic Radiation; Sources de rayonnements electromagnetiques excites par des particules beta; Vozbuzhdennye beta-chastitsami istochniki ehlektromagnitnogo izlucheniya; Fuentes de radiacion electromagnetica excitadas por particulas beta

    Energy Technology Data Exchange (ETDEWEB)

    Cameron, J F; Rhodes, J R [Physics Group, Isotope Research Division, (AERE), Wantage Research Laboratory, Wantage, Berks (United Kingdom)

    1962-01-15

    Beta-excited sources of electromagnetic radiation covering the energy region 1-200 keV and suitable for industrial use are described. H{sup 3}, Pm{sup 147}, Kr{sup 85}, Tl{sup 204} and (Sr+Y){sup 90} were chosen as sources of beta particles by the criteria of long half-life, low price, ready availability and high specific activity. The {beta}-excited sources have been designed on the basis of a compromise between practical source construction and the best theoretical efficiency in a given energy region. In their paper, the authors calculate the number of photons produced per beta particle and consider how the results must be corrected for self-absorption of the X-rays. In the calculations account is taken of both bremsstrahlung and characteristic {alpha}-radiation; optimum characteristic X-ray yield is achieved for targets with an atomic number between 40 and 60. ''Sandwich'' targets of 1-2 beta half-value thicknesses are found to give maximum photon-yields in the desired energy region. Al, Ag and Au are suitable from the manufacturing point of view as source coverings. They were also found to give satisfactory bremsstrahlung and X-ray yields and distribution for various energy regions in the range 1-200 keV when correctly combined with the above-mentioned D-emitters. Some energy spectra are given and absorption curves in Al and Fe are shown for the best source-target combinations. The difference between sources constructed of {beta}-emitters sandwiched between target foils and intimate source-target mixtures was found to be small. Tables are given as a guide to the best source to be used for a particular absorber thickness range. (author) [French] Les auteurs decrivent des sources de rayonnements electromagnetiques excites par des particules beta, couvrant une gamme d'energies allant de 1 a 200 keV et convenant aux usages industriels. Comme sources de particules beta on a choisi le tritium, le {sup 147}Pm, le {sup 85}Kr, le {sup 204}Tl et le {sup 90}(Sr+Y), en

  8. 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.

  9. 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.

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.

  15. Measurement and analysis of high energy radiation through activation detectors. Application in dosimetry; Sur la mesure et l'analyse des rayonnements de haute energie par detecteurs a activation. Application a la dosimetrie

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-10-15

    This work is concerned with the possibility of measurement and analysis of radiation fluences within objects of small volume submitted to a high energy proton beam. The first part, consecrated to the establishment of a method of analysis, comprises a detailed study of the radiation nature and energy spectra as well as of the various dosimetry methods. In order to select a group of detectors, high energy nuclear reactions were systematically studied and for some of them cross sections were measured or calculated: for example the cross section of the reaction {sup 11}B (p,n) {sup 11}C between 150 and 3000 MeV and of the reaction {sup 34}S (p,2pn) {sup 32}P between 50 and 3000 MeV. The second part is relative to the application of the fore-mentioned analysis to radiation within a tissue equivalent phantom irradiated by 3 GeV protons. This analysis is sufficiently detailed to allow the reconstitution of the absorbed doses, the dose equivalent and, contingent on a better knowledge of the dose due to heavy particles, the quality factors. It allowed also to follow the evolution of the various dosimetric data as a function of the depth inside the phantom and to verify calculations already done by other researchers. The comparison of the measured doses and the corresponding detector activities revealed the possibility that some detectors could give directly the absorbed dose, or even the dose equivalent, by a simple activity measurement. (author) [French] Le travail porte sur la possibilite de mesure et d'analyse, a l'aide de detecteurs a activation, des fluences de rayonnements a l'interieur d'un objet de petit volume soumis a un faisceau de protons de tres haute energie. La premiere partie, consacree a la mise au point de la methode d'analyse des fluences, comporte une etude detaillee de la nature des rayonnements et de leurs spectres energetiques ainsi que des differentes methodes de dosimetrie. Pour arriver au choix d'un groupe de

  16. Cobalt-60 and Caesium-137 Gamma Sources; Sources de rayonnement gamma au cobalt-60 et au cesium-137; Gamma-istochniki iz kobal'ta-605 i tseziya-137; Fuentes gamma de cobalto-60 y de cesio-137

    Energy Technology Data Exchange (ETDEWEB)

    Kulish, E E; Fradkin, G M [Academy of Sciences of the USSR, Moscow, Union of Soviet Socialits Republics (Russian Federation)

    1960-07-15

    The paper gives the main technical characteristics of gamma sources produced in the USSR using cobalt-60 and caesium-137 and discusses some of the problems of their production technology. The paper contains information on the radiation spectra of Co{sup 60} and Cs{sup 137} and of the source material from which they are prepared. Data are given on the dependence of the activity of cobalt sources upon the intensity of the neutron beam and the geometrical size of the sample. The yield of caesium by uranium fission is also analyzed. The problem of hermetic sealing of the sources is discussed and a complete nomenclature of all the sources manufactured in the USSR are listed, their size and activity also being indicated. In conclusion a comparison of Co{sup 60} and Cs{sup 137} sources is made. (author) [French] Cette communication expose les caracteristiques techniques fondamentales des sources de rayonnement gamma a base de cobalt-60 et de cesium-137 pro- duites en URSS; on y examine egalement certaines questions relatives a la technologie de leur production. La communication contient des donnees sur la nature du rayonnement des isotopes {sup 60}Co et {sup 137}Cs, ainsi que sur celle des matieres brutes utilisees pour leur preparation. On donne les resultats obtenus lors de l'etude de la variation de l'activite des sources au cobalt en fonction de la valeur du flux de neutrons et des dimensions geometriques de l'echantillon, ainsi que les resultats relatifs a la valeur du rendement en isotopes de cesium lors de la fission des noyaux d'uranium. On etudie ensuite les procedes pour assurer l'hermeticite de ces sources. Suit une nomenclature complete des sources produites en URSS, comportant des indications sur leurs dimensions geometriques et sur les valeurs de leur activite. Enfin, il est procede a une comparaison des sources au {sup 60}Co et au {sup 137}Cs. (author) [Spanish] En este informe se describen las principales caracteristicas tecnicas de las fuentes gamma de

  17. Measurement and analysis of high energy radiation through activation detectors. Application in dosimetry; Sur la mesure et l'analyse des rayonnements de haute energie par detecteurs a activation. Application a la dosimetrie

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-10-15

    This work is concerned with the possibility of measurement and analysis of radiation fluences within objects of small volume submitted to a high energy proton beam. The first part, consecrated to the establishment of a method of analysis, comprises a detailed study of the radiation nature and energy spectra as well as of the various dosimetry methods. In order to select a group of detectors, high energy nuclear reactions were systematically studied and for some of them cross sections were measured or calculated: for example the cross section of the reaction {sup 11}B (p,n) {sup 11}C between 150 and 3000 MeV and of the reaction {sup 34}S (p,2pn) {sup 32}P between 50 and 3000 MeV. The second part is relative to the application of the fore-mentioned analysis to radiation within a tissue equivalent phantom irradiated by 3 GeV protons. This analysis is sufficiently detailed to allow the reconstitution of the absorbed doses, the dose equivalent and, contingent on a better knowledge of the dose due to heavy particles, the quality factors. It allowed also to follow the evolution of the various dosimetric data as a function of the depth inside the phantom and to verify calculations already done by other researchers. The comparison of the measured doses and the corresponding detector activities revealed the possibility that some detectors could give directly the absorbed dose, or even the dose equivalent, by a simple activity measurement. (author) [French] Le travail porte sur la possibilite de mesure et d'analyse, a l'aide de detecteurs a activation, des fluences de rayonnements a l'interieur d'un objet de petit volume soumis a un faisceau de protons de tres haute energie. La premiere partie, consacree a la mise au point de la methode d'analyse des fluences, comporte une etude detaillee de la nature des rayonnements et de leurs spectres energetiques ainsi que des differentes methodes de dosimetrie. Pour arriver au choix d'un groupe de detecteurs, une etude systematique des

  18. 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)

  19. Germanium junction detectors. Theoretical and practical factors governing their use in radiation spectrometry; Detecteurs a jonction au germanium. Elements theoriques et pratiques pour l'utilisation en spectrometrie de rayonnements

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    Semi-conductor detectors have recently greatly increased the possibilities available to nuclear spectroscopists for the study of {alpha}, {beta} and {gamma} radiations. Their use in radio-chemistry has encouraged us to study their principle, their mechanism and also the conditions under which they can be used. The first part, which is theoretical, consists of a summary of what should be known concerning the best use of junction detectors, in particular Ge (Li) detectors. The second part, which is experimental, summarizes the laboratory work carried out over a period of one year on Ge (Li) detectors. Stress is laid on the possibilities presented by the use of these detectors as photo-electric spectrometers, and also on the precautions required. Amongst the numerous results presented, the resolution of 2.52 keV obtained for the {gamma} radiation of 145.5 keV for {sup 141}Ce may be particularly noted. (authors) [French] Les detecteurs a semi-conducteurs ont recemment accru les possibilites offertes aux spectroscopistes nucleaires pour l'etude des radiations {alpha}, {beta}, {gamma}. Leurs utilisations en radiochimie nous ont incite a en etudier le principe, le mecanisme et d'autre part les conditions d'emploi. La premiere partie, theorique, rappelle l'essentiel de ce qu'il est utile de connaitre pour une utilisation optimale des detecteurs a jonctions et en particulier des detecteurs Ge (Li). La deuxieme partie, experimentale, resume les travaux realises au laboratoire pendant un an avec des detecteurs Ge (Li). Nous insistons sur les possibilites offertes et les precautions a prendre dans l'utilisation de ces detecteurs comme spectrometres photoelectriques. Parmi les nombreux resultats presentes, citons la resolution de 2,52 keV obtenue pour le rayonnement {gamma} de 145 f5 keV du {sup 141}Ce. (auteurs)

  20. Determination of the cross-sections of some nuclear reactions occurring as a result of cosmic radiation (1963); Determination des sections efficaces de quelques reactions nucleaires intervenant dans les effets ou rayonnement cosmique (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-06-15

    The high energy reactions studied during this research are reactions liable to occur as a result of cosmic radiation. On the one hand the reaction {sup 16}O(p, 3p){sup 14}C was studied and its cross-section measured between 65 MeV and 2.7 GeV; a value of 2.3 mb {+-} 0.5 was found. These values have mode it possible to forecast measurable quantities of carbon-14 in meteorites and also to measure them. On the other hand the reactions {sup 12}C({sup 16}O...), {sup 12}C({sup 14}N...) and {sup 12}C({sup 12}C...) have been studied and an attempt has been made to explain the mechanism of these reactions. (author) [French] Les reactions a hautes energies qui ont ete etudiees au court de ce travail sont des reactions susceptibles de se produire sous l'effet du rayonnement cosmique. Il s'agit d'une part de la reaction {sup 16}O(p, 3p){sup 14}C dont on a mesure la section efficoce egale a 2,3 mb {+-} 0,5 entre 65 MeV et 2,7 GeV. Ces valeurs ont permis de prevoir des quantites mesurables de carbone 14 dans les meteorites et par suite de les determiner. D'autre part les reaction {sup 12}C({sup 16}O...), {sup 12}C({sup 14}N...) et {sup 12}C({sup 12}C...) ont ete etudiees et on a tente d'expliquer le mecanisme de ces reactions. (auteur)

  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. Câbles électriques - Calcul du courant admissible - Partie 2: Résistance thermique - Section 2: Méthode de calcul des coefficients de réduction de l'intensité de courant admissible pour des groupes de câbles posés à l'air libre et protégés du rayonnement solaire direct

    CERN Document Server

    1995-01-01

    Câbles électriques - Calcul du courant admissible - Partie 2: Résistance thermique - Section 2: Méthode de calcul des coefficients de réduction de l'intensité de courant admissible pour des groupes de câbles posés à l'air libre et protégés du rayonnement solaire direct

  3. About the problem of the delays between particles belonging to the cosmic radiation; Sur le probleme des retards entre des particules appartenant au rayonnement cosmique

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-07-01

    After having examined briefly the problem of the delays who can appear between particles of high energy, issued of a same mother particle, we studied in a more details the case of the loaded particles, loosing their energy by ionization. The delay that settles between two particles of mass M belonging to this last species is defined by the difference between the times that they take to do the same distance. In the vacuum, the delays can reach any values. But, when the particles diffuse themselves in a middle absorbing, the delays stretch toward a definite limit whatever the initial energies of the particles is. One demonstrates that the maximum delay is given by ({delta}t){sub max} {approx_equal} 0,6 E{sub 0} / cK{sub min}, where E{sub 0} = Mc{sup 2} represents the energy to the rest of the particle and K{sub min} the minimum loss of energy by cm of course in the given middle. For example, in the case of the protons crossing different absorbing surroundings, the values of ({delta}t){sub max} for air (Tpn), water, the Al and the Pb are respectively equal to 8,3.10{sup -6}, 9,7.10{sup -9}, 45.10{sup -9} and 1,6 10{sup -9} dry. The corresponding values of ({delta}t){sub max} for the electrons, are the order of 10{sup -9} dry for air and the order of 10{sup -12} dry for the condensed surroundings. It results that, if the particles belonging has a sheaf demonstrated between them of the superior delays to those that are indicate, the fact would constitute a sufficient proof of the existence of heavy particles to the breast of the sheaf. Otherwise, the relation that joins ({delta}t){sub max} to the mass M could act as basis to a method of mass spectrography of the big energy particles. (author) [French] Apres avoir examine succintement le probleme des retards qui peuvent apparaitre entre des particules de grande energie, issues d'une meme particule mere, on etudie d'une facon plus detaillee le cas des particules chargees, ne perdant leur energie que par ionisation. Le

  4. 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.

  5. 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

  6. 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

  7. Theoretical and Applied Aspects of Radiation D-Values for Spores of Clostridium Botulinum; Aspects Theoriques et Pratiques des Valeurs D de Rayonnement Appliquees aux Spores de Clostridium Botulinum; Teoreticheskie i prikladnye aspekty koehffitsienta izlucheniya odlya spor Clostridium Botulinum; Aspectos Teoricos y Practicos de los Valores D para Esporas del Clostridium Botulinum

    Energy Technology Data Exchange (ETDEWEB)

    Grecz, N. [Biophysics Laboratory, Illinois Institute Of Technology, Chicago, IL (United States)

    1966-11-15

    suspending medium may either compete for radicals, e.g. most foods and microbiological media are radical scavengers, or it may promote formation of harmful radicals, e. g. phosphate buffer forms phosphinic acid, oxygen forms peroxy and perhydroxye radicals. Changes of D{sub 10}-values of an individual strain caused by various environmental conditions can be related to indirect effects, while changes of D{sub 10} values from strain to strain under standardized conditions relate to the amount and structure of nucleoid DNA in spores. In this respect all strains of C. botulinum studied to date can be tentatively divided into three groups: Group 1 includes strains (A, B and E) with D values around 0.13 Mrad or less. These spores exhibit single-hit inactivation curves and have probably one chromosome with a low repair probability. Group 2 includes strains 12885 A, 62A, 77A, 9B clustering around D{sub 10} =0.23 Mrad. Available target data suggest that these spores possess one chromosome of 900 {mu} with a repair multiplicity of 13. Group 3 includes the highly-resistant strains 33A, 36A, 40B, 41B, and 53B clustering around D{sub 10} = 0.33 Mrad. Available target data suggest that these spores possess two chromosomes of 900{mu} each with a repair multiplicity (N) between 80 and 90, i.e. N = 13{sup 2}/2. (author) [French] Il a ete constate que les spores de C. botulinum offrent aux rayonnements ionisants une resistance qui est egale ou superieure a celle des spores d'autres organismes non toxiques provoquant l'alterration des denrees alimentaires. Pour cette raison, les normes de traitement microbiologique appliquees pour la conservation des aliments par les rayonnements sont toujours fonction de la radioresistance des spores de C. botulinum. L'indice de cette radioreistance est la valeur Dio definie comme la dose necessaire pour inactiver un cycle logarithmique (90%) d'une population de spores donnee, tandis que le terme 12 x D a ete arbitrairement defini comme la dose sure pour la

  8. 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

  9. 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.

  10. Catalytic Activity and Nuclear Radiation; L'activite catalytique et les rayonnements nucleaires; Kataliticheskaya aktivnost' i yadernoe izluchenie; La actividad catalitica y las radiaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Turkevich, J.; Ikawa, T.; Nozaki, F.; Stamires, D. [Princeton University, N.J (United States)

    1963-11-15

    remplacant en partie l e sodium d'un tamis moleculaire du type Linde Y (Na{sub 56}(AlO{sub 2}){sub 56}(SiO{sub 2}){sub 126}) par l'ion ammonium pour l e decomposer ensuite de maniere a retirer a la fois l'ammoniaque et l'eau, ce qui cree des sites depourvus d e cations dans le tamis. Ils ont prepare une serie de ces catalyseurs possedant des nombres regulierement croissants de sites decationises (de 0 a 100%par rapport a la teneur primitive en sodium). Ils ont etudie l'activite catalytique de ces deux series de catalyseurs avant et apres exposition aux rayons gamma, en observant ia cinetique de la decomposition du cumene en benzene et propylene, l'isomerisation du butene - 1 en butene-2 par deplacement de la double liaison et la reaction d'echange hydrogene-deuteriu'm. Le nombre des sites actifs a ete determine par empoisonnement progressif a la quinoleine; on a donc pu chiffrer l'activite par site. Les auteurs ont aussi etudie ces substances en mesurant la resonance de spin des electrons pour des agents de transfert des electrons adsorbes, notamment la triphenylamine, le perylene et le diphenylethylene symetrique. Ils ont constate que la capacite de transfert des electrons est parallele a l'activite catalytique. lis ont pris la resonance protonique de l'eau absorbee pour caracteriser la nature du site catalytique. (author) [Spanish] Los autores exponen los resultados de nuevos trabajos acerca de los efectos de los rayos gamma sobre la actividad catalitica de un gel de silice y alumina y sobre tamices moleculares descationizados del tipo Linde Y. A tal efecto, prepararon una serie graduada de catalizadores de gel de silice y alumina coprecipitados, con diez distintos valores equidistantes para la razon atomica alumina/silice. Otra serie de catalizadores se obtuvo sustituyendo parcialmente el sodio de un tamiz molecular Linde Y, Na{sup 56}(AlO{sub 2}){sub 56}(SiO{sub 2}){sub 126}, por el ion amonio y descomponiendolo despues para expulsar tanto el amonio como el agua, con lo

  11. 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.

  12. 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...

  13. 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

  14. 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

  15. 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...

  16. High-Dose Ionizing Radiation Photographic Dosimetry; Mesure, par des Methodes Photogra Phiques, de Doses Elevees de Rayonnements Ionisants; 0424 041e 0422 041e 0413 0420 0414 ; Dosimetria Fotografica de Dosis Elevadas de Radiaciones Ionizantes

    Energy Technology Data Exchange (ETDEWEB)

    Trousil, J.; Bucina, I. [Institute for Research Production and Application of Radioisotopes Prague, Czechoslovakia (Czech Republic)

    1965-06-15

    energy dependence and latent image fading on the accuracy of exposure measurement was determined. Finally the errors in film dosimetry of high-level doses, which were observed on,the basis of experimental work with the aid of mathematical statistics, are described. The increase over the error in the range of little and severe blackening is also considered. The errors associated with calibration, energy dependence, latent image fading, chemical processing and measurement of blackening are also taken into account. The error associated with the assumption that the dose assessed by the film badge corresponds to the whole-body dose is not considered. (author) [French] Les auteurs decrivent une methode photographique de mesure de doses de rayonnements comprises entre 10 mr et 1000 r (rayons gamma et rayons X de haute energie). Cette methode comporte l ' emploi de deux films a emulsions differentes, qui sont montes dans un meme boitier. Cette methode a pour caracteristique essentielle de permettre d' evaluer les doses comprises dans les limites indiquees ci-dessus sans savoir s' il y a eu exposition a une dose plus elevee, avec une precision superieure a {+-}25% dans toute l'etendue de mesure (fidelite de 95%); elle permet aussi d'evaluer de maniere assez approchee l'energie des rayonnements auxquels le film a ete expose. Le memoire traite des appareils, types de films et traitements chimiques qui rendent ces mesures possibles. Il decrit le principe de la construction d'un densitometre qui permet de mesurer avec la meme precision le noircissement du film dans une gamme allant de D = 0 a D = 6. Il est ainsi possible de tirer parti de toute la region ou le noircissement du film peut etre employe. Etant donne qu'aucun photomultiplicateur n' est utilise, les possibilites de surexposition sont reduites au minimum et l'appareil peut donc etre utilise pour les mesures normales. Le memoire indique egalement les caracteristiques que les films dosimetres doivent avoir pour etre utilises

  17. Theoretical galactic cosmic ray electron spectrum obtained for sources of varying geometry; Spectre theorique des electrons du rayonnement cosmique dans la galaxie obtenu pour des sources a geometrie variable

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Jokipii and Meyer have recently obtained an electron density energy spectrum of the cosmic rays, originating in the Galaxy, using integral solutions of the steady state transfer equations, by considering a circular cylindric galactic disc as source and approximating the resulting fourth order integral. In this report, we present general results, obtained by using an arbitrary circular cylindric source, without restricting ourselves to the galactic disc. The integrals are treated exactly. The conclusions of Jokipii and Meyer form special cases of these results. We also obtain an exponential energy variation which, at the moment, is not observed experimentally. The second part of this work deals with more complicated, but perhaps more realistic models of elliptic cylindric and ellipsoidal galactic disc sources. One may also note that a very large source concentrated in a very small region gives a spectrum not unlike that for a small source distributed throughout a large volume. Finally, it may be remarked that the model adopted is much less restrictive than the artificial conception of 'leakage time' followed by other workers. (author) [French] Jokipii et Meyer ont dernierement obtenu un spectre d'energie pour les electrons galactiques dans le rayonnement cosmique, en utilisant les solutions des equations de transfert, a l'etat stationnaire, ces dernieres etant sous forme d'integrales, en prenant une source completement diffusee dans le disque galactique, celui-ci etant hypothetiquement choisi comme circulaire et cylindrique et en faisant une approximation sur l'integrale du quatrieme degre. Dans ce rapport, nous presentons des resultats generaux obtenus en faisant appel a une source, diffusee dans un cylindre circulaire, arbitrairement choisi, c'est-a-dire sans nous restreindre au disque galactique comme source. Les integrales sont traitees d'une maniere exacte. Les conclusions de Jokipii et Meyer constituent des cas speciaux des resultats precedents. Nous obtenons

  18. 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

  19. Effects of Incorporated Radioactivity and External Radiation on Heterogeneous Catalysis; Effets de la radioactivite incorporee et des rayonnements externes sur la catalyse heterogene; Vliyanie vvedennoj radioaktivnosti i vneshnego oblucheniya na geterogennyj kataliz; Efectos de la radiactividad incorporada y de la irradiacion externa sobre la catalisis heterogenea

    Energy Technology Data Exchange (ETDEWEB)

    Krohn, N. A.; Wymer, R. G. [Oak Ridge National Laboratory, Oak Ridge and University of Tennessee, Knoxville, Tennessee (United States)

    1963-11-15

    {sub 3} - Al{sub 2}O{sub 3} active. Ils ont fait des recherches sur les effets de l'incorporation de radioisotopes dans les catalyseurs et d'une exposition prealable aux rayons gamma du cobalt-60. Les catalyseurs au sulfate de magnesium et au sulfate double de magnesium et de sodium contenant jusqu'a 45,5 mc de {sup 35}S par gramme etaient moins actifs que les catalyseurs non radioactifs de composition analogue si on les comparait par unite de surface. La reduction de l'activite catalytique persistait meme apres qu'une desintegration importante se fut produite. En outre, on n'a pas observe de changements de l'activite catalytique sous exposition a des rayons X au cours de la reaction. On en conclut que l'emission de particules beta par le catalyseur au cours de son emploi est sans effet. Les resultats faisant etat d'une augmentation de l'activite catalytique peuvent etre attribues au fait que pour des conditions donnees de preparation, les catalyseurs radioactifs ont une plus grande surface que leur correspondants non radioactiis et qu'on n'avait pas tenu compte de ce fait. L'exposition prealable de ces catalyseurs aux rayons gamma du cobalt-60 a raison de 10{sup 11} erg/g a ete sans effet sur l'activite du catalyseur. Par contre, la meme exposition prealable des catalyseurs au Cr{sub 2}O{sub 3} - Al{sub 2}O{sub 3} aux rayons gamma du cobalt-60 a raison de 4,2 x 10{sup 11} erg/g a augmente l'activite catalytique d'environ 34% a 485{sup o}C, mais l'incorporation d'une quantite de {sup 147}Pm atteignant 148 mc/g de catalyseur est restee pratiquement sans effet. On n'a pas observe dans ce cas d'effet significatif des rayonnements sur la surface active ou sur l'energie d'activation apparente. (author) [Spanish] Los autores estudian la deshidratacion del ciclohexanol en fase vapor en presencia de catalizadores de sulfato magnesico y d e sulfato magnesico-sulfato sodico, asi como la transformacion del metilciclohexano en tolueno por deshidrogenacion sobre catalizadores de

  20. Radiation Treatment of Meat Products and Animal By-Products; Traitement par Rayonnements des Viandes et Derives et des Sous-Produits Animaux; Radiatsionnaya obrabotka myasnykh produktov i subproduktov zhivotnogo proiskhozhdeniya; Irradiacion de la Carne y sus Derivados

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, P. -I.E. [Danish Meat Research Institute, Roskilde (Denmark)

    1966-11-15

    Application of radiation in food technology can only be considered as an alternative to existing preservation methods when a higher quality product and/or a cheaper product will result, or in cases where no alternative methods exist. With this view in mind, work performed at the Danish Meat Research Institute on sliced bacon, canned hams, luncheon meat, and animal feeding stuffs, i.e. meat and bone meal and blood meal, is reviewed and discussed. The conclusion drawn from the experimental results is that the formation of off-flavours in irradiated meat products is a very serious problem and the most important obstacle to a successful application of irradiation in meat processing. It is, therefore, essential that future research should concentrate on finding means to reduce the irradiation flavour. A number of approaches to solve this problem are mentioned and the Danish work in this field which has been centred mainly on the use of very high dose-rates and of non-equal dose distribution in cans is reviewed, and the concepts briefly described. (author) [French] L'application des rayonnements dans l'industrie alimentaire ne saurait etre consideree en remplacement des methodes de conservation actuelles que s'il en resulte un produit de qualite superieure ou un produit meilleur marche, ou encore lorsqu'on ne peut utiliser aucune methode de rechange. Dans cet esprit, l'auteur examine et commente les travaux accomplis par l'Institut danois de recherches sur la viande concernant le lard en tranches, le jambon en conserve, les pates de viande en conserve (luncheon meat) et les aliments pour animaux, c'est-a-dire les farines de viande et d'os et la farine de sang. Il conclut des resultats experimentaux que la formation de gouts indesirables dans les viandes irradiees pose un probleme tres serieux et constitue l'obstacle le plus important au succes de l'application des rayonnements a la preparation des viandes. Il importe donc que les futures recherches portent avant tout sur

  1. 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

  2. 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

  3. 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.

  4. 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.)

  5. 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

  6. 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

  7. The design and construction of a scintillation pair spectrometer for the detection of {gamma}-rays in the energy range 2-20 MeV; Realisation d'un spectrometre a scintillations et a paires pour la detection des rayonnements {gamma} d'energie comprise entre 2 et 20 MeV

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-15

    The scintillation pair spectrometer is designed to allow the measurement of the energy of {gamma} rays in the range 2 to 20 MeV. Such an instrument is chosen because of its main features: high energy resolution and ease of working. Against this, however, the efficiency is low. It was possible to tolerate this low efficiency because of the facts that the {gamma}-rays studied emanated from (p, {gamma}) reactions and that the two electrostatic acceleration available could provide beams of 500 {mu}A having energy maxima at 300 and 600 keV. We used the {gamma} rays produced by the reactions {sup 23}Na (p, {gamma}) {sup 24}Mg, {sup 19}F (p, {alpha} {gamma}) {sup 16}O and {sup 7}Li (p, {gamma}) {sup 8}Be as well as the {gamma} rays emitted by sources of RTh and of {sup 24}Na. Under these conditions the spectrometer attained a resolving power of 6,5 {+-} 0,5 per cent at 6,1 MeV and it was able to separate the 14,8 and 17,6 MeV lines produced by the reaction {sup 7}Li (p, {gamma}) {sup 8}Be. As well as this, the efficiency which varied from 2.10{sup -4} to 1,7.10{sup -3} between 2 and 20 MeV was well above the efficiencies already obtained with this type of instrument. (author) [French] Le spectrometre a scintillations et a paires presente dans cette these a pour but de mesurer l'energie des rayonnements {gamma} dans la bande de 2 a 20 MeV. Le choix d'un tel appareil est du a ses caracteristiques essentielles: bonne resolution en energie et maniabilite. Par contre, son efficacite est faible. Nous avons pu tolerer cette faible efficacite car les rayonnements {gamma} que nous avons etudies provenaient de reactions (p, {gamma}) et les deux accelerateurs electrostatiques dont nous disposions pouvaient fournir des faisceaux de 500 {mu}A avec des energies maximum de 300 et 600 keV. Nous avons utilise les rayonnements {gamma} produits par les reactions {sup 23}Na (p, {gamma}) {sup 24}Mg, {sup 19}F (p, {alpha} {gamma}) {sup 16}O et {sup 7}Li (p, {gamma}) {sup 8}Be ainsi que les

  8. 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.

  9. 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...

  10. 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...

  11. 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.

  12. 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.

  13. Synthesis of Graft Copolymers by Small Doses of Irradiation; Synthese des copolymeres greffes au moyen de petites doses de rayonnements; Sintez privitykh sopolimerov s pomoshch'yu malykh doz oblucheniya; Sintesis de copolimeros de injerto mediante pequenas dosis de radiacion

    Energy Technology Data Exchange (ETDEWEB)

    Dobo, J; Somogyi, M; Kiss, L

    1960-07-15

    In addition to grafting, there is often an undesirable alteration in the properties of the original polymer when polymer monomer mixtures are irradiated. As a result of irradiation, grafting occurs not only on the original polymeric backbone, but also on the already grafted side-chains. The result is an acceleration of grafting. The effect is especially pronounced in the case of preformed polymers, if irradiation is carried out intermittently. The grafting of styrene can be accelerated by the addition of some solvents which suppress the protective effect of the styrene on the polymer. Grafting can be accelerated by other additives. The swelling properties of the irradiated films were investigated. (author) [French] Lorsque des melanges de polymeres et de monomeres sont soumis a des rayonnements, il se produit souvent, en meme temps que la greffe, une alteration facheuse des proprietes du polymere original. L'irradiation provoque une reaction de greffage, non seulement sur le polymere original, mais aussi sur les chaines laterales deja greffees. Il en resulte une acceleration du processus de greffage. L'effet est particulierement marque dans le cas des polymeres preformes, lorsque l'irradiation est effectuee par intermittence. On peut accelerer le processus de greffage du styrolene en ajoutant certains solvants qui suppriment l'action protectrice du styrolene sur le polymere. On peut aussi accelerer le processus a l'aide d'autres additifs. Les auteurs ont etudie les proprietes de gonflement des pellicules irradiees. (author) [Spanish] Simultaneamente con el injerto, bajo la accion de las radiaciones se produce frecuentemente una alteracion de las propiedades del polimero original, efecto que convendria evitar. Por lo tanto, quiza ofrezcan interes los elevados grados de injerto obtenidos en nuestros laboratorios con pequenas dosis de radiacion. La irradiacion no solo provoca una reaccion de injerto en la estructura polimerica original, sino tambien en las cadenas

  14. 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.

  15. 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

  16. 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.

  17. 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

  18. Design Experience on a Multi-Mecacurie Radiation Facility; Etudes et experiences concernant un emetteur de rayonnements de plusieurs megacuries; Opytnoe proektirovani e ustanovki, obladayushchej sverkhmoshchnym izlucheniem; Estudios sobre el proyecto de un dispositivo de irradiacion de varios megacuries

    Energy Technology Data Exchange (ETDEWEB)

    Brunton, D C; Donovan, J; Voyvodic, L [Curtiss-Wright Corporation, Princeton, NJ (United States); Armour Research Foundation, 10 W. 35th Street, Chicago 10, IL (United States)

    1960-07-15

    This paper describes the research and development work on radiator design and engineering which has been carried out with respect to the design of the {sup H}igh Intensity Food Irradiator{sup .} The problems discussed are those common to all large, package irradiators. The first phase of the research and development work was devoted to achieving a clear understanding of plaque type radiators and the effect of changes in the design parameters on the performance of such a unit. Initially, the performance of a single plaque radiator was studied theoretically, experimentally and by computer analysis. The parameters studied were source size and specific activity, source thickness and cladding, target density and geometrical factors including source and target heights, lengths and widths, and size of air gap between source and target. The performance was examined with respect to capacity, dwell time in the unit, dose uniformity, unit efficiency, and overall cost. Simplified expressions for radiator performance have been developed and verified by experiment. A three dimensional code for applying a Monte Carlo type analysis to radiator performance has been developed and applied to this problem with good agreement with experimental measurements. The radiator design programme was expanded to include an investigation of multi-plaque, multi-pass systems and hence includes essentially the three dimensional matrix of sources as well as plaque type radiators. Engineering requirements with respect to conveyors for product handling are examined in conjunction with source design and effect on performance specifications. Source handling methods, safety systems and facility controls are likewise reviewed. Finally the preparation of the source material itself including measurement, encapsulation and leak testing is described. (author) [French] Le memoire decrit les travaux de recherche et de mise au point pour le dessin et la construction d'emetteurs de rayonnements, effectues en vue

  19. 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.

  20. 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

  1. 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.

  2. 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.

  3. 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....

  4. 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 ...

  5. 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.

  6. Use of alpha-radiation for the industrial measurement of surface weight; Utilisation du rayonnement alpha pour les mesures industrielles de poids superficiel; Primenenie al'fa-oblucheniya dlya promyshlennogo izmereniya vesa naruzhnogo pokrova; Empleo industrial de los rayos alfa para la medicion de pesos por unidad de superficie

    Energy Technology Data Exchange (ETDEWEB)

    Perette, J; Maugest, J [Compagnie d' Applications et Recherches Atomiques, Saint-Denis (France)

    1962-01-15

    The possibility of using alpha-radiation for industrial measurement of the surface weight of thin materials has been mentioned by several authors. The techniques have been adapted for industrial use thanks to research on new equipment which, while employing standard techniques, was specially designed for alpha-radiation. To compensate for variations in the absorbent capacity of the source-detector interval, a two-path differential method must be used. By alternate feeding of the ionization chambers, alternate amplification and detection circuits can be used without prior conversion of the ionization current. The measurement range is 6 to 55 g/m{sup 2} and measurement is accurate to 1% in conditions of perfect stability. The complete equipment used for continuous measurement on production machines is described. The technique can also be used with beta-radiation. (author) [French] Les possibilites d'emploi du rayonnement alpha pour les mesures industrielles de poids superficiel de materiaux minces ont deja ete citees par plusieurs auteurs. L'exploitation industrielle de ces techniques a pu se developper grace a l'etude de nouveaux appareils qui, bien qu'utilisant des techniques classiques, ont ete specialement concus pour l'utili sation du rayonnement alpha. L'emploi d'une methode differentielle a deux trajets est indispensable pour la compensation des variations de pouvoir absorbant de l'intervalle source-detecteur. L'alimentation en alternatif des chambres d'ionisation permet l'utilisation de circuits alternatifs d'amplification et de detection sans conversion prealable du courant d'ionisation. La gamme de mesure s'etend de 6 g a 55 g/m{sup 2} avec line precision de 1% dans des conditions de parfaite stabilite. On decrit le dispositif complet utilise pour les mesures en continu sur les machines de production. Cette technique est egalement utilisable pour les rayonnements beta. (author) [Spanish] Diversos investigadores ya han mencionado la posibilidad de emplear

  7. Technical Developments in the USAEC Process Radiation Development Program; Etudes technologiques dans le cadre du programme de mise au point d'applications industrielles des rayonnements de la CEA-EU; Issledovaniya v oblasti promyshlennogo primeneniya izluchenij, vkhodyashchie v programmu komissii po atomnoj ehnergii USAEC; Progresos tecnicos en el programa de la USAEC para el fomento de la irradiacion industrial

    Energy Technology Data Exchange (ETDEWEB)

    Machurek, J. E.; Stein, M. H. [Division of Isotopes Development, USAEC, Washington, DC (United States)

    1963-11-15

    A broad range of researches have been undertaken in the USAEC 'Process radiation development program'. The primary objective of these studies is to foster development of technology leading to the productive industrial use of ionizing radiation. Results of fourteen of these investigations are reported.some in outline in this paper and some in detail in these Proceedings. The subjects included are researches on: (1) Preparation of wood-plastic combinations using gamma radiation to induce polymerization. (2) Use of fission-product beta radiation for the hydrogenation of coal and coal products to produce liquid hydrocarbon fuels. (3) Production of semi-conductor devices with the formation of predetermined spacial distribution impurity patterns via neutron transmutation doping. (4) Radiation-induced polymerization of ethylene and copolymers. (5) Basic studies in radiation-induced reaction mechanisms and kinetics. (6) Radiation chemistry involved in the fluorination of various aromatic compounds. (7) Use of polyfunctional monomers for enhanced radiation cross-linking of polyethylene, polypropylene, polyisobutylene and cellulose acetate. (8) Effect of swelling, strain and temperature on the physical and chemical properties of radiation produced polymers. (9) Radiation-induced changes in polymers leading to graft copolymerization as influenced by structural factors. (10) The utilization of nuclear radiation for the modification of textile materials. (11) Radiation-induced reactions utilizing krypton-85. (12) The preparation of a ''Radiation Handbook''. (13) Use of the organometallic bond in high level gamma radiation dosimetry. (14) The development of a solar cell dosimeter. (author) [French] Des recherches tres diverses ont ete entreprises dans le cadre du programme de mise au point d'applications industrielles des rayonnements execute par la CEA-EU. Ce programme a pour but essentiel de favoriser le developpement de la technologie en vue d'un emploi industriel productif

  8. The Importance of Dosimetry to the Medical Management of Persons Accidentally Exposed to High Levels of Radiation; Le Role de la Dosimetrie Dans les Soins Medicaux a Donner aux Personnes Accidentellement Exposees a de Fortes Doses de Rayonnement; 0417 041d 0410 0427 0414 ; Importancia de la Dosimetria para el Tratamiento Medico de las Personas Accidentalmente Expuestas a Dosis Elevadas de Radiaciones

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, G. A.; Lushbaugh, C. C. [Medical Division, Oak Ridge Institute of Nuclear Studies (United States); Auxier, J. A. [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1965-06-15

    Radiation accidents continue to occur sporadically and it appears that there is no hope of eliminating them entirely. The management of patients exposed to large doses of radiation is constantly improving because of increasing ability to prevent and treat infection and to control haemorrhage. The possible effectiveness of temporary bone marrow grafts offers promise of a further reduction in mortality. The use of this growing biological information is closely related to, and to a large extent dependent upon, improvements in physical dosimetry for radiation accidents. (author) [French] Des accidents provoques par les rayonnements continuent a se produire de temps a autre et il ne semble guere que l'on puisse esperer les eliminer entierement. Toutefois, le traitement des sujets exposes a de fortes doses de rayonnement ne cesse de s'ameliorer; on parvient, en effet, dans une mesure croissante a empecher et a traiter l*infection ainsi qu'a arreter l'hemorragie. Comme la greffe temporaire de la moelle des os semble devoir donner des resultats, on peut s*attendre a une nouvelle reduction du taux de mortalite. L'application de ces connaissances biologiques sans cesse accrues est fonction, dans une large mesure, des ameliorations apportees a la dosimetrie physique des accidents nucleaires. (author) [Spanish] De vez en cuando se siguen produciendo accidentes de irradiacion y las perspectivas de evitarlos por completo parecen ser bastante remotas. El tratamiento de las victimas expuestas a dosis elevadas de radiaciones mejora constantemente debido a la creciente posibilidad de prevenir y tratar las infecciones, y de controlar las hemorragias. Tambien es posible que la eficacia de ios injertos temporales de medula osea se traduzca en una disminucion de la mortalidad. El aprovechamiento de estos conocimientos biologicos cada vez mas amplios guarda una estrecha relacion con los perfeccionamientos en materia de dosimetria fisica en caso de accidentes de irradiacion. (author

  9. Early Post-Irradiation Changes in the Metabolism of Biogenic Amines; Les Changements Precoces du Metabolisme des Amines Biogenes apres Irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Deanovic, Z [Institut Rudjer Boskovic, Zagreb, Yugoslavia (Croatia)

    1971-03-15

    There is accumulating evidence for the radiation-induced release of biogenic amines from their body stores. Having in mind the high patho-physiological activity of these ''local'' hormones and ''neuro-hormones'', it is reasonable to assume that they play an important role in the pathogenesis of the acute radiation syndrome. Under these pathological conditions the possible synergic and antagonistic effects of biogenic amines due to their complex interactions must be taken into consideration. The extent and dose-dependence of post-irradiation changes in the metabolism of histamine, serotonin, catecholamines and acetylcholine will be examined regarding particularly the search for biochemical indicators of radiation injury. The determination of bio-amines and their metabolites in urine seems to be a suitable method for following up those metabolic changes which could be of a biodosimetrical and/or prognostical value. Data published on this subject, obtained in experimental animals as well as in man, have been reviewed and the applicability of these tests is discussed. (author) [French] Des preuves se sont accumulees, qui demontrent que les amines biogenes sont liberees de leurs depots sous l'effet des rayonnements ionisants. Etant donne la grande activite pathophysiologique de ces hormones 'locales' et 'neurohormones', il est raisonnable de considerer que ces substances biogenes jouent un role important dans la pathogenese du syndrome aigu d'irradiation. Dans ces conditions pathologiques il faut tenir compte des effets synergiques et antagonistes des bio-amines, lies a des interactions compliquees. Les changements metaboliques en fonction de la dose recue font l'objet d'un examen qui englobe les alterations quantitatives de .'histamine, de la serotonine, des catecholamines et de l'acetylcholine et dont l'objectif est la recherche sur des indicateurs biochimiques de la lesion provoquee par l'irradiation. L'analyse des bio-amines et de leurs metabolites dans les urines

  10. 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.

  11. 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)

  12. 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.

  13. 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)

  14. Application of Nuclear Radiation to Textile Materials and Processes. Radiation-induced graft copolymerization of vinyl monomers and fibrous polymers; Applications des rayonnements aux textiles. Formation radiochimique de copolymeres ''greffes'' par l'action de monomeres vinyliques sur des polymeres en fibre; Primenenie yadernogo izlucheniya v tekstil'noj promyshlennosti. Obrazovanie privitykh sopolimerov iz vinilovykh monomerov i voloknistykh polimerov pod dejstviem izlucheniya; Aplicaciones de las radiaciones nucleares a los procesos y materiales textiles. Copolimerizacion por injerto radioinducida de monomeros vinilicos y de polimeros fibrosos

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, Jr., A. A.; Rutherford, H. A. [University of North Carolina at Raleigh, NC (United States)

    1963-11-15

    materials is not good enough for commercial acceptance. The strength of cellulose acetate yam, as well as the modulus, can be materially increased by the addition of polyacrylonitrile. Other monomers do not behave in this manner. There is some indication that the fibre may be improved with one compound, especially with respect to its behaviour in the wet state. Fibre modification by the procedure described might be practical commercially if techniques that will increase the rate of diffusion of the monomer into the fibre structure can be developed. (author) [French] Les auteurs ont mis au point une methode qui permet de realiser par les rayonnements un greffage homogene de monomeres vinyliques volatils sur des polymeres en fibres. Elle consiste a ajouter le compose organique en phase vapeur; on procede, soit par irradiation de l'ensemble, soit par irradiation prealable des polymeres, aux rayons du cobalt-60. Les auteurs ont etudie des systemes qui accelerent la formation des copolymeres ''greffes''; ils ont constate qu'il est possible d'ajouter des quantites significatives de plusieurs des monomeres sans qu'il en resulte de dommages radioinduits dans le substrat fibreux. Les polymeres en fibres relativement instables en presence des rayonnements sont ceux qui fixent le plus facilement les composes vinyliques. C'est le cas des matieres cellulosiques, des esters de cellulose, des polyamides et du polypropylene. Le monomere s'ajoute au substrat fibreux par un mecanisme de radicaux libres, et, comme on l'a indique plus haut, on peut irradier d'abord les polymeres et ensuite provoquer le greffage par exposition de la matiere irradiee S la vapeur du monomere. On a tente de determiner la duree de vie des radicaux libres; il est difficile de donner des chiffres exacts, mais on a demontre qu'ils peuvent subsister dans certaines fibres 15 a 20 heures apres l'irradiation, meme a la temperature ambiante. Des resultats experimentaux preliminaires donnent egalement a penser que le temps

  15. 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.

  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

    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...

  17. 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...

  18. 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.)

  19. 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.

  20. 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.

  1. 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

  2. Some Problems of Calculation and Design of High-Activity Gamma Units; Quelques aspects du calcul et de l'etablissement de projets d'installations puissantes emettrices de rayonnement gamma; Nekotorye voprosy rascheta i proektirovaniya moshchnykh gamma-ustanovok; Algunos aspectos del calculo y construccion de instalaciones de irradiacion gamma de elevada intensidad

    Energy Technology Data Exchange (ETDEWEB)

    Bibergal, A V; Leshchinsky, N I; Margulis, U Ya; Khrushev, V G [Academy of Sciences of the USSR, Moscow, Union of Soviet Socialist Republics (Russian Federation)

    1960-07-15

    The report describes the principal requirements for gamma units intended for various purposes. Several methods of calculating the dose fields for various forms of irradiators are given, as well as graphs, nomograms and formulae to estimate the amount of gamma-ray dose absorbed by the irradiated object from cobalt-60 and caesium-137. Some of the calculated data have been confirmed by experiment. The advantages of irradiators of various geometry employed in experimental and commercial units are discussed. The irradiation technique for various objects is analyzed and the optimum irradiation conditions (radiation utilization factor, dose field homogeneity, etc.) are discussed. Several rational shielding systems are suggested to simplify irradiation process and recharging, and to reduce the cost of design and operation. (author) [French] Resume Cette communication expose les conditions fondamentales auxquelles doivent satisfaire les installations emettrices de rayonnement gamma, destinees, a divers usages. Elle explique certaines methodes pour le calcul des champs recevant une dose determinee en fonction de la forme du dispositif d'irradiation; elle contient des courbes, des nomogrammes et des formules permettant de calculer la valeur de la dose de rayons gamma du cobalt-60 et du cesium-137 recue par l'echantillon soumis a l'irradiation. Certaines donnees etablies par le calcul ont ete confirmees experimentalement. On examine l'utilite d'employer des dispositifs d'irradiation de configurations variees dans des installations experimentales et des installations industrielles. Les auteurs examinent la technologie de l'irradiation de divers echantillons en vue de choisir les conditions optimales d'irradiation (facteur d'utilisation du rayonnement, uniformite du champ recevant une dose determinee, etc.). Quelques systemes rationnels de protection, simplifiant le processus d'irradiation, sont exposes ainsi que des methodes permettant un echange de charge dans les

  3. Recovery of Mice Thymus after X-Rays and 15 MeV Electrons. Comparative Study of the Cell Population Using Tritiated Thymidine; Regeneration du Thymus chez la Souris Apres Irradiation par des Rayons X et des Electrons de 15 MeV. Etude Comparee de la Population Cellulaire a l'Aide de Thymidine Tritiee; 0412 043e 0414 ; Restauracion del Timo de los Ratones Despues de Irradiarlo con Rayos X y Electrones de 15 MeV. Estudio Comparativo de la Poblacion Celular Utilizando Timidina Tritiada

    Energy Technology Data Exchange (ETDEWEB)

    Biagini, C.; Paleani Vettori, P. G.; Zito Bignami, R. [Istituto di Radiologia dell' Universita and Comitato Nazionale per l' Energia Nucleare, Rome (Italy)

    1962-02-15

    The mechanism of recovery from acute radiation damage may be studied by using two types of radiations which show small differences in the acute RBE, and large differences of effect in the recovery phase. As observed in previous experiments, this condition is achieved by comparing the effects in mammals of 150 kVpX-rays and those of 15 MeV electrons produced by a betatron. The present paper presents the results of an autoradiographic study on the behaviour of single classes of cells of the mice thymus by use of tritiated thymidine as DNA precursor. Data are related to the modifications in distribution of the size categories of the cell population and to organ weight. After irradiation the large to small cell ratio is increased ; the incorporation of tritiated thymidine is reduced in large and in small lymphocytes. In the acute phase of effect, no significant differences between X-rays and electrons are observed in cell sizes and in labelling of large cells. A relative change appears in labelling of small cells, a fact that may have a relation with the RBE values of fast electrons, in agreement with the organ weight data. In the recovery, less differentiated cells show active proliferation, but the percentage of mature lymphocytes remains small. After exposure to 15 MeV electrons proliferative activity of large cells is greater, according to the time curves of the thymic atrophy. From the above results, regenerative potentiality appears related to the degree of damage on primitive cells; for a given dose, the latter appears larger after X-rays than after electrons. (author) [French] On peut etudier le mecanisme de la guerison de radiolesions aiguees en utilisant deux types de rayonnements, qui ont a peu pres le meme EBR, mais dont les effets sont tres differents pendant la phase de regeneration. Comme les auteurs l'ont observe dans des experiences anterieures, une bonne methode consiste a comparer, chez des mammiferes, les effets des rayons X de 150 kVp avec ceux des

  4. Theoretical and experimental study of a calorimetric technique for measuring energy deposition in materials caused by complex pile irradiation; Etude theorique et experimentale d'une technique calorimetrique de mesure des depots d'energie dans les materiaux dus au rayonnement complexe de pile

    Energy Technology Data Exchange (ETDEWEB)

    Mas, P; Sciers, P; Droulers, Y [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires, 38 - Grenoble (France)

    1962-07-01

    Calorimetric methods may be used to measure gamma fluxes greater than 10{sup 6} r/h near the cores of swimming pool reactors. The theory, design, and properties of isothermal calorimeters are discussed, and experimental results obtained with two types are presented. Measurement of energy deposition in materials and the long term integration of energy depositions are other uses of these devices. Results of measurements on heat deposition in steel and water are given. Fluxes were also measured. (authors) [French] Une premiere partie traite de la theorie des calorimetres isothermes mis en oeuvre au C.K.N. Grenoble. La puissance deposee dans le calorimetre par les flux de rayonnement echauffe celui-ci. L'echauffement est mesure a l'aide d'un thermocouple. On montre que l'on a ainsi une mesure absolue de cette puissance. Une deuxieme partie traite de l'etude experimentale de: deux types d'appareils utilises: leur construction, les resultats experimentaux, leurs utilisations. Trois de celles-ci sont particulierement interessantes: - la mesure des hauts flux gamma, - la mesure du depot d'energie dans les materiaux, - l'integration pendant une longue duree des depots d'energie (un modele de calorimetre a fonctionne a ce jour 2 500 heures et a integre 9 x 10 puissance 10 rads gamma et 6 x 10 puissance 18 neutrons rapides). La troisieme partie est consacree a l'etude des qualites de l'appareil: robustesse, fidelite, precision, sensibilite, gamme de mesure. Enfin dans la derniere partie sont decrites deux applications de la methode calorimetrique a la mesure du depot d'energie dans un acier special et dans l'eau. (auteurs)

  5. Chemical Changes Induced by Irradiation in Meats and Meat Components; Transformations Chimiques Provoquees par les Rayonnements dans les Viandes et Leurs Constituants; Khimicheskie prevrashcheniya v myasnykh produktakh i ikh sostavnykh chastyakh pod vozdejstviem oblucheniya; Alteraciones Quimicas Producidas por Irradiacion de las Carnes y de sus Componentes

    Energy Technology Data Exchange (ETDEWEB)

    Merritt, C. Jr. [Pioneering Research Division, United States Army Natick Laboratories, Natick, MA (United States)

    1966-11-15

    The acceptability of meats preserved by irradiation has been hampered by the formation of an irradiation flavour and odour. This flavour and odour is believed to be due to the volatile chemical compounds produced by radiation impact on the protein and lipid molecules. The analysis of the volatile compounds has been accomplished, employing programmed cryogenic temperature gas chromatography for separation of the complex mixtures obtained, and rapid scanning mass spectrometry for identification of the individually separated components. Comprehensive analyses of the volatiles from irradiated ground beef, pork, mutton, lamb, and veal, as well as the volatile irradiation degradation products of several amino acids and proteins, animal fats, methyl esters of fatty acids, and triglycerides have been made. The results of the analysis of the irradiated component meat substances are compared with those obtained from the irradiation of meat itself, and of separate meat fractions, thus establishing the contribution of each fraction to the total. Mechanisms are postulated for the formation of the volatile components from each fraction and for interactions among intermediates from different fractions. (author) [French] La comestibilite des viandes conservees par les rayonnements s'est trouvee diminuee a la suite de l'apparition dans celles-ci d'un gout et d'une odeur engendres par l'irradiation. On pense que ces derniers sont dus aux composes chimiques volatils qui sont formes par l'action des rayonnements sur les molecules des proteines et des lipides. Il a ete procede a l'analyse des composes volatils a l'aide d'un programme de chromatographie en phase gazeuse a temperature cryogenique visant a separer les constituants des melanges complexes obtenus, et par spectrometrie de masse a balayage rapide destinee a identifier les constituants separes. L'auteur a effectue des analyses completes des composes volatils emanant de viande hachee de boeuf, de porc, de mouton, d'agneau et de

  6. Perspectives for the Use of Ionizing Radiation in the Decontamination (Salmonella Radicidation) of Some Frozen Proteinaceous Foods and Dry Mixed Feed Ingredients; Perspectives de l'Emploi des Rayonnements pour la Decontamination (Radicidation de Salmonella) de Certains Aliments Proteiques Congeles et des Constituants de Melanges Alimentaires Secs pour Animaux; Perspektivy ispol'zovaniya ioniziruyushchego izlucheniya dlya unichtozheniya bakterij (Gruppy Salmonella) nekotorykh zamorozhennykh belkovykh osnovnykh pishchevykh produktov i sukhikh komponentov smeshannogo'fura; Radiodescontaminacion (Radicidacion de la Salmonella) de Algunos Alimentos Proteicos Basicos Congelados y de Componentes de Alimentos Secos para Animales

    Energy Technology Data Exchange (ETDEWEB)

    Mossel, D. A.A. [Central Institute for Nutrition and Food Research T.N.O., Zeist (Netherlands)

    1966-11-15

    and Peru might be the most promising areas for the first tests of this sort, as they are amongst the greatest exporters of some of the commodities that are most frequently found contaminated with Salmonellae (frozen boneless horse meat, and fish and cottonseed meals), while having generally well- equipped laboratories and reasonably well-trained graduate staff available. A 50 000-Ci source of {sup 60}Co, or an X-ray machine of a similar output, may be successfully used in such test runs. Microbiological evaluation techniques for routinely controlling the efficacy of such irradiation treatments have already been worked out and tested under pilot plant conditions. Finally, wherever possible, the merits of these radicidation treatments should be experimentally compared with those of competitive, conventional processing methods, such as pelleting in the decontamination of feed ingredients; this approach would make it possible for the industries concerned to take their decisions at the completion of the first commercial-scale tests. (author) [French] La decontamination par les rayonnements, notamment celle des denrees proteiques de base a faible activite chimique de la teneur en eau est apparue comme une des premieres applications prometteuses de l'energie ionisante au traitement des denrees alimentaires destinees a la consommation humaine ou animale; les raisons en sont les suivantes: a) alteration radio chimique limitee des denrees en question; b) absence de toute proliferation microbienne apres irradiation; c) avantages techniques souvent exceptionnels, telle la possibilite d'application a des produits deja empaquetes, par exemple aux constituants de melanges alimentaires pour animaux, et la decontamination efficace sans alteration simultanee de la fraicheur, notamment dans le cas des viandes rouges et de la volaille. Comme premiere etape, on a procede anterieurement a des experiences en laboratoire en vue de determiner les diverses doses necessaires et de verifier

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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 ...

  18. 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.

  19. The Main Technological Characteristics of Apparatus for Industrial Radiochemical Processes, in Particular Ethylene Polymerization; Caracteristique techniques fondamentals des appareils pour l'application industrielle de reactions chimiques sous rayonnement (notamment la polymerisation de l'ethylene ); Osnovnye tekhnologicheskie kharakteristiki apparatov dlya provedeniya radiatsionno-khimi-cheskikh protsessov (v chastnosti, dlya polimerizatsii ehtilena) v promyshlennom masshtabe; Principales caracteristicas tecnologicas de los aparatos para la aplicacion industrial de reacciones radioquimicas

    Energy Technology Data Exchange (ETDEWEB)

    Syrkus, N P; Breger, A K; Weinstein, B I [Karpov Physicochemical Institute, Moscow, USSR (Russian Federation)

    1960-07-15

    The paper gives a general review of some of the main technological features of apparatus, for instance spherical apparatus, for industrial radiochemical processes. A method is proposed for estimating the effectiveness of apparatus of any given construction by comparing it with the output of an infinitely large apparatus having the same radiation source. An account is given of the technological features of an apparatus for radio-polymerizing ethylene at 200 atmospheres and 25{sup o}C{sup 1} with a rodshaped gamma-radiation source (Co{sup 60}) of variable activity. This apparatus can be designed to suit the mean dose rate which the power efficiency of the apparatus allows. It is shown that the yield, Q, of the apparatus is, other things being equal, a constant ration of the power, W{sub 0}, of the gamma-radiation of the apparatus. In the apparatus reviewed, Q {approx} W{sub 0}{sup 0,5}. (author) [French] Le memoire contient un expose general des caracteristiques techniques essentielles des appareils, par exemple d'un appareil du type spherique, pour l'application industrielle de reactions chimiques sous rayonnement. Le memoire propose une methode pour evaluer l'efficacite d'appareils de tous types en comparant la productivite de chaque modele avec celle d'un appareil infiniment grand, alimente par une source de rayonnement identique. Le memoire indique le calcul des caracteristiques techniques de l'appareil destine a la polymerisation sous rayonnement de l'ethylene (pression : 200 atmospheres, temperature: 25{sup o}C{sup 2} avec une source allongee de rayonnement gamma Co{sup 60} pour diverses activites. Un appareil de ce type peut etre calcule selon les valeurs moyennes de l'intensite des doses, determinees selon la valeur du coefficient d'efficacite totale energetique de l'appareil. On constate que la productivite (Q) de l'appareil, toutes choses egales d'ailleurs, est puissance de l'intensite (W{sub 0}) du rayonnement gamma de l'appareil. Pour l'appareil considere

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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 ...

  7. The use aeroplanes and vehicles for prospecting. The technique of the detection radioactivity. The future opened up by the use of the discrimination of energies; Methodes de prospection autoportee et aeroportee. La technique de la detection des rayonnements. Les perspectives offertes par la discrimination des energies

    Energy Technology Data Exchange (ETDEWEB)

    Guitton, J; Berbezier, J; Blangy, B; Lallemant, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The idea of installing activity detectors on aeroplanes and vehicles has been widely applied by the CEA since the start of prospecting in the arid and tropical regions of the Communaute Francaise. Three systems of detection have been developed and compared in a systematic manner: a group of 50 G.M. tubes; the sodium iodide scintillator; the plastic scintillator. The sodium iodide scintillator is used as a standard reference; the results are compared by graphical recording. Airborne prospecting is carried out in two stages: the initial flights, which follow a kilometre square network, make possible the discovery of the most likely zones; these likely zones are then examined in greater detail using light aeroplanes or helicopters. The two types of airborne scintillation measuring devices which have been developed by the CEA are described in this article. The practical results obtained during systematic and detailed airborne prospecting campaigns in the Hoggar are described. The difficulty in airborne uranium prospecting is to be able to immediately distinguish while in flight, anomalies caused by uranium from those caused by thorium. (author) [French] L'idee de monter des detecteurs de rayonnements sur des avions ou des vehicules a ete largement appliquee par le CEA des le debut des prospections dans les pays sahariens et tropicaux de la Communaute Fran ise. On a realise et compare d'une maniere systematique trois moyens de detection: groupe de 50 tubes GM; scintillateur d'iodure de sodium, scintillateur plastique. L'appareil de reference sera le scintillateur d'iodure de sodium; les resultats sont compares par enregistrement graphique. La prospection aeroportee se fait en deux etapes; les premiers vols systematiques suivant un quadrillage kilometrique permettent de reperer les zones interessantes; ces dernieres font l'objet d'examens plus detailles effectues en avion leger ou en helicoptere. Dans cet article, on decrit les deux types de scintillometres aeroportes

  8. Experimental study of the effect of an electric field on thermal exchanges under forced convection with gaseous carbon anhydride in presence of the radiation of the Melusine pile; Etude experimentale de l'effet d'un champ electrique sur les echanges thermiques en convection forcee avec l'anhydride carbonique gazeux en presence du rayonnement de la pile Melusine

    Energy Technology Data Exchange (ETDEWEB)

    Perroud, P.; Rebiere, J.; Verdier, J.

    1961-01-21

    Previous studies showed that, under free or forced convection, the application of a non-uniform electric field with a sufficient intensity at the neighbourhood of the heating elements resulted in a significant improvement of the thermal exchange coefficient under some flow rate and pressure conditions. But these improvements first required the creation of ions in the gas (shock ionization and existence of a corona effect above a sufficient voltage). This document therefore report further studies performed at the neighbourhood of the Melusine atomic pile which would provide ionizing radiations of much greater intensity. The objectives were, on the one hand, a global verification of work hypotheses imagined for the exchange improvement mechanism, and, on the other hand, to obtain data on the conditions under which this exchange improvement mechanism could be used in channels of a reactor. The authors present the instrumentation (measurement cells, gas circuit, heating circuit, high voltage circuit), describe how physical values are measured (pressure, gas flow rate, temperature of the heating element, gas temperature, high voltage). They describe how they compare powers exchanged under forced convection between dioxide carbon and a heated wire with or without external ionizing radiations, and report the various performed calculations (power supplied to the gas, temperature shift, Nusselt and Reynolds numbers). They report and discuss experimental results obtained outside the pile without ionizing radiations, and within the pile in presence of a ionizing radiation [French] Les essais ont ete effectues dans les conditions suivantes: nombres de Reynolds variant de 20.000 a 80.000, pression de 11 a 21 kg/cm{sup 2}, temperatures moyennes de l'element chauffant de 200 a 600 deg. C, tension electrique de 0 a 30 kV eff et intensite maximum du rayonnement γ, 3x10{sup 7} roentgen/h. On a confirme, hors pile, que l'augmentation de la puissance echangee, au dessus du seuil d

  9. Rapid Estimation of Fast-Neutron Doses following Radiation Exposure in Criticality Accidents: The S{sup 32}(n, p)P{sup 32} Reaction in Body Hair; Prompte Evaluation des Doses de Neutrons Rapides apres une Exposition au Rayonnement a la Suite d'Accidents de Criticite: Reaction {sup 32}S(n, p){sup 32}P dans le Systeme Pileux; 0411 042b 0421 0414 ; Evaluacion Acelerada de Dosis de Neutrones Rapidos Despues de una Irradiacion Consecutiva a un Accidente de Criticidad: La Reaccion {sup 32}S(n, p){sup 32}P en el Pelo

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, D. F. [Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1965-06-15

    Unique chemical composition, fixed anatomical location, and ready availability combine to make human hair a useful material for rapid estimation of fast neutron doses sustained by personnel involved in accidental nuclear critical excursions. The sulphur content of human hair is remarkably constant regardless of sex, colour, or distribution; values of 0.048 {+-}0.005 g sulphur per gram of hair indicate that 5% can be used as a standard figure for the abundance of sulphur in preliminary dose estimates without resorting to individual sulphur analyses. In the absence of easily removable external contamination, hair contains less than 0.025% phosphorus; since the activation cross-sections of phosphorus and sulphur are similar, the virtual absence of phosphorus permits the use of hair as a biological sulphur threshold detector for measuring the flux of neutrons with energies in excess of 2.5 MeV by the S{sup 32}(n, p)P{sup 32} reaction. Techniques for rapid isolation of radiochemically pure P{sup 32} have been developed with a view toward providing clinically useful estimates of the fast neutron exposure of criticality accident victims. In the absence of gross fission product contamination, preliminary estimates can be made within two hours; the more extensive procedure for eliminating fission products requires approximately six hours for a preliminary estimate. Experiments employing the well-defined fission spectrum of an unshielded critical assembly have consistently provided estimates of neutron dose within {+-}10% of referee dosimetry. Moreover, the fixed anatomical location of hair samples makes it possible to deduce orientation and asymmetry of exposure from a comparison of the relative specific activities of samples from different regioris of the body. Experience with three nuclear critical excursions resulting in fatalities has demonstrated that in each case exposures were markedly asymmetrical. Thus, P{sup 32} measurements on hair provide valuable complementary information for comparison with average total-body neutron exposure estimates based on blood Na{sup 24} measurements. Fission yield estimates based on deduced geometries in each case were in good agreement with independent determinations of total fissions by more conventional analytical procedures. For rapid approximations of fast neutron dose, P{sup 32} activity in dpm/g hair at T = 0 from any counting system of known efficiency is simply multiplied by 0.49 to obtain ''sulphur-level'' neutron dose in rads. (author) [French] Etant donne sa composition chimique constante, sa situation anatomique fixe et sa facilite de prelevement, le systeme pileux de l'homme offre un materiau de choix permettant d'evaluer en peu de temps des doses de neutrons rapides recues par le personnel implique dans des accidents de criticite. La teneur en soufre du cheveu ou du poil est remarquablement constante, independente du sexe, de la couleur ou de la region ou il pousse; comme cette teneur est de 0,048 {+-} 0,005 g au gramme, on peut prendre le chiffre de 5% pour les estimations preliminaires de dose, sans avoir a proceder chaque fois a un dosage individuel du soufre. En l'absence d'une contamination externe facile a eliminer, le cheveu ou le poil contient moins de 0,025% de phosphore; etant donne que les sections efficaces d'activation du soufre et du phosphore sont semblables, l'absence virtuelle de phosphore permet d'utiliser le soufre du cheveu ou du poil comme un detecteur biologique a seuil pour la mesure du flux de neutrons de 2,5 MeV et plus, en appliquant la reaction {sup 32}S(n, p){sup 32}P. On a mis au point des methodes d'isolement rapide de {sup 32}P radiochimiquement pur pour permettre des estimations a des fins cliniques de l'exposition aux neutrons rapides des victimes des accidents de criticite. En l'absence d'une forte contamination par les produits de fission, on peut proceder aux evaluations dans les deux heures. Le procede plus complet qui comporte l'elimination des produits de fission exige environ six heures pour une evaluation preliminaire. Des experiences a l'aide du spectre de fission bien defini provenant d'un assemblage critique non blinde fournissent constamment des evaluations de dose de neutrons ne s'ecartant pas plus de 10% en plus et en moins des mesures dosimetriques de reference. En outre, du fait de la position anatomique fixe des echantillons pileux, on. peut connaitre l'orientation et le parametre d'asymetrie de l'exposition en comparant les activites specifiques d'echantillons provenant de differentes regions du corps. On a constate a l'occasion de trois emballements critiques qui ont fait des victimes que, dans chaque cas, les expositions etaient nettement dissymetriques. Ainsi, le dosage du {sup 32}P sur le systeme pileux fournit des renseignements complementaires de grande valeur que l'on peut comparer avec les evaluations de l'exposition totale du corps aux neutrons par la mesure de la teneur du sang en {sup 24}Na. Des estimations du rendement de fission, fondees sur les geometries deduites dans chaque cas, concordent bien avec les evaluations independantes des fissions totales obtenues par des methodes analytiques plus classiques. Pour la determination approximative rapide de la dose des neutrons rapides, il suffit de multiplier par 0,49 l'activite du {sup 32}P dans le cheveu ou dans le poil, exprimee en desintegrations par minute et par gramme, a la temperature O, obtenue avec tout ensemble de comptage d'une sensibilite connue,- pour obtenir la dose en rad des neutrons dits de la 'bande du soufre'. (author) [Spanish] Dada su composicion quimica constante, su situacion anatomica fija y la facilidad con que pueden sacarse muestras, el pelo humano constituye un material muy util para determinar en poco tiempo las dosis de neutrones rapidos recibidas por el personal afectado por accidentes de criticidad. El contenido en azufre del cabello y del pelo humano es notablemente uniforme y no depende del sexo, del color o de la zona de localizacion; arroja valores de 0,048*0,005 g de azufre por gramo de pelo, de modo que en las evaluaciones preliminares de dosis se puede emplear como norma la cifra de 5% para la abundancia de azufre sin necesidad de efectuar analisis individuales. En ausencia de una contaminacion externa, facil de eliminar, el pelo contiene menos del 0, 025% de fosforo; como las secciones eficaces de activacion del fosforo y el azufre son similares, la ausencia virtual de fosforo permite emplear el azufre del pelo como detector biologico de umbral para medir flujos neutronicos de energia superior a 2,5 M e V por la reaccion {sup 32}S(n, p){sup 32}P. Se han perfeccionado tecnicas de separacion rapida de radioquimicamente puro para poder evaluar con fines clinicos la exposicion a los neutrones rapidos de las victimas de accidentes de criticidad. Si la contaminacion por productos de fision no es grave se puede efectuar una evaluacion preliminar en el plazo de dos horas; 'mientras que si es necesario eliminarla, el procedimiento requiere aproximadamente seis horas. Los experimentos efectuados con el espectro de fision bien definido de un conjunto critico sin blindar han dado siempre para la dosis -neutronica valores que diferian en menos de 10 Degree-Sign Inverted-Exclamation-Mark o de los hallados por los metodos dosimetricos de control. Ademas, comparando las actividades especificas de muestras de pelo de diversas zonas del cuerpo, se puede determinar la orientacion y la asimetria de la exposicion. La experiencia adquirida en tres accidentes de criticidad mortales ha demostrado que las exposiciones eran siempre marcadamente asimetricas. Asi, pues, las determinaciones del {sup 32}P presente en el pelo suministran datos complementarios muy valiosos que pueden compararse con las evaluaciones de la exposicion neutronica media del organismo entero por medicion del {sup 24}Na contenido en la sangre. Las evaluaciones de los rendimientos de fision, basadas en las geometrias que se han deducido para cada caso, concordaban satisfactoriamente con las determinaciones independientes de las fisiones totales efectuadas por procedimientos analiticos clasicos. Para obtener rapidamente la dosis aproximada de neutrones rapidos, basta multiplicar por 0,49 la actividad del {sup 32}P, expresada en des/min. g de pelo a T = 0 y medida con cualquier sistema de recuento de rendimiento conocido, para obtener la dosis neutronica en rad correspondiente al 'nivel azufre'. (author) [Russian] Sochetanie unikal'nogo himicheskogo sostava, opredelennogo anatomicheskogo stroenija i dostupnosti, delaet chelovecheskij volos poleznym materialom dlja bystroj ocenki doz bystryh nejtronov, poluchaemyh personalom, svjazannym s rabotoj v avarijnyh uslovijah v kriticheskom sostojanii. V chelovecheskom volose otmechaetsja odno i to zhe soderzhanie sery, nezavisimo ot pola, cveta ili raspredelenija. Velichina 0,048 {+-} 0,005g sery na 1 g volosa ukazyvaet, chto 5 % mogut byt' ispol'zovany v kachestve standartnoj cifry dlja harakteristiki soderzhanija sery pri predvaritel'nyh ocenkah dozy bez vnesenija popravok na analiz soderzhanija sery v volosah otdel'nyh lic. Pri otsutstvii legko udaljaemogo vneshnego zagrjaznenija v volosah soderzhitsja menee 0,025 procentov fosfora. Poskol'ku poperechnye sechenija aktivacii fosfora i sery odinakovy, fakticheskoe otsutstvie fosfora daet vozmozhnost' ispol'zovat' volos v kachestve porogovogo detektora dlja biologicheskoj sery pri izmerenii potoka nejtronov s jenergiej svyshe 2,5 Mjev s pomoshh'ju reakcii S{sup 32}(n, p)P{sup 32}. Razrabotany metody dlja bystrogo vydelenija radiohimicheski chistogo R{sup 32} s cel'ju obespechenija klinicheski poleznyh ocenok obluchenija bystrymi nejtronami postradavshih vo vremja avarij v kriticheskom sostojanii. Pri otsutstvii bol'shogo zagrjaznenija produktami delenija predvaritel'nye ocenki mozhno provesti v techenie dvuh chasov. Dlja osushhestvlenija bolee shirokoj procedury po udaleniju produktov delenija dlja celej predvaritel'noj ocenki trebuetsja priblizitel'no shest' chasov. V rezul'tate provedenija jeksperimentov s ispol'zovaniem chetko opredelennyh spektrov delenija na nejekranirovannoj kriticheskoj sborke postojanno imelas' vozmozhnost' dat' ocenku nejtronnoj dozy v predelah {+-}10% v ramkah jetalonnoj dozimetrii. Bolee togo, opredelennoe anatomicheskoe stroenie obrazcov volos daet vozmozhnost' umen'shit' orientaciju i asimmetriju obluchenija v rezul'tate sravnenija otnositel'nyh udel'nyh aktivnostej obrazcov v razlichnyh chastjah organizma. Opyt raboty vo vremja treh jadernyh avarij v sostojanii kritichnosti, privedshih k zhertvam, pokazal, chto v kazhdom sluchae obluchenie bylo'zametno asimmetrichnym. Tak, v rezul'tate izmenenij soderzhanija R{sup 32} v volosah priobretaetsja cennaja dopolnitel'naja informacija dlja sravnenija so srednimi ocenkami nejtronnogo obluchenija vsego organizma, osnovannymi na izmerenijah soderzhanija Na{sup 24} v krovi. Ocenki vyhoda produktov delenija, osnovannye na metodah deduktivnoj geometrii, v kazhdom sluchae nahodilis' v horoshem soglasii s provedennymi nezavisimo opredelenijami obshhego vyhoda produktov delenija bolee obychnymi analiticheskimi metodami. Dlja bystrogo priblizitel'nogo opredelenija dozy bystryh nejtronov velichina aktivnosti R{sup 32} v rasp/min/g v volosah pri T = 0 pri ljuboj sisteme scheta izvestnoj jeffektivnosti prosto umnozhaetsja na kojefficient 0,49 dlja poluchenija velichiny nejtronnoj dozy v radah, vyrazhennoj v vide ''urovnja sery''. (author)

  10. 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)

  11. 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

  12. The non ionizing radiations; Les rayonnements non ionisants

    Energy Technology Data Exchange (ETDEWEB)

    Vecchia, P. [Institut National de la Sante, Lab. de Physique, Rome (Italy); Souques, M. [Electricite de France (EDF), Service des Etudes Medicales, 75 - Paris (France); Lambrozo, J. [EDF/GDF, Service des Etudes Medicales, 75 - Paris (France)] [and others

    2003-07-01

    The biological effects of non ionizing radiations are studied in this part. The magnetic fields and the cardiac implants, melatonin secretion among the electricians exposed to magnetic fields of 50 hz, the effects of electromagnetic fields in professional medium, evaluation of the effect of an exposure to a signal of a mobile phone (GSM 900) on the skin are the different subjects discussed. (N.C.)

  13. The radiations and the living; Les rayonnements et le vivant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The radiation and the living is divided in five parts: biological radiation effects, early response to ionizing radiation, molecular and cellular effects, external radiotherapy, internal radiotherapy, principles of NMR imaging. About the biological radiation effects, whereas first models of biological effects were based on the sole dose at the cell nucleus, it now appears that the origin of the effects lies in the production of scarce critical events -micro energy-deposits overlapping the DNA. Recent theories have successively examined the role of track-end ionization clusters and of core ionizations in DNA atoms. About the molecular and cellular radiation effects, because of the important role of the DNA molecule, radio-induced DNA lesions are more studied. Many cells are able to respond effectively to the DNA lesions in the minutes, the hours, the days which follow the aggression: early response. This respond can lead, in the case of cells irradiated in mitotic activity, to the stop at critical stages of cell cycle, time to activate the systems of repair of genomic lesions. However, when the badly or not repaired DNA lesions durably persist, this state creates a risk of passage of mutations in the daughter cells. The persistence of these lesions can also engage cells towards processes of cellular death by apoptosis or necrosis. In this lecture will be developed different classes of identified lesions, cellular antioxidant defenses, then the various key molecules involved in the early response after irradiation. The third part devoted to external radiotherapy tell us that radiotherapy is naturally at the edge between medicine and physics. Over the past twenty years, where external radiation therapy moved towards an increased conformation of the dose distribution (conformal therapy), major improvements (extensive use of MRI and PET for tumor imaging and delineation, beam optimization methods to improve the dose distribution, on line imaging) originally came from the physics world. During this overview of external radiation therapy, we will first consider the basic concepts (types of particles, dose distribution, particle accelerators, radiobiological concepts, treatment planning models) and then follow the procedure of a standard treatment, in order to notice the routine use of the concepts, the problems encountered (precision in particular) and the practical experience. From this an from the recent improvements in radiation therapy, we will finally illustrate how much the transfer of knowledge and technology from physics to the hospital can improve the daily treatment of the patients. Whatever can be said about the evolution of various treatment modalities, external beam radiotherapy is still under active development. Concerning internal radiotherapy, when, in nuclear medicine, a radiopharmaceutical compound is an association of a radioactive emitter and a biological vector and that kind of therapeutic agents is used safely to treat both benign or malign diseases: this is called internal radiotherapy. Depending on localisation and effectiveness various compounds have been developed by manufacturers. They are specifically directed against a given disease and use beta emitters in order to get a high radiation dose in a small volume. Although historically bound to treatment of thyroid disease with iodine 131, internal radiotherapy meets a renewed interest with the use of new antibodies linked to yttrium 90 or iodine 131 in hematology, or in the treatment of Gastro Entero Pancreatic (G.E.P.) tumors with radiolabeled somatostatin analogs. In the last course, the principles of nuclear Magnetic Resonance (NMR) and image formation (MRI) are presented. T1 and T2 contrast mechanism and one example of gradient echo pulse sequence are described. In the last part of the course, two main applications in neuroimaging are analysed, functional MRI and diffusion MRI. These five courses are followed by overheads relative to levels of living organization, natural history of cancer (in two parts), internal radiotherapy, applications of subatomic physics tools to the areas of nuclear medicine. (N.C.)

  14. Effects of Radiation on Germ Cells of Insects: Dominant Lethals, Gamete Inactivation and Gonial-Cell Killing; Effets des rayonnements sur les cellules germinales des insectes: letalite dominante, inactivation des gametes et destruction des cellules des gonades; Vozdejstvie radiatsii na polovye kletki nasekomykh: dominantnye letali, inaktivatsiya gamet i umershchvlenie polovykh kletok; Efectos de las radiaciones sobre las celulas germinales de los insectos: elementos letales dominantes, inactivacion de los gametos y exterminacion de las celulas gonadicas

    Energy Technology Data Exchange (ETDEWEB)

    Von Borstel, R. C. [Biology Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1963-09-15

    Radiations and chemical mutagens kill cells in numerous ways: by one of several kinds of induced dominant lethality, by a direct inactivation of function as with sperm, and by genetically undefinable types of death which may or may not be related to dominant lethality per se. Also, chemical mutagens appear to exert a curious enhancement of the fertilizing capacity of sperm. The different stages of oflgenesis and spermatogenesis respond with unequal sensitivity to radiation, and individual cells pass through stages conferring as much as a 50-fold difference in sensitivity. Where species of Diptera, Hymenoptera and Coleoptera can be compared, a striking similarity of response to radiation can be observed, both to stage sensitivity and degree of response with dose. The silkworm, Bombyx mori (Lepidoptera), seems to be similar in most respects to representatives of the other orders in response of germ cells to radiation, but differs sharply in types of dominant lethality induced. Species having atypical genetic mechanisms (e.g.,the lecanoid system of Planococcus citri (Hemipt. : Coccidae) are special cases, and their responses to radiation are considerably modified from those of other species. For insect population control by the irradiation-of-male method, dominant lethality is as advantageous in species where matings are multiple as in species where mating occurs once. Sperm inactivation and gonial killing can be regarded as instances of true sterility and are maximally effective only in species where mating occurs once. For most efficient control, doses should be chosen which would induce maximum dominant lethality, minimum sperm inactivation and complete killing of gonial cells. These parameters are simple to determine by gamete viability measurements, irradiated and unirradiated population competition experiments and histological examination of gonia. (author) [French] Les rayonnements et les agents chimiques de mutation detruisent les cellules de nombreuses facons

  15. Technical and Economic Considerations in the Preservation of Meats and Poultry by Ionizing Radiation; Considerations d'Ordre Technique et Economique sur la Conservation des Viandes et de la Volaille par les Rayonnements Ionisants; Tekhnicheskie i ehkonomicheskie soobrazheniya otnositel'no'konservatsii myasa i ptitsy s pomoshch'yu ioniziruyushchikh izluchenij; Consideraciones Tecnicas y Economicas Acerca de la Conservacion de Carnes y Volateria por Irradiacion

    Energy Technology Data Exchange (ETDEWEB)

    Urbain, W. M. [Department of Food Science, Michigan State University, East Lansing, MI (United States)

    1966-11-15

    Radiation-sterilized meats and poultry can be of a quality better than that obtained with thermal processing. Where the normal method of preservation of meat and poultry during distribution is refrigeration, radiation at sterilizing levels is not likely to replace it. A principal reason for this is cost. In such a civilian market, radiation-sterilized meats will serve primarily as convenience foods. Radiation-pasteurization could provide a significant product life extension for fresh meats and poultry by delaying microbial spoilage, especially in the centralized preparation of retail cuts. Other factors of meat spoilage of a chemical or physical nature, however, are not controlled by radiation; and until they are, there is no real marketing value in the use of radiation. For fresh or frozen poultry there is the possibility of Salmonella control, should this be needed. Costs for sterilization and pasteurization are estimated and are presented in a form to permit selection of specific conditions within a range for certain important variables. From a commercial viewpoint, it is important to determine the consumer acceptance of radiation- sterilized meats and poultry. The usual approach to such a determination is to market the products in question in a limited manner and to measure the acceptance under such market conditions. To accomplish this with radiation-sterilized foods, the next step appears to be to obtain a production capability to supply the products for test marketing. (author) [French] Les viandes et la volaille sterilisees par les rayonnements peuvent etre de meilleure qualite que celle obtenue par un traitement thermique; Lorsqu'on utilise la refrigeration comme methode normale de conservation de la viande et de la volaille en cours de distribution, il est peu probable qu'on lui substitue l'irradiation a des doses sterilisantes. La principale raison eri est le cout eleve de l'irradiation. Dans un marche destine a repondre aux besoins civils, les viandes

  16. Establishment and Study of Dose Fields for the Irradiation of Experimental Animals with High-Energy Protons; Creation et Etude de Champs de Rayonnements pour l'Irradiation d'Animaux de Grande Taille par des Protons de Haute Energie; Sozdanie i issledovanie doznykh polej dlya oblucheniya ehksperimental'nykh zhivotnykh protonami bol'shoj ehnergii; Produccion y Estudio de Campos Radia Torios para la Exposicion de Animales de Laboratorio a Protones de Elevada Energia

    Energy Technology Data Exchange (ETDEWEB)

    Afanas' ev, V. P.; Keirim-Markus, I. B.; Kuznecova, S. S.; Litvinova, Je. G.; Sokolova, I. K.; Stukina, L. E.

    1964-03-15

    Present-day accelerators make it possible to obtain beams of protons which have adequate intensity but are not suitable for the general irradiation of large experimental animals. Using the synchrotron of the Joint Institute of Nuclear Research it has been shown that with the aid of absorbers it is possible to expand a proton beam to the dimensions required, without introducing the accompanying radiations. Dose fields, uniform within {+-} 10%, in which primary protons constitute between 99 and 88% of the tissue dose, were obtained for irradiation of dogs with protons of energy 510, 250 and 120 MeV. The tissue doses and the radiation composition were studied in a dog phantom. Irradiation conditions for ensuring uniform radiation of the dog's body are proposed. Various questions of high-energy proton dosimetry are discussed, and the use of different types of dosimeter are considered in this connection. The paper also describes a method of determining the contribution of cascade neutrons to the proton flux, using activation detectors. (author) [French] Les accelerateurs actuels permettent d'obtenir des faisceaux de protons d'une intensite suffisante mais impropres a l'irradiation generale de grands animaux d'experience. A l'aide du synchrocyclotron OIAI, on a montre que le recours aux absorbants permet d'elargir le faisceau de protons jusqu'aux dimensions voulues sans y introduire de rayonnements secondaires. Pour irradier des chiens par des protons de 510, 250 et 120 MeV, on a pu ainsi realiser des champs de rayonnements uniformes a {+-}10% pres, dans lesquels les protons primaires constituaient 99 a 88% de la dose tissulaire. Les auteurs ont etudie des doses tissulaires et la composition du rayonnement a l'interieur d'un fantome de chien. Ils indiquent dans quelles conditions on assure une irradiation uniforme du corps de l'animal. Les auteurs examinent plusieurs questions relatives a la dosimetrie des neutrons de grande energie. Ils justifient l'emploide divers

  17. 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...

  18. 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.

  19. 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.

  20. 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

  1. Description of Radiation Sources Installed at the French Atomic Energy Commissariat; Description de sources de rayonnement installees au commissariat a l'energie atomique; Opisanie istochnikov oblucheniya, nakhodyashchikhsya v frantsuzskom komissariate po atomnoj ehnergii; Descripcion de las fuentes de radiaciones instaladas en el commissariat a l'energie

    Energy Technology Data Exchange (ETDEWEB)

    Leveque, P

    1960-07-15

    partie de cette casemate est amenagee en chambre frigorifique ce qui permettra de faire des essais de conservation alimentaire sous rayonnement. - les canaux verticaux du reacteur EL 2 dits ''trous de chimiste''; lorsque ces canaux sont chemises avec une feuille de cadmium, le flux gamma obtenu passe de 100 000 a 200 000 r/h mais ils ne peuvent servir qu'a l'irradiation de matieres organiques car il y a activation de la plupart des produits mis a irradier par le flux epithermique et rapide. L'auteur decrit ensuite le dispositif du Centre Lyonnais d'Applications atomiques, cree pres de Lyon par un groupe d'industriels. Cette installation, dont la mise en service est prevue pour le debut de 1960, aura un caractere semi-industriel (source de cobalt-60 de 3 000 dans un premier stade, puis de 40 000 curies) et permettra d'effectuer des irradiations en continu. (author) [Spanish] El autor describe en primer lugar cuatro instalaciones que se encuentran en el Centro de Estudios Nucleares de Saclay: - una fuente de {sup 60}Co de 600 curies, para laboratorio; el dispositivo utilizado es sencillo y seguro, pero no permite modificar a voluntad la intensidad del flujo de rayos gamma; - un conjunto de 7 fuentes de {sup 60}Co (de las cuales la mas potente tiene 1 000 curies) instalado en una casamata de hormigon; un dispositivo neumatico permite colocar en posicion de trabajo la fuente o las fuentes necesarias; - una casamata con capacidad suficiente para recibir 100 barras de combustible procedentes del nuevo reactor EL-3; un sector de esta casamata esta acondicionado como camara frigorifica, lo que permitira llevar a cabo ensayos sobre la conservacion de alimentos por irradiacion; - los canales verticales del reactor EL-2 denominados ''orificios para usos quimicos'''; cuando estos canales se revisten interiormente con laminas de cadmio, la intensidad del flujo de rayos gamma aumenta de 100 000 a 200 000 roentgens/hora , pero solo puede utilizarse para la irradiacion de sustancias

  2. Application of Radiation for the Control of Salmonellae in Various Foods; Destruction des Salmonellae par les Rayonnements dans Divers Produits Alimentaires; Primenenie izluchenij dlya unichtozheniya salmonell v razlichnykh pishchevykh produktakh; Empleo de las Radiaciones Ionizantes en la Lucha Contra las Salmonellae de Diferentes Aumentos

    Energy Technology Data Exchange (ETDEWEB)

    Ley, F. J. [Wantage Research Laboratory (A.E.R.E.), Wantage, Berks. (United Kingdom)

    1966-11-15

    Microbiological studies on the use of ionizing radiation for the elimination of Salmonellae from various foods have demonstrated that a wide variety of factors can influence the radiation sensitivity of the organisms. These factors include the nature of the food itself and the temperature during irradiation, e.g. whether frozen or unfrozen. The difference in resistance of different serotypes of Salmonellae irradiated under the same conditions has also been well established. Dose/survival curves constructed for the purpose of making a choice of dose for a particular application must therefore be established for the practical conditions envisaged and be based on the most resistant serotype present. Since these conditions can never be exactly reproduced in the laboratory, the choice of dose should be confirmed by a substantial amount of work with the naturally-contaminated material. It is apparent that the doses required for the treatment of various foods lie within the' range 0.5 to 1.0 Mrad, achieving a reduction in numbers of initial populations by a factor of between 10{sup 5} and 10{sup 7} . The most promising processes are those considered for frozen and dried-egg products, frozen meats and animal feedingstuffs. (author) [French] A la suite d'etudes microbiologiques sur la possibilite d'employer des rayonnements ionisants pour detruire les Salmonellaedans divers produits alimentaires, il est apparu que la radio- sensibiliteide ces organismes depend de nombreux facteurs, en particulier de la nature du produit et de sa temperature (produit congele ou non) pendant l'irradiation. On a egalement reconnu que diverses varietes serologiques de Salmonellae, irradiees dans les memes conditions, ont une radioresistance differente. Des,courbes de survie en fonction de la dose, construites en vue de determiner la dose necessaire poiir Un traitement' donne, doivent donc etre etablies pour les conditions pratiques envisagees et compte tenu de la plus resistante des varietes

  3. 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

  4. The Effects of Beta Rays (Tritium) on the Growth of Rickettsiae and Influenza Virus; Effets du Rayonnement Beta (du Tritium) sur la Proliferation des Rickettsies et des Virus de la Grippe; 0414 0435 ; Influencia de los Rayos Beta (Tritio) sobre la Multiplicacion de Rickettsia y de Virus de la Gripe

    Energy Technology Data Exchange (ETDEWEB)

    Greiff, D. [Marquette University, School of Medicine, Milwaukee, WI (United States)

    1962-02-15

    vesiculaire) etait completement inhibee -dans les oeufs contenant de l'oxyde de tritium a raison de 180, 90 et 45 millicuries par oeuf et partiellement inhibee chez les groupes contenant 22,5 et 11,2 millicuries par oeuf. Des resultats analogues ont ete obtenus apres inoculation d'oxyde de tritium, a raison de 1 millicurie pour 10{sup 8} cellules, dans des cultures de cellules KB, disposees en couches isolees et infectees par R. mooseri ou R. akari. L'injection d'oxyde de tritium, avant l'infection par le virus, a eu pour effet de reduire la periode latente pour la liberation des virus de la grippe hors de la membrane chorio-allantoieque des oeufs -embryonnes. Deux heures apres l'inoculation de l'agent infectieux, le nombre des virus s'etait multiplie par mille dans les fluides chorio-allantoieques des oeufs traites. Lorsque des quantites -decelables de virus sont apparues dans les fluides chorio-allantoieques des oeufs temoins, huit heures apres l'infection, la DI{sub 50} des oeufs trities etait de 10{sup -5,6}; vingt-quatre heures apres l'infection, les deux series presentaient une DI{sub 50} de 10{sup -7,5}. Les quantites de virus dans les membranes des oeufs trities etaient egalement accrues. La liberation du virus a ete obtenue par les procedes suivants: enlevement et lavage des membranes, sechage des membranes par sublimation sous vide a basse temperature et rupture des cellules des membranes par rehydratation dans l'eau distillee. (author) [Spanish] La multiplicacion de Rickettsia mooseri (tifus de los roedores) aumenta' considerablemente en los huevos fecundados cuando estos contienen 180, 90 y 45 mcuries de oxido de tritio por huevo siendo el incremento ligero en los que contienen solamente 22,5 mcuries/huevo ; cuando solo se administran 11,2 mcuries/huevo, no se aprecia ningun aumento de la infeccion en comparacion con los testigos. La multiplicacion de Rickettsia akari (viruela rickettsial) quedo totalmente inhibida en los huevos que contenian 180, 90 y 45 mcuries

  5. 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.

  6. [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.

  7. 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-20 β dihydroprogestérone (3 mg/kg) à des femelles dont les ovocytes sont au stade de « vésicule germinative semi-périphérique » entraîne une chute du niveau de t-GtH, très hautement significative 24 h. après injection, qui résulte vraisemblablement d'une rétroaction négative sur la sécrétion hypophysaire. Par la suite, après ovulation, la t-GtH plasmatique s'élève davantage chez les femelles subissant la rétention des ovules (50 µg/ml environ) que chez les femelles ...

  8. Radioisotopes and Radiation in Animal and Plant Insect Pest Control; Emploi des radioisotopes et des rayonnements dans la lutte contre les insectes nuisibles aux plantes et aux animaux; Ispol'zovanie radioizotopov i radiashchi v bor'be s nasekomymi-vreditelyami rastenij i zhivotnykh; Utilizacion de los radioisotopos y de las radiaciones en la lucha contra los insectos nocivos para las plantas y los animales

    Energy Technology Data Exchange (ETDEWEB)

    Andreev, S. V.; Martens, B. K.; Samojlova, V. A.; Molchanova, Z. I. [Vsesoyuznyj Institut Zashchity Rastenij, Leningrad, SSSR (Russian Federation)

    1963-09-15

    degrees of stability when subjected to the action of herbicides. Pesticides containing trace quantities of isotopes with short half-lives can be used as a means of judging the merits of various spraying systems for treating seeds and agricultural crops with pesticides; this method also provides information about the optimum doses. Experiments have shown that ionizing radiations can be used to increase the virulence of insect nosophytes (Beauveria vassiana Unill.) and thus improve the efficiency of microbiological insect-pest-control methods. The sterilizing and lethal effects of ionizing radiations are also useful in combatting insect pests. Gamma-ray experiments have made it possible to establish sterilizing doses for a number of insect pests which attack crops and stored products (Calandra granaria L., Acanthoscelides obtectus Say, Pectinophora malvella Hb., Leptinotarsa decemlineota Say, Chloridea obsoleta F.). The data obtained in these investigations will be used to develop and improve the methods of insect-pest control used in agriculture. (author) [French] Le probleme de la lutte contre les parasites des cultures presente une grande importance pour l'economie nationale. Il importe, pour le resoudre, de tirer parti des realisations scientifiques les plus recentes. Pour rationaliser les methodes actuelles de lutte contre les insectes nuisibles et accroitre l'efficacite de ces methodes, on a fait appel aux radioisotopes et aux rayonnements. Grace a remploi des radioisotopes et des rayonnements, il est possible de rationaliser dans une large mesure les methodes utilisees et d'augmenter leur efficacite. A cet effet, il est indispensable d'etudier a fond les problemes d'ecologie, de toxicologie, etc. Dans le domaine de l'ecologie, la methode du radiomarquage des insectes est particulierement prometteuse. L'emploi de radioisotopes pour le marquage des insectes ravageurs des cereales (Eurygaster integriceps Put. et Hadena sordida Skh.) et de leurs parasites (Meniscus

  9. Effect of cobalt-60 {gamma} radiation and of thermal neutrons on high resistance P and N silicon. Possibility of obtaining a nuclear compensation for P type silicon; Effects du rayonnement {gamma} du cobalt 60 et de neutrons thermiques sur du silicium P et N de haute resistivite. Possibilite de realiser une compensation nucleaire d'un silicium du type P

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-11-01

    Type P silicon has been compensated by the production of a controlled and uniform amount of donor atoms ({sup 31}P) using thermal neutrons to bring about a nuclear transformation. It is shown that it is possible in this way to reduce by a factor of about one hundred the overall concentration of residual ionised impurities in the purest crystals obtained by floating zone purification (2 x 10{sup 12} atoms/cm{sup 3}). The degree compensation obtained is limited by the initial inhomogeneity of acceptor impurities which have to be compensated. Lattice defects which still remain after prolonged annealings reduce the life-time of the material to about 10 {mu}s approximately. Particle detectors having thicknesses of 2 to 5 mm have been built by this process; they give good results, particularly at low temperatures. A study has also been made of the number and of the nature of lattice defects produced by thermal neutrons in high resistivity P and N type crystals. These defects have been compared to those produced by {gamma} rays from {sup 60}Co. A discussion is given of the validity of the Wertheim model concerning pronounced recombination at low temperatures (77 deg. K - 300 deg. K) of primary defect-interstitial pairs. The nature of the defects introducing energy levels into the lower half of the forbidden band has been studied. (author) [French] On a compense du silicium de type P en produisant, au moyen de neutrons thermiques, par transmutation nucleaire une quantite controlee et uniforme d'atomes donneurs ({sup 31}P). On montre qu'on peut ainsi reduire de cent fois environ la densite nette d'impuretes ionisees residuelles subsistant dans les cristaux les plus purs obtenus par purification par zone flottante (2.10{sup 12} atomes/cm{sup 3}). Le degre de compensation obtenu est limite par i'inhomogeneite initiale des impuretes acceptrices a compenser. Des defauts de reseau qui subsistent meme apres des recuits prolonges reduisent la duree de vie du materiau a 10 {mu

  10. An Assessment of those Metabolites Considered to be of Value in the Diagnosis of Exposure to Radiation; Evaluation des Metabolites Consideres Comme Utiles dans le Diagnostic des Expositions aux Rayonnements; 041e 0426 0414 ; Evaluacion de los Metabolitos Considerados Utiles para Diagnosticar la Exposicion a las Radiaciones

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H.; Bates, T. H. [United Kingdom Atomic Energy Authority, Chapelcross, Annan, Scotland (United Kingdom)

    1965-06-15

    a suivi de pres - du point de vue quantitatif - l'excretion urinaire des substances suivantes: creatinine, creatine, {beta}-nitramine (total), acide {beta}-amino isobutyrique, acide pyrrole-2-carboxylique, acide hydroxy-5-indolylacetique et indoxyle-sulfate. Bien qu'aucun des sujets n'ait subi une irradiation de l'organisme entier, on constate que des modifications de la fonction metabolique resultant de radiolesions peuvent influer sur l'excretion urinaire. Les auteurs examinent les raisons biochimiques et l'interpretation de ces formes d'excretion pour la partie de l'organisme qui a ete irradiee; cependant, au stade actuel de l'enquete, ils arrivent a la conclusion qu'une evaluation quantitative des lesions biologiques n'est pas possible. Neanmoins, ces essais peuvent faciliter au clinicien le choix de la therapie a appliquer. Des essais preliminaires sur les changements observes dans certains metabolites du plasma, chez des rats exposes a une seule dose sous-letale de rayons X, meritent d'etre extrapoles en vue de leur application a des etudes sur l'homme. On a mesure les concentrations dans le plasma des matieres ci-apres: hydroxy- 5-tryptamine, acide urique, transaminases glutamo-oxalacetique et glutamo-pyruvique du serum, 'fractions globuliniques de la proteine, phosphokinase de creatine, aminopeptidase de leucine, aminopeptidase de lysyle, callicreine, callidine, zinc et manganese. Des changements qualitatifs pourtant assez importants ont ete observes, apres irradiation, dans les teneurs du plasma en acide urique, en aminopeptidase de leucine, en aminopeptidase de lysyle, en zinc et en manganese. Les auteurs examinent la portee de ces donnees. Dans ces etudes, ils ont surtout utilize des methodes simples et rapides. (author) [Spanish] Se han examinado algunos metabolitos excretados por via urinaria por seres humanos expuestos a radiaciones X y {gamma} con fines terapeuticos. Dichos pacientes habian recibido dosis de hasta 5000 r durante un periodo comprendido

  11. Structure and magnetic properties of new Be-substituted langasites A{sub 3}Ga{sub 3}Ge{sub 2}BeO{sub 14} (A=Pr, Nd, and Sm)

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, A.Z., E-mail: sharmaa5@myumanitoba.ca [Department of Chemistry, University of Manitoba, 66 Chancellors Cir, Winnipeg, MB, Canada R3T 2N2 (Canada); Silverstein, H.J. [Department of Chemistry, University of Manitoba, 66 Chancellors Cir, Winnipeg, MB, Canada R3T 2N2 (Canada); Hallas, A.M. [Department of Physics and Astronomy, McMaster University, 1280 Main St. W, Hamilton, ON, Canada L8S 4M1 (Canada); Luke, G.M. [Department of Physics and Astronomy, McMaster University, 1280 Main St. W, Hamilton, ON, Canada L8S 4M1 (Canada); Canadian Institute for Advanced Research, 180 Dundas Street W, Suite 1400, Toronto, ON, Canada M5G 1Z8 (Canada); Wiebe, C.R. [Department of Chemistry, University of Manitoba, 66 Chancellors Cir, Winnipeg, MB, Canada R3T 2N2 (Canada); Department of Chemistry, University of Winnipeg, 515 Portage Ave, Winnipeg, MB, Canada R3B 2E9 (Canada); Department of Physics and Astronomy, McMaster University, 1280 Main St. W, Hamilton, ON, Canada L8S 4M1 (Canada); Canadian Institute for Advanced Research, 180 Dundas Street W, Suite 1400, Toronto, ON, Canada M5G 1Z8 (Canada)

    2016-01-15

    Langasites have been studied extensively in past for their functional properties and use in telecommunication. A thorough understanding of their ground state is limited by the difficulty in synthesizing new members belonging to this series due to the formation of competing phases such as the garnets. Three magnetic langasites A{sub 3}Ga{sub 3}Ge{sub 2}BeO{sub 14} (A=Pr, Nd, and Sm) and a non-magnetic lattice standard La{sub 3}Ga{sub 3}Ge{sub 2}BeO{sub 14} were synthesized using the ceramic method. These were further characterized by X-ray diffraction, magnetization, magnetic susceptibility and heat capacity measurements. All three langasites exhibit net antiferromagnetic interactions at low temperatures and no evidence of long range magnetic ordering was observed down to 0.350 K. - Graphical abstract: Kagome network formed by the magnetic ions in the new Be-langasites. The ground states of three new members were explored using different physical property measurements such as X-ray diffraction, magnetization, magnetic susceptibility and heat capacity (a–d show refinement patterns for the langasites). These can be added to the list of candidate spin liquid materials. - Highlights: • Four new langasites A{sub 3}Ga{sub 3}Ge{sub 2}BeO{sub 14} (A=La, Pr, Nd, and Sm) were synthesized. • These were characterized using physical and magnetic property measurements. • These langasites exhibit net antiferromagnetic interactions at low temperatures. • No evidence of long range magnetic ordering was observed down to 0.350 K. • Can be potential Spin liquid candidates.

  12. APR1400 Containment Simulation with CONTAIN code

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Moon Kyu; Chung, Bub Dong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-05-15

    The more realistic containment pressure variation predicted by the CONTAIN code through the coupled analysis during a large break loss of coolant accident in the nuclear power plant is expected to provide more accurate prediction for the plant behavior than a standalone MARS-KS calculation. The input deck has been generated based on the already available ARP- 1400 input for CONTEMPT code. Similarly to the CONTEMPT input deck, a simple two-cell model was adopted to model the containment behavior, one cell for the containment inner volume and another cell for the environment condition. The developed input for the CONTAIN code is to be eventually applied for the coupled code calculation of MARS-KS/CONTAIN

  13. APR1400 Containment Simulation with CONTAIN code

    International Nuclear Information System (INIS)

    Hwang, Moon Kyu; Chung, Bub Dong

    2010-01-01

    The more realistic containment pressure variation predicted by the CONTAIN code through the coupled analysis during a large break loss of coolant accident in the nuclear power plant is expected to provide more accurate prediction for the plant behavior than a standalone MARS-KS calculation. The input deck has been generated based on the already available ARP- 1400 input for CONTEMPT code. Similarly to the CONTEMPT input deck, a simple two-cell model was adopted to model the containment behavior, one cell for the containment inner volume and another cell for the environment condition. The developed input for the CONTAIN code is to be eventually applied for the coupled code calculation of MARS-KS/CONTAIN

  14. Monthly results of measurements. Apr 1999

    International Nuclear Information System (INIS)

    1999-01-01

    This report of the O.P.R.I. (Office of Protection against Ionizing Radiations) exposes the principal results concerning the routine monitoring of environmental radioactivity in France: atmospheric dusts, rainwater, surface water, underground water, sewage water, drinking water, food chain (milk, vegetables, fishes), sea water around nuclear sites and other sites. The activities of various radioisotopes are presented in tables. (N.C.)

  15. Monthly results of measurements: Apr 2001

    International Nuclear Information System (INIS)

    2001-01-01

    This report of the OPRI (Office of Protection against Ionizing Radiations) exposes the principal results concerning the routine monitoring of environmental radioactivity in France: atmospheric dusts, rainwater, surface water, underground water, sewage water, drinking water, food chain (milk, vegetables, fishes), sea water around nuclear sites and other sites. The activities of various radioisotopes are presented in tables

  16. Monthly results of measurements: Apr 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This report of the OPRI (Office of Protection against Ionizing Radiations) exposes the principal results concerning the routine monitoring of environmental radioactivity in France: atmospheric dusts, rainwater, surface water, underground water, sewage water, drinking water, food chain (milk, vegetables, fishes), sea water around nuclear sites and other sites. The activities of various radioisotopes are presented in tables

  17. SAJAA MarApr 31-39

    African Journals Online (AJOL)

    Studio G5

    a few NRTIs increase P-glycoprotein activity.17 The induction of .... undergo a more thorough evaluation, which includes blood gas ..... patients with reduced plasma cholinesterase activity (e.g. organophosphate exposure); obese patients.

  18. Võistlused : [kalasport, 28. apr. - 30. juun. 2012

    Index Scriptorium Estoniae

    2012-01-01

    Kevadkalake, Töörahva Kala, Kevadsärg, Vagula Röövik, Saadjärve Haug, EMV Õngitsemises (mehed), Linnakala, Suure-Jaani Spinning, Tuulekala Trolling, Rakvere Koger, Gorodenko Spinning, EMV Õngitsemises (naised ja noored)

  19. IRIS Bimonthly Public Meeting (Apr 2014)

    Science.gov (United States)

    EPA hosted a public meeting/webinar to provide an opportunity for the public to give input and participate in an open discussion regarding several IRIS chemical assessments for Diethyl Phthalate (DEP) and Hexabromocyclododecane (HBCD).

  20. Monthly results of measurements, Apr 1988

    International Nuclear Information System (INIS)

    1988-04-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the routine monitoring of environmental radioactivity in France: atmospheric dusts, rainwater, surface water, underground water, sewage water, drinking water, food chain (milk, vegetables, fishes), sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables. This report exposes also the results of special radiation measurements resulting from the Chernobyl accident [fr

  1. Prevalence and resistance patterns of commensal S. aureus in community-dwelling GP patients and socio-demographic associations. A cross-sectional study in the framework of the APRES-project in Austria.

    Science.gov (United States)

    Hoffmann, Kathryn; den Heijer, Casper D J; George, Aaron; Apfalter, Petra; Maier, Manfred

    2015-05-16

    The aim of the present study was to assess the prevalence and resistance of commensal S. aureus in the nasal microbiota of community-dwelling persons in Austria, as well as to identify possible associations with socio-demographic factors. Multi-drug resistance in this population was additionally studied. This cross-sectional study was conducted within the context of the European APRES project. In nine European countries, nasal swabs were collected from 32,206 general practice patients who received care for non-infectious reasons. In Austria, 20 GPs attempted to recruit 200 consecutive patients without infectious diseases, with each patient completing demographic questionnaires as well as providing a nose swab sample. Isolation, identification, and resistance testing of S. aureus were performed. Statistical analyses included subgroup analyses and logistic regression models. 3309 nose swabs and corresponding questionnaires from Austrian subjects were analyzed. S. aureus was identified in 16.6 % (n = 549) of nose swabs, of which 70.1 % were resistant against one or more antibiotics, mainly penicillin. S. aureus carrier status was significantly associated with male sex (OR 1.6; 1.3-2.0), younger age (OR 1.3; 1.0-1.8), living in a rural area (OR 1.4; 1.1-1.7) and working in the healthcare sector (OR 1.5; 1.0-2.1). Multi-drug resistances were identified in 13.7 % (n = 75) of the S. aureus carriers and 1.5 % (n = 8) tested positive for MRSA. The highest resistance rate was observed against penicillin (64.8 %), followed by azithromycin (13.5 %) and erythromycin with 13.3 %. This study describes the prevalence and resistance patterns of commensal S. aureus in community-dwelling persons in Austria and shows that differences exist between socio-demographic groups. Demographic associations have been found for S. aureus carriers but not for carriers of resistant S. aureus strains. Only two thirds of S. aureus strains were found to be resistant against small spectrum penicillin

  2. Radiation-pulse transmission via a long cable without a preamplifier and/or a pulse transformer; Transmission d'impulsions de rayonnement par cable long sans l'adjonction d'un preamplificateur ou d'un transformateur d'impulsions; Peredacha impul'snykh izluchenij no kabelyu na dal'nie rasstoyaniya bez predvaritel'nogo usileniya i/ili bez preobrazovaniya impul'sov; Transmision de impulsos por cables de gran longitud sin preamplificador y/o transformador de impulsos

    Energy Technology Data Exchange (ETDEWEB)

    Miwa, H; Tohyama, T [Kobe Kogyo Corporation, Okubo, Akashi, Hyogo (Japan)

    1962-04-15

    conditions such as high or low temperature, high neutron (gamma) flux, etc. A single coaxial cable enables the simple operation of detectors in remote positions. Scintillation gamma spectroscopy was not affected by a long cable pulse-transmission of over 500 m. (author) [French] Pour l'introduction de transistors dans les instruments d'electronique nucleaire, la faiblesse inherente de l'impedance d'entree exige certaines modifications du circuit d'entree. Les auteurs ont fait une etude comparee de trois circuits d'entree caracterises par leur tension (systeme 1), leur tension-courant (systeme 2) et leur courant (systeme 3). Le systeme 1 est, dans une large mesure, analogue a celui du circuit des tubes a vide classiques. Les auteurs ont mis au point un emetteur-analyseur polarise par contre-reaction; utilise comme circuit a haute impedance d'entree, depassant 10{sup 7} {Omega}, il a donne d'excellents resultats, sans affecter la stabilite du courant continu. Presque tous les detecteurs de rayonnement peuvent etre consideres comme des generateurs de courant. Ainsi, la sortie des detecteurs peut etre connectee a l'amplificateur a faible impedance d'entree. C'est le systeme 3 qui donne une excellente amplitude d'impulsion; toutefois, la limite superieure de frequence de l'amplificateur devrait depasser 10 MHz, compte tenu de la vitesse des impulsions et de la faible valeur de la constante de temps d'integration a l'entree. Le systeme 2 est une combinaison des deux autres. Le courant de sortie des detecteurs est connecte par une resistance de 10{sup 5} {Omega} environ a l'amplificateur a faible impedance d'entree. La resistance donne la valeur convenable a la constante de temps d'integration a l'entree et ramene a 2 MHz environ la limite superieure de frequence exigee par le circuit electronique. En outre, ce dispositif permet de maintenir la proportionnalite entre l'amplitude de l'impulsion et l'energie du rayonnement. Lorsqu'on emploie des detecteurs a gaz, la resistance joue

  3. Non intrusive measurement of residual moisture rate of plutonium oxide powder in sealed boxes; Mesure non intrusive du taux d`humidite residuel de la poudre d`oxyde de plutonium contenue dans des boites scellees

    Energy Technology Data Exchange (ETDEWEB)

    Pochet, T.; Edeline, J.C.; Domenech, T.

    1993-12-31

    This document deals with the best method to create a non intrusive measurement of residual moisture of plutonium oxide in stainless steel sealed boxes (sensibility, precision, reproducibility and feasibility in laboratory). This method is the neutron spectrometry by {sup 3}He (n,p) {sup 3}He reaction. (TEC). 16 refs., 16 figs., 2 tabs.

  4. Soil contamination. part 1. changes in the humidity of non saturated soils after reject in a limited space. part 2. movements of radioactive ions in non saturated soils after reject in a limited space; Contamination des sols (1. partie). Evolution de l'humidite dans les sols non satures apres rejets sur une surface limitee. (2. partie). Comportement des ions radioactifs dans les sols non satures apres rejets d'eau sur une surface limitee

    Energy Technology Data Exchange (ETDEWEB)

    Rancon, D [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1972-07-01

    upon the counting rate of radioactivity. This method which have allowed to get various results about {sup 131}I and {sup 85}Sr can be generalized to other radioisotopes and other soils. They are applicable to radiological safety of sites studies : Testing storage plants, estimate of accidents hazards and protection of subterranean waters. (author) [French] II est important, dans les etudes de surete radiologique de sites, de connaitre les mouvements d'eau dans les terrains non satures surmontant la nappe aquifere, cette tranche de terrain aere pouvant servir de protection contre la contamination de la nappe. L'utilisation d'humidimetres a neutrons a permis de construire graphiquement les coupes des etats hydriques du terrain et les evolutions dans le temps du volume du sol mouille a partir d'un rejet affectant une superficie restreinte. On mesure aussi les gradients d'humidite, les cinetiques d'assechement, la capacite de retention du sol et la teneur en eau gravifique suspendue en en equilibre avec la charge d'eau. L'etat hydrique initial influence la vitesse d'infiltration et non la vitesse d'avancement du front d'humectation, on peut donc calculer la quantite d'eau accumulable par le terrain. Apres l'arret du rejet, le volume de sol mouille evolue jusqu'a un etat d'equilibre limite par le front d'humectation, les redistributions d'humidite s'effectuant seulement au sein de ce volume; ainsi, en cas de rejet de liquide radioactif, les ions contaminants resteront confines dans un volume mesurable limite par le front d'humectation. Partie 2. Pour faire suite au rapport sur les mouvements d'eau dans les sols non satures apres rejet sur une surface limitee - CEA R 3635 (1) - on etudie les mouvements des ions radioactifs dans ces sols en utilisant un anion et un cathion caracteristiques: l'iode 131 et le strontium 85. La methode est basee sur la mesure simultanee des fronts d'humidite et d'activite au moyen d'humidimetre a neutrons et d'une sonde d'activite specialement

  5. Physical Properties of P.V.C. Attenuated Network Copolymers Produced by Ionizing Radiation; Proprietes physiques des copolymeres obtenus sous l'action de rayonnements ionisants et dont le reseau est attenue par l'effet du chlorure de polyvinyle; Fizicheskie svojstva polivinilkhloridnykh obednennykh tsepej sopolimerov, poluchennykh v rezul'tate vozdejstviya ioniziruyushchej radiatsii; Propiedades fisicas de los copolimeros de redes atenuadas por cloruro de polivinilo obtenidos por irradiacion

    Energy Technology Data Exchange (ETDEWEB)

    Pinner, S H [Tube Investments Research Laboratories, Hinxton Hall, Cambridge (United Kingdom)

    1960-07-15

    The cross-linking of polyvinyl chloride with ionizing radiation poses special problems. Due to rather unfavourable cross-linking and dislinking parameters for this polymer, the radiation doses necessary for high cross-link densities are uneconomicall y large and discolouration and dehydrohalogenatio n are simultaneously produced. These difficulties have been overcome by the incorporation into the P. V. C., prior to irradiation, of diallyl and triallyl esters. Heavily cross-linked products are thereby obtained with relatively low doses of ionizing radiation. Examination of the physical properties of the products suggests that these are not simply graft copolymers, which term normally implies the presence of long branch chains, but are polymer attenuated allyl networks. In these materials, the desirable properties of the parent polymer and of the allyl network are combined. The tensile strength, modulus and elongation of the attenuated network copolymers are presented and discussed as a function of temperature and of the concentration and functionality of the allyl ester. Reference is also made to the swelling and chemical resistance of the products. (author) [French] La reticulation du chlorure de polyvinyle sous l'action des rayonnements ionisants pose des problemes particuliers. Les parametres de reticulation et de degradation etant plutot defavorables pour ce polymere, les doses d'irradiation necessaires a l'obtention de fortes densites de pontage sont trop elevees pour donner des resultats economiquement interessants; elles provoquent simultanement la decoloration et la deshalogenhydratation. Il a ete possible de surmonter ces difficultes par introduction d'esters diallyliques et triallyliques dans le chlorure de polyvinyle, avant irradiation. Ce procede permet d'obtenir au moyen de doses d'irradiation relativement faibles des produits fortement reticules. L'etude des proprietes physiques de ces produits montre qu'il s'agit non pas de simples copolymeres greffes

  6. Potentialités écologiques des carrières de quartzite après exploitation : l'exemple de la carrière de Cheffois (Vendée, France

    Directory of Open Access Journals (Sweden)

    François Bétard

    2011-06-01

    Full Text Available Dans les carrières de roches massives abandonnées après l'exploitation, l'aridité du sol et le caractère oligotrophe du milieu, conjugués à la présence de parois rocheuses et de plans d'eau au niveau des excavations les plus profondes, sont des éléments favorables à l'expression d'une biodiversité renouvelée et originale. Un inventaire écologique mené sur la carrière de quartzite de Cheffois, située dans le sud du Massif Armoricain, a révélé la richesse biologique de ce type de milieu semi-naturel. Les résultats de l'inventaire ont conduit à distinguer six types d'habitats néoformés correspondant à d'anciens secteurs d'exploitation : (1 un plan d'eau de fosse, (2 une zone de carreau humide, (3 une zone de carreau sec, (4 des fronts de taille d'expositions variées, (5 des remblais boisés, et (6 une galerie souterraine. Ces six types de milieux sont eux-mêmes subdivisés en une mosaïque de petits habitats, favorisant au final une grande biodiversité avec le développement de nombreuses espèces végétales et animales, dont certaines à forte valeur patrimoniale. Replacé dans le contexte du Bas-Bocage vendéen, l'apport écologique de la carrière de quartzite est évalué et confronté aux pertes en biodiversité engendrées par l'ouverture de la carrière. Avec les autres carrières de quartzite situées sur les sites rocheux des environs, elles constituent, ensemble, un réseau de carrières partiellement inondées pouvant contribuer à la création d'un véritable corridor écologique, dans une matrice bocagère actuellement en perte de biodiversité.In abandoned quarries of massive rocks, the aridity and oligotrophic character of soils, combined with the presence of rock walls and water bodies in the deeper excavations, are favourable to the expression of a renewed, original biodiversity. An ecological survey carried out on the quartzite quarry of Cheffois, located in the southern Armorican Massif, revealed the

  7. Ar neatliekamās medicīniskās palīdzības brigādēm stacionārā nogādāto pacientu apmierinātība ar veselības aprūpi pirms stacionāra un stacionāra etapā

    OpenAIRE

    Dzene, Dace

    2017-01-01

    Autore: Dace Dzene, stud.apl.nr. dd15034 Darba vadītājs: Dr.med. Igors Ivanovs Ar neatliekamās medicīniskās palīdzības brigādēm stacionārā nogādāto pacientu apmierinātība ar veselības aprūpi pirms stacionāra un stacionāra etapā. Maģistra darbs, Latvijas universitāte, Rīga, 2017. Darbs sastāv no teorētiskās un empīriskās daļas, 6 nodaļām, 66 lapām, 29 attēliem, 10 tabulām, 2 pielikumiem. Pētījuma mērķis ir noskaidrot pacientu apmierinātību ar saņemto veselības aprūpes kvalitāti pirms st...

  8. Thermal And Gamma-Radiation Annealing Of The Iridium-192 Recoil Species In Crystalline Na{sub 2}IrCl{sub 6} {center_dot} 6H{sub 2}O; Recuit Thermique et par Rayonnement Gamma de l'espece {sup 192}Ir de Recul dans des Cristaux de Na{sub 2}IrCl{sub 6} * 6H{sub 2}O; 0422 0415 041f 041b 041e 0412 041e 0419 0418 0413 0410 041c 041c 0410 - 041e 0422 0416 0418 0413 041f 0420 041e 0414 0423 041a 0422 041e 0412 041e 0422 0414 0410 0427 0418 0418 0420 0418 0414 0418 042f -192 0412 041a 0420 0418 0421 0422 0410 041b 041b 0418 0427 0415 0421 041a 041e 041c Na{sub 2}IrCl{sub 6} {center_dot} 6H{sub 2}O; Regeneracion Termica y por Irradiacion Gamma de las Especies de Retroceso del Iridio-192 en Na{sub 2}IrCl{sub 6} {center_dot} 6H{sub 2}O Cristalino

    Energy Technology Data Exchange (ETDEWEB)

    Bell, Rita; Herr, W. [Kernforschungsanlage Juelich, Institut fuer Kernchemie der Universitaet Koeln, Cologne, Federal Republic of Germany (Germany)

    1965-04-15

    }){sup 192}lr. Si la plupart de ces composes ont un caractere anionique, deux d'entre eux se comportent comme des cations marques avec {sup 192}Ir. Les auteurs ont analyse le comportement de ces composes sans entraineur a l'egard des agents de reduction et d'oxydation et leur vieillissement en solution. Ils ont etudie separement l'hydrolyse des complexes hexachloro d'iridium, tri-et quadrivalent, qui avaient ete marques avec {sup 36}Cl et {sup 192}Ir. La comparaison entre les deux series de resultats, corroboree par d'autres donnees obtenues au moyen de l'analyse par activation neutronique, permet d'identifier les produits de recul, qui pour la plupart sont des complexes octaedriques d'iridium (III) contenant une plus ou moins grande proportion des coordinats Cl{sup -}, H{sub 2}O et OH{sup -}. Evidemment, l'eau de cristallisation joue un role important dans la formation des especes chimiques de recul. Avec le recuit thermique de ces produits a 120 Degree-Sign C, les auteurs ont observe une diminution rapide des rendements en complexes aquochloro, hydroxychloro et aquohydroxychloro en faveur de la formation de la substance mere, sauf dans le cas du complexe pentachloro. Celui-ci ne diminue qu'apres une augmentation initiale, ce qui montre qu' il fait fonction de produit intermediaire dans le recuit d'autres produits d'accompagnement. Le recuit provoque par les rayonnements gamma presente de nombreuses phases distinctes, avec tendance generale a une transition des especes chimiques moins chlorees a d'autres especes plus chlorees, aboutissant finalement a la formation du complexe hexachloro. Le processus de recuit consiste donc en un retour d es atomes (ou ions) Cl dans la sphere des coordinats et un deplacement simultane de H{sub 2}O et de OH (OH{sup -}). (author) [Spanish] Por electroforesis sobre papel resulta posible separar hasta 13 diferentes compuestos de retroceso formados como consecuencia de la reaccion nuclear {sup 192}Ir(n, {gamma}) {sup 192}Ir aplicada al Na{sub 2

  9. From après-ski to après-tourism: the Alps in transition?

    Directory of Open Access Journals (Sweden)

    Philippe Bourdeau

    2009-12-01

    Full Text Available Winter sports occupy a prominent place in European tourism, not only because of their economic importance in mountainous areas but also due to their major symbolic significance in the "leisure civilisation". Yet the world of winter tourism is full of uncertainties connected with climate change and also with evolutions and structural breaks that call into question the development model on which it is based. This context of profound change gives us the opportunity to question the limits of the industrial model that has governed the development of the Alps for the practice of skiing and to examine alternative future scenarios to "all-out skiing" and even "all-out tourism".Les sports d’hiver occupent une place de premier plan dans le tourisme européen, non seulement du fait de leur poids économique dans les régions de montagne, mais aussi par leur forte dimension symbolique dans la « civilisation des loisirs ». Pourtant l’univers du tourisme hivernal est parcouru par de nombreuses incertitudes liées au changement climatique, mais aussi à des évolutions et des ruptures structurelles qui remettent en question le modèle de développement sur lequel il repose. Ce contexte de mutation permet d’interroger les limites du modèle industriel qui a présidé à l’aménagement des Alpes pour la pratique du ski et d’examiner des figures d’avenir alternatives au « tout ski » et même au « tout tourisme ».

  10. The transition radiation. 2. experimental study of the optical transition radiation; Le rayonnement de transition: 2. etude experimentale du rayonnement de transition optique

    Energy Technology Data Exchange (ETDEWEB)

    Couillaud, Ch.; Haouat, G.; Seguin, S.; Striby, S

    1999-07-01

    Optical-transition-radiation-based diagnostics have been widely used for many years on electron accelerators in order to measure beam energy and transverse and longitudinal emittances. These diagnostics are very attractive for high brightness electron beams used as drivers for radiation sources. Such diagnostics have been performed on the ELSA facility (18 MeV electron energy, 100 A peak current) using both a single interface and an OTR-Wartski interferometer. We present the accelerator, the experimental set-up and the method for analyzing the OTR angular distribution. Then, the experimental results are described and compared with those from the three gradient method. In addition, we present a beam energy measurement using OTR interferogram analysis. (author)

  11. The distribution of a pure beta-emitter in the human body. Problems and preliminary results of Bremsstrahlung measurements in vivo; La repartition d'un emetteur beta pur dans l'organisme humain. Problemes poses par les mesures in vivo du rayonnement de freinage et premiers resultats obtenus; Raspredelenie chistogo beta-izluchatel ya v chelovecheskom organizme Problemy i predvaritel'ny e rezul'taty izmerenij tormoznogo izlucheniya v zhivom organizme; Distribucion de un emisor beta puro en el organisme humano. Problemas planteados por las mediciones in vivo de la radiacion de frenado y resultados preliminares obtenidos

    Energy Technology Data Exchange (ETDEWEB)

    Mehl, H G [Strahleninstitut der Freien Universitaet, Berlin (Germany)

    1959-07-01

    In vivo measurements of the distribution of a pure beta-emitter in the human body were previously limited to the localization of radioactivity in superficial tissues only, owing to the short range of the beta particles in tissue. During die last few years the analysis has been extended by means of bremsstrahlung measurements to activities in deep-lying tissues. The present paper deals with problems and results of this new technique. On the basis of an analysis of the physical nature of this radiation, the construction of suitable detection devices is discussed. The theoretical and experimental work done in this field are reviewed. In order to make a proper interpretation of the results obtained, it is necessary to analyse the various factors involved. These include particularly the area ''seen'' by the detector, the specific activity of the tissue seen and the depth of the organ under consideration, A discussion of the results of such measurements already published will permit an assessment of the present situation and of the nature of the problems still unsolved. (author) [French] Les mesures in vivo de la repartition d'un emetteur beta pur dans l'organisme humain se limitaient autrefois a la localisation de la radioactivite dans les tissus superficiels, en raison du faible parcours des particules beta dans l'organisme. Depuis quelques armees, il est possible, grace aux mesures du rayonnement de freinage, d'etudier egalement la radioactivite dans les tissus profonds. L'auteur examine les problemes poses par cette technique nouvelle et les resultats qu'elle permet d'obtenir. Il indique des procedes de detection fondes sur les caracteristiques physiques de ce rayonnement. Il decrit les recherches theoriques et experimentales qui ont ete faites dans ce domaine. Pour interpreter correctement les resultats obtenus, il importe d'analyser les differents facteurs qui interviennent, notamment la surface par le detecteur, l'activite specifique du tissu observe et

  12. Industrial applications of radiation chemistry; Perspectives industrielles de la chimie sous rayonnement

    Energy Technology Data Exchange (ETDEWEB)

    Puig, Jean Rene [Commissariat a l' energie atomique et aux energies alternatives - CEA, Service de chimie-physique, CEN de Saclay (France)

    1959-07-01

    The status of industrial applications of radiation chemistry as it stands 6 months after the second Geneva international conference is described. The main features of the interaction of ionizing radiations with matter are briefly stated and a review is made of the best studied and the more promising systems of radiation chemistry. The fields of organics, plastics, heterogeneous catalysis are emphasized. Economies of radiation production and utilization are discussed. Reprint of a paper published in Industries atomiques - no. 5-6, 1959.

  13. Spécialiste de programme principal, rayonnement stratégique (h/f ...

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

    évalue le rendement de l'ensemble des bénéficiaires de l'ITT ou d'un groupe prioritaire de bénéficiaires pour ce qui est de l'influence stratégique sur les politiques et de la mobilisation du public; établit les besoins en matière de soutien technique et de formation, évalue les coûts et les priorités et fait des recommandations ...

  14. Calculation codes for radiant heat transfers; Les codes de calcul de rayonnement thermique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This document reports on 12 papers about computerized simulation and modeling of radiant heat transfers and fluid flows in various industrial and domestic situations: space heating, metal industry (furnaces, boilers..), aerospace industry (turbojet engines, combustion chambers) etc.. This workshop was organized by the ``radiation`` section of the French society of thermal engineers. (J.S.)

  15. Risks induced by laser radiation; Risques induits par le rayonnement laser

    Energy Technology Data Exchange (ETDEWEB)

    Courant, D [CEA Fontenay-aux-Roses, 92 (France). Dept. de Radiobiologie et de Radiopathologie

    2001-07-01

    The use of lasers is often dangerous because of the emitted power, the wave length, the conduction system(optical fiber, wave guide, mirrors) and the use conditions. The safety notion involves the precise knowledge of materials, the biological effects in function of laser emission parameters, the knowledge of protection standards, the observance of use rules and the personnel training. This chapter treats the risks induced by the beam. It gives the different biological effects induced by the laser beam, at the eye and skin levels that are at the origin of exposure limits and the lasers classification recommended by the protection standards. (N.C.)

  16. Energies, health, medicine. Low radiation doses; Energies, sante, medecine. Les faibles doses de rayonnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This file concerns the biological radiation effects with a special mention for low radiation doses. The situation of knowledge in this area and the mechanisms of carcinogenesis are detailed, the different directions of researches are given. The radiation doses coming from medical examinations are given and compared with natural radioactivity. It constitutes a state of the situation on ionizing radiations, known effects, levels, natural radioactivity and the case of radon, medicine with diagnosis and radiotherapy. (N.C.)

  17. Study of the radiation in divertor plasmas; Etude du rayonnement dans les plasmas de divertor

    Energy Technology Data Exchange (ETDEWEB)

    Laugier, F

    2000-10-19

    We have studied the cooling of the edge plasma by radiation in the divertor volume, in order to optimize the extraction of power in tokamaks and to limit the wall erosion. In attached divertor plasmas experiments, the concentration of intrinsic impurities at the edge is related to the response of the wall to the incident energy flow of plasma, depending on a phenomenological law. We carried out an analysis of the radiation according to this law and to the control parameters of the discharges. The largest radiated fraction and best synergy are obtained when the concentration of intrinsic impurities strongly increases with the energy of incident plasma. On the other hand, the erosion of the wall is stronger. In detached plasmas, we proved that the performances in terms of incident plasma energy loss and pressure loss are optimal when the density of the slowest neutrals is strong at the edge and when their radial penetration is small. On Tore Supra, we highlighted the correlations between the maximum Mach number of incident plasma flow, the radiation front and the penetration of the neutrals. A simple diagnostic based on the localization of the maximum Mach number proves that detached mode is not optimal on Tore Supra, because the radial penetration of the slowest neutrals is not sufficiently small. In the last part, we obtained the three-dimensional topology of the radiation in the ergodic divertor using a spectral analysis code and boundary conditions consistent with the temperature distribution on the wall. The radiation is maximum in front of the divertor modules. As a consequence, radiated power is underestimated by standards measurements of Tore Supra that are located between the modules. We finally showed that the profiles of temperature along the field lines are modulated, this is specific to the ergodic divertor. (author)

  18. Snow measurement by cosmic radiation; Mesure de la neige par rayonnement cosmique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-02-01

    The knowledge of the water content equivalence of the snow cover is an important element for the improvement of the water resource management. It allows in particular to evaluate and foresee the filling up supplies of big seasonal reservoirs. Electricite de France (EdF), in collaboration with the national center of scientific research (CNRS) and Meteo France, has developed a new generation of sensors, the cosmic radiation snow gauge, allowing the automatic monitoring of the status of snow stocks by the measurement of the water value of the snow cover. (J.S.)

  19. Radiation hazards in the neighbourhood of uranium reactors; Dangers des rayonnements aupres des piles a uranium

    Energy Technology Data Exchange (ETDEWEB)

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

    1956-07-01

    Radiation hazards near uranium reactors may be divided in two groups. Hazards when the reactor is normally operating: {gamma} radiation from hot uranium or air contamination by fission gases, {gamma} radiation or contamination by the coolant (air, nitrogen, heavy-water), {gamma} radiation from radioisotopes. Hazards in the case of an accident: presence of hot uranium in the atmosphere, soil contamination. (author) [French] Les dangers d'irradiation aupres des piles a uranium sont a classer essentiellement en deux groupes. Les dangers existant aupres d'une pile exploitee normalement: irradiation {gamma} par l'uranium irradie ou contamination de l'air par des gaz de fission, irradiation {gamma} ou contamination par les fluides de refroidissement (air, azote, eau lourde), irradiation {gamma} par les radioelements fabriques. Les dangers en cas d'accident survenant a un reacteur en fonctionnement, ayant pour consequence : la presence dans l'air d'uranium irradie, la contamination du sol. (auteur)

  20. Calculation codes for radiant heat transfers; Les codes de calcul de rayonnement thermique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This document reports on 12 papers about computerized simulation and modeling of radiant heat transfers and fluid flows in various industrial and domestic situations: space heating, metal industry (furnaces, boilers..), aerospace industry (turbojet engines, combustion chambers) etc.. This workshop was organized by the ``radiation`` section of the French society of thermal engineers. (J.S.)

  1. The X-ray transition radiation; Le rayonnement de transition X

    Energy Technology Data Exchange (ETDEWEB)

    Couillaud, Ch

    2000-07-01

    The interest of producing high-energy radiation using a small-size electron accelerator is growing since many years. It appeared that such accelerators should drive x-ray sources to produce a high flux of radiation. The range of photon-energy available when using electron linacs, for example, is between a few tens of eV and the maximum electron kinetic energy. The transition radiation, which is produced when a charged particle crosses the interface between two media of different permittivities, is a very promising way due to its high production rate. We present here a study of this physical process involving moderate-energy relativistic electrons (20 MeV). We recall the main characteristics of the radiation when the interface is crossed at normal incidence and derive the analytical production yields when the interaction takes place at grazing incidence. The results for both geometries are compared. Finally, the scale laws allowing the optimization of the spectral source brilliance are presented. (author)

  2. Un think tank ouest-africain accroît son rayonnement et renforce ses ...

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

    28 avr. 2016 ... La criminalité et la pauvreté au Ghana urbain. La manière dont la criminalité et la pauvreté interagissent a été étudiée et débattue dans la littérature de recherche occidentale, mais on sait pe. Voir davantageLa criminalité et la pauvreté au Ghana urbain · Ce que nous faisons · Financement · Ressources ...

  3. Effets de rayonnement sur les detecteurs au silicium a pixels du detecteur ATLAS

    CERN Document Server

    Lebel, Celine

    2007-01-01

    Two detection systems are using pixel silicon detectors in the ATLAS detector: the Pixel, which is the subdetector closest to the interaction point, and the MPX network. The activation of the materials present in the Pixel produced by radiation has been measured in two experiments which we performed at CERF (CERN) and NPI-ASCR (Czech Republic). These experimental studies of activation are com- pared with GEANT4 simulations. The results of these comparisons show that the simulation can predict the activities with a precision of an order of magnitude. They also show that GEANT4 fails to produce certain radioisotopes seen in the experimental activation studies. The contribution to background and the resid- ual doses due to the desintegration of the radioisotopes produced by fast neutrons (category in which falls the expected average neutron energy of 1 MeV in ATLAS) are extrapolated to ATLAS conditions. It is found that this background in the AT- LAS Pixel subdetector will be negligible and that the doses are we...

  4. About particular use of ionizing radiations; Des usages particuliers des rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-02-01

    Different uses of ionizing radiations are reviewed: tracers techniques, nuclear gauges, dating by carbon 14, silica doping, use of gamma irradiation for the density measurement in civil engineering, use of a electron capture detector to study by gas chromatography chlorinated contaminants in environment, neutron activation as environmental gauge, analysis of lead in paint and pollutants in ground and dusts, help for work of art valuation by x spectrometry. (N.C.)

  5. Cosmic rays and radiations from the cosmos; Rayons cosmiques et rayonnement du cosmos

    Energy Technology Data Exchange (ETDEWEB)

    Parizot, E

    2005-12-01

    This document gathers a lot of recent information concerning cosmic radiations, it is divided into 4 parts. Part I: energy, mass and angular spectra of cosmic rays. Part II: general phenomenology of cosmic rays, this part deals with the standard model, the maximal energy of protons inside supernova remnants, nucleosynthesis of light elements, and super-bubbles. Part III: radiations from the cosmos, this part deals with high energy gamma rays, non-thermal radiation of super-bubbles, positron transport, and the Compton trail of gamma-ray bursts. Part IV: the Pierre Auger observatory (OPA), this part deals with the detection of gamma ray bursts at OPA, the measurement of anisotropy, and top-down models. (A.C.)

  6. What is cosmic radiation?; Qu'est ce-que le rayonnement cosmique?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The earth was indeed receiving ionizing radiations from the heavens. This cosmic radiation consists of particles travelling near the speed of light. It consists of two components, the first of which is permanent and of galactic origin, while the other is more sporadic, depending on the sun's activities. Natural land-based sources expose each of us to an average total dose of 2.4 mSv per year (source UNSCEAR). In addition, the human activities using ionizing radiation contribute to an average annual exposure of 1.4 mSv, originating primarily with medical activities ( radiodiagnostic and radiation therapy). Members of flights crew are subject to exposure. The total dose of cosmic radiation received is is directly proportional with the duration of exposure, and thus with the duration of the flight. Measurement taken on board aircraft during the 1990's showed that flight personnel (on long haul flights) receive an average dose of approximately the same magnitude as the one due to exposure to natural radioactivity in France. The damage caused by ionizing radiation depends on the quantity of energy released by radiation into the cells of each organ or tissue of the human body(exposure dose). For a given quantity of absorbed energy (dose expressed in Gray), the damage will vary according to the nature of the radiation and the affected organ. These effects are of two types: acute effects and deferred effects. Two measurements are essential for radiation protection: the measurements of the dose of radiation absorbed by the body and the assessment of the risk associated with the absorbed dose. Two units were thus created: the gray and the sievert. (N.C.)

  7. The radiation effects on the living cell; Les effets des rayonnements sur la cellule vivante

    Energy Technology Data Exchange (ETDEWEB)

    Sage, E; Dutrillaux, B; Soussi, Th [Institut Curie, 75 - Paris (France); [Centre National de la Recherche Scientifique (CNRS), 75 - Paris (France); Boiteux, S; Lopez, B [CEA-CNRS/Fontenay-aux-Roses, 92 (France); Feunteun, J [Institut Gustave Roussy, 94 - Villejuif (France)

    1999-06-01

    This publication is a presentation of particular points discussed during the colloquium of the 15-18 june 1999, for which scientific researches are performed at the CEA/CNRS. They deal with the radiobiology, for the radiation effects on living matter; with the DNA, for the knowledge and repair mechanisms on cells submitted to ionizing radiations; with the exposition to UV in correlation with neoplasms; with the P53 gene which is a tumour suppressor. (A.L.B.)

  8. Effects of low doses of ionizing radiation; Effets des faibles doses de rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

    Masse, R. [Office de Protection contre les Rayonnements Ionisants, 78 - le Vesinet (France)

    2006-07-01

    Several groups of human have been irradiated by accidental or medical exposure, if no gene defect has been associated to these exposures, some radioinduced cancers interesting several organs are observed among persons exposed over 100 to 200 mSv delivered at high dose rate. Numerous steps are now identified between the initial energy deposit in tissue and the aberrations of cell that lead to tumors but the sequence of events and the specific character of some of them are the subject of controversy. The stake of this controversy is the risk assessment. From the hypothesis called linear relationship without threshold is developed an approach that leads to predict cancers at any tiny dose without real scientific foundation. The nature and the intensity of biological effects depend on the quantity of energy absorbed in tissue and the modality of its distribution in space and time. The probability to reach a target (a gene) associated to the cancerating of tissue is directly proportional to the dose without any other threshold than the quantity of energy necessary to the effect, its probability of effect can be a more complex function and depends on the quality of the damage produced as well as the ability of the cell to repair the damage. These two parameters are influenced by the concentration of initial injuries in the target so by the quality of radiation and by the dose rate. The mechanisms of defence explain the low efficiency of radiation as carcinogen and then the linearity of effects in the area of low doses is certainly the least defensible scientific hypothesis for the prediction of the risks. (N.C.)

  9. Blue light hazards for ocular lesions; Risques oculaires du rayonnement bleu

    Energy Technology Data Exchange (ETDEWEB)

    Cesarini, J.P. [INSERM, Fondation Ophtalmologique A. de Rothschild, 75 - Paris (France); CES, Agents physique, AFSSET (France)

    2009-10-15

    The blue light range (400-500 nm) of visible radiation stimulates specifically cones and rods of the retina. The carried energy by these wavelengths is absorbed and transferred to specific pigments. Their energy is sufficient to produce free radicals and singlet form of oxygen. Intense sources, rich in blue light radiation, may induce, in the retina, photo-toxic lesions either limited or short-lived or photothermal lesions more or less definitive. Repeated photo-toxic lesions should be the root for the age-related maculo-pathy (A.R.M.) also called late macular degeneration (A.M.D.). As a consequence, the attention should be drawn on the potential risk linked to modern lighting as 'daylight' lamp, compact fluorescent lamps, energy saving (C.F.L.) and light-emitting diodes (L.E.D.) for which a specific vigilance should be enforced. (author)

  10. Construction of an apparatus for measuring the low-temperature thermal conductivity before and after neutron irradiation. Application to uranium dioxide (1963); Realisation d'un appareil pour la mesure de la conductibilite thermique a basse temperature avant et apres irradiation neutronique. Application au dioxyde d'uranium (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Bethoux, O [Commisariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1963-09-15

    An apparatus has been studied and built which makes it possible to alternatively irradiate a sample at room temperature in the reactor 'Melusine' at the Grenoble Nuclear Research Centre, and to measure its thermal conductivity between 20 and 100 deg. K in perfect safety. The results obtained on UO{sub 2} have made it possible on the one hand to check experimentally that the spin-phonon diffusion leads to a thermal resistance independent of temperature above 30 deg. K, and on the other hand to propose a simple theory which takes into count the role played by the damage due to U-235 fission products in the decrease of thermal conductivity after irradiation. (author) [French] Un appareil permettant alternativement d'irradier un echantillon a temperature ambiante dans le reacteur ''Melusine'' du C.E.N.G., et de mesurer sa conductibilite thermique entre 20 et 100 deg. K en toute securite, a ete etudie et construit Les resultats obtenus sur UO{sub 2} ont permis, d'une part, de verifier experimentalement que la diffusion spin-phonon conduit a une resistance thermique independante de la temperature au-dessus de 30 deg. K, et, d'autre part, de proposer une theorie simple tenant compte du role joue par les degats dus aux produits de fission de l'uranium 235, dans la deterioration de la conductibilite thermique apres irradiation. (auteur)

  11. Les réseaux sociaux et l’échange entre l’homme politique et les internautes : le cas de Facebook après les élections présidentielles en France Social Networks and the Exchange Between Politicians and Surfers: Facebook and the presidential post elections in France

    Directory of Open Access Journals (Sweden)

    Galia Yanoshevsky

    2010-10-01

    Full Text Available A travers l’analyse des interactions entre hommes politiques et internautes sur Facebook après les élections présidentielles de 2007 en France, cet article vise à montrer comment les réseaux sociaux sont exploités par les deux parties. Au départ un réseau décentralisé qui lie les gens sans intervention politico-hiérarchique, Facebook est mobilisé par les hommes politiques au service de leur besoins. Quelles en sont les conséquences pour la sphère publique : s’agit-il d’un outil qui permet à l’internaute de déjouer les usages de marketing politique qu’en fait l’homme politique ?The purpose of this article is to show how social networks, and more specifically Facebook, are used by politicians and their supporters. This is achieved through a detailed analysis of exchange of posts between politicians and surfers in the period following the presidential election campaigns in France of 2007. It is shown how politicians take advantage of Facebook, despite its initially being a decentralized social network, connecting people without a political or hierarchic purpose. The article attempts to show some of the consequences of such an exploitation of a public network for the public sphere and asks how much leverage there is for the surfers/citizens in moderating political marketing on Facebook.

  12. Nuclear power reactors in the world. Apr 1991 ed.

    International Nuclear Information System (INIS)

    1991-01-01

    This is the eleventh edition of Reference Data Series No. 2, Nuclear Power Reactors in the World, which is published once per year, to present the most recent reactor data available to the Agency. It contains the following summarized information: General information as of the end of 1990, on power reactors operating or under construction, and shut down; performance data on reactors operating in the Agency's Member States, as reported to the IAEA. This information is collected by the Agency by circulating questionnaires to the Member States through the designated national correspondents. The replies are used to maintain computerized files on general and design data of, and operating experience with, power reactors. The Agency's Power Reactor Information System (PRIS) comprising the above files provides all the information and data previously published in the Agency's Power Reactors in Member States and currently published in the Agency's Operating Experience with Nuclear Power Stations in Member States. 5 figs, 19 tabs

  13. RES COVER APR QQ April 4th Final

    Indian Academy of Sciences (India)

    ART

    As we grew older, we became conscious of his work, his struggles and achievements. We came to know of his ... five books during his long teaching career. AKR gained legendary ... portable typewriter every night till late hours. He was keenly ...

  14. RES COVER APR QQ April 4th Final

    Indian Academy of Sciences (India)

    ART

    In a real world, it is impossible to get a crystal completely devoid of defects ... Anisotropic magnetoresistance. (AMR) originates from anisopropic spin-orbit interaction and causes the resistance to depend on the relative orientation of electric current ... possible due to the development in thin film deposition tech- niques such ...

  15. 457.pdf | apr2014 | jess | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    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. Ethical Guidelines and Procedures document. Posted on 17 January 2017. A revised version of the document 'Scientific Values: Ethical Guidelines ...

  16. Nuclear power reactors in the world. Apr 1985 ed.

    International Nuclear Information System (INIS)

    1985-01-01

    This is the fifth edition of Reference Data Series No. 2, Nuclear Power Reactors in the World, which replaces the Agency's publication Power Reactors in Member States. This bulletin contains the following summarized information on nuclear power reactors in the world: General information as of the end of 1984 on reactors operating or under construction and such additional information on planned and shutdown reactors as is available; Performance data on major reactor types operating in the Agency's Member States. The information is collected by the Agency by circulating questionnaires to the Member States through the designated national correspondents. The replies are used to maintain computerized files on general and design data of and operating experience with reactors

  17. Two years after the storms; 2 ans apres les tempetes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-12-01

    This document takes stock on the power distribution repair, two years after the storms of december 1999 in France. It also presents the new organization (FIRE) developed to face such natural or accidental disasters. (A.L.B.)

  18. Expo. O2 un an apres, entre oubli et nostalgie

    CERN Multimedia

    Bourget, A

    2003-01-01

    "La manifestation s'etait ouverte, il y a tout juste douze mois, sur fond de scepticisme et de critiques. Dix millions d'entrees plus tard, il en reste des souvenirs de fete, quelques images marquantes, comme celle du Monolithe, et un sentiment d'identite eclatee" (2 pages).

  19. RES COVER APR QQ April 4th Final

    Indian Academy of Sciences (India)

    ART

    exhausted. This results in the exponential increase in the copies of the template DNA (Figure 1). In traditional PCR, the product is analyzed only at the end of the reaction. .... their quality of life due to early detection. Suggested Reading. [1].

  20. Chernobyl, 13 years after; Tchernobyl, 13 ans apres

    Energy Technology Data Exchange (ETDEWEB)

    Regniault-Lacharme, Mireille; Metivier, Henri [Inst. de Protection et de Surete Nucleaire, CEA Centre d' Etudes de Fontenay-aux-Roses, 92 (France)

    1999-04-01

    This is an annual report, regularly issued by IPSN, that presents the ecological and health consequences of the Chernobyl Nuclear Accident. The present status of the Chernobyl Nuclear Plant, which Ukraine engaged to stop definitively in year 2000, is summarized. The only reactor unit now in operation is Chernobylsk-3 Reactor which poses two safety questions: evolution of cracks in part of the tubing and behaviour of the pressure tubes. Although, some improvements in the RBMK reactor types were introduced, problems remain that make IPSN to stress the requirement of stopping this NPP completely. In the contaminated territories surrounding Chernobyl incidence rate of infant thyroid cancers continues to grow, reaching values 10 to 100 times higher than the natural rate. In France the IPSN analyzed 60,000 records carried out in 17 sites during May 1986 and April 1989. It was estimated that the individual dose received during 60 years (1986-2046) by the inhabitants of the most affected zone (eastern France) is lower than 1.5 mSv, a value lower than 1% of the natural cosmic and telluric radioactivity exposure for the same period. For the persons assumed to live in the most attacked forests (from eastern France) and nourishing daily with venison and mushrooms the highest estimate is 1 mSv a year. Concerning the 'hot spots', identified in mountains by IPSN and CRIIRAD, the doses received by excursionists are around 0.015 mSv. For an average inhabitant of the country the dose piled up in the thyroid due to iodine-131 fallout is estimated to 0.5-2 mSv for an adult and 6.5-16 mSv for an infant. These doses are 100 to 1000 times lower than the ones to which the infants living in the neighbourhood of Chernobyl are exposed to. The contents of the report is displayed in the following six chapters: 1. Chernobyl in some figures; 2. The 'sarcophagus' and the reactors of the Chernobyl NPP; 3. Health consequences of the Chernobyl accident;. 4. The impact of Chernobyl fallout in France; 5. Chernobyl's environment and the management of contaminated territories.; 6. The French-German initiative for Chernobyl.

  1. Chernobyl, 14 years later; Tchernobyl, 14 ans apres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This report draws an account of the consequences of Chernobyl accident 14 years after the disaster. It is made up of 8 chapters whose titles are: (1) Some figures about Chernobyl accident, (2) Chernobyl nuclear power plant, (3)Sanitary consequences of Chernobyl accident, (4) The management of contaminated lands, (5) The impact in France of Chernobyl fallout, (6) International cooperation, (7) More information about Chernobyl and (8) Glossary.

  2. After Imagining/ Après l'imaginer: Imaginations

    Directory of Open Access Journals (Sweden)

    Managing Editors

    2010-12-01

    Full Text Available We welcome you to Imaginations: Journal of Cross-Cultural Image Studies / Revue d’études interculturelles de l’image, an open-access online peer-reviewed journal born out of research and developments in cross-cultural and intersecting epistemological fields that have at their root a determined focus on the role and power of the image in contemporary culture and in cultural communications. Nous vous souhaitons la bienvenue à Imaginations: Journal of Cross-Cultural Image Studies / Revue d’études interculturelles de l’image, un journal en ligne à accès libre dont les contributions sont préalablement soumises à un comité de révision par les pairs. Cette publication est le fruit d’un vif intérêt pour la recherche et la pratique au croisement de multiples champs épistémologiques et interculturels autour du rôle et de la puissance de l’image dans la société et les média contemporains.

  3. To rehabilitate life after Tchernobyl..; Rehabiliter la vie apres Tchernobyl..

    Energy Technology Data Exchange (ETDEWEB)

    Paillard, B.; Pena-Vega, A. [Centre d' Etudes Transdisciplinaires, Sociologie, Anthropologie, Histoire, EHESS, 75 - Paris (France)

    2003-09-01

    This article is a survey of the difficult daily life of the people living in a small town 70 km away from Chernobyl. The local authorities have to cope with first, the global aging of the population due to the massive departure of young families in 1991 when the first cases of thyroid cancers broke out and secondly, the arrival of very poor people that settled in the abandoned accommodations. The preventive measures taken to limit the internal contamination of the inhabitants are difficult to implement and maintain because of the invisibility of radioactivity, the flourishing surrounding nature, time passing and the lack of danger awareness of the new inhabitants. The poor standard of population health is due to aging (cancers and cardiovascular diseases), to the impact of radioactive contamination (thyroid cancer among the young) but is aggravated by the very low standard of living (tuberculosis is spreading). The local economy collapsed when 50% of the land were banned from any farming activity because of the radioactive contamination, another important resource was the forest but today a large part of wood is unfit for being sold or used as firewood. On the other hand the management of contaminated areas has driven up the production costs. (A.C.)

  4. Interface of RETRAN/MASTER Code System for APR1400

    International Nuclear Information System (INIS)

    Ku, Keuk Jong; Kang, Sang Hee; Kim, Han Gon

    2008-01-01

    MASTER(Multi-purpose Analyzer for Static and Transient Effects of Reactors), which was developed by KAERI, is a nuclear analysis and design code which can simulate the pressurized water reactor core or boiling water reactor core in 3-dimensional geometry. RETRAN is a best-estimate code for transient analysis of Non-LOCA. RETRAN code generates neutron number density in core using point kinetics model which includes feedback reactivities and converts the neutron number density into reactor power. It is conventional that RETRAN code for power generation is roughly to extrapolate feedback reactivities which are provided by MASTER code only one time before transient analysis. The purpose of this paper is to interface RETRAN code with MASTER code by real-time processing and to supply adequate feedback reactivities to RETRAN code. So, we develop interface code called MATRAN for real-time feedback reactivity processing. And for the application of MATRAN code, we compare the results of real-time MATRAN code with those of conventional RETRAN/MASTER code

  5. Chernobyl, fifteen years after; Tchernobyl, 15 ans apres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-04-01

    This work has been constituted around four questions: the future of the Chernobyl site, the damaged reactor, and the sarcophagus around it; the health consequences of the accident on the persons that have worked on the damaged reactor and on the population in the countries the most exposed to fallout,; the situation of contaminated territories around the power plant and their management today; the last question concerns especially the France with the consequences of the radioactive cloud and what we know about the health risks induced by this event. (N.C.)

  6. 15 CFR 740.16 - Additional permissive reexports (APR).

    Science.gov (United States)

    2010-01-01

    ... commodities being reexported are not controlled for NP, CB, MT, SI or CC reasons and are not military... described in ECCN 6A003.b.4.b and “military commodities” described in ECCN 0A919 may not be exported under....-origin components may be accompanied by U.S.-origin controlled spare parts, provided that they do not...

  7. Apres nous, le déluge / Toomas Hendrik Ilves

    Index Scriptorium Estoniae

    Ilves, Toomas Hendrik, 1953-

    2005-01-01

    Autor mõtiskleb Euroopa Parlamendi liikmena selle üle, mida Euroopa viimase kuu sündmused tähendavad ja endaga kaasa toovad. Põhiseadusliku leppe läbikukkumine, vanade liikmesriikide suhtumine uutesse, Venemaa mõju väikestele Ida-Euroopa riikidele, soovitused Eestile edasiseks käitumiseks

  8. 1078.pdf | apr252007 | currsci | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    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 Technology Summer ...

  9. articles27.htm | apr25 | currsci | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    2018-03-13

    Lists of selected candidates. Interaction Meeting on Women In Science. Posted on 12 March 2018. Meeting will be on March 13, 2018 in Multimedia Room, Physics Department, IISc. 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 in Infosys, ...

  10. tutorial2.pdf | apr102000 | currsci | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    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. Theory Of Evolution. Posted on 23 January 2018. Joint Statement by the Three Science Academies of India on the teaching of the theory of evolution

  11. What nuclear industry after Fukushima?; Quel nucleaire apres Fukushima?

    Energy Technology Data Exchange (ETDEWEB)

    Barre, Bertrand [Institut national des sciences et techniques nucleaires, CEA-Saclay, 91191 Gif-sur-Yvette Cedex (France)

    2011-07-01

    Nuclear power experienced a fast growth during the 70's and 80's, but a quasi-stagnation during the 90's. Since the beginning of the 21. century, a so-called renaissance could be witnessed, fuelled by concerns about energy security of supply, volatility of oil and gas prices, fear of an incoming 'peak oil', and, last but not least, the threat of global climate change due to the anthropogenic emissions of greenhouse effect gases. Then, on March 11 2011, a monster earthquake followed by a violent tsunami triggered an accident which all but destroyed four nuclear reactors on the Fukushima-Daiichi site, on the east coast of Honshu, the main Japanese island. There was meltdown in three reactor cores, hydrogen explosions which blew off the upper structures of four reactor buildings, and massive radioactive contamination of a spread of land north-west of the site as well as radioactive releases to the ocean. This accident triggered reactions of various intensities throughout the world, awakening the fears, and questions raised 25 years before by the Chernobyl accident. But the tsunami did not make the fundamentals of the renaissance disappear. After a pause, to fully learn lessons from the accident, the renaissance is likely to start again, all the much since the 'third generation' nuclear plants would have survived unscathed the Fukushima earthquake and tsunami. (author)

  12. RES COVER APR QQ April 4th Final

    Indian Academy of Sciences (India)

    ART

    Problem1: Suppose n birds land randomly on a wire connecting two columns, where n ≥ 2. Each bird is watching its nearest neighbour. What is the expected number of unwatched birds? Solution to How Many Birds are Unwatched. 1 Soubhik Chakraborty, Reso- nance, Vol. 13, No.1, p.88,. January 2008. Let the length of ...

  13. 613.pdf | apr2015 | jess | Indian Academy of Sciences

    Indian Academy of Sciences (India)

    Recent Refresher Courses. Experimental Physics, C.S. Sundar, 20 June 2017 to 05 July 2017 G.B.P.U.A.& T., Pantnagar MORE · Recent Lecture workshops. Recent advances in chemical sciences, 13–15 June 2017, St. Thomas College, Pala MORE ...

  14. Structural Analysis of Advanced Refueling Machine of APR1400

    International Nuclear Information System (INIS)

    Cho, J. R.; Kim, Y. H.; Park, B. T.; Park, J. B.; Jung, J. H.

    2007-01-01

    The Refueling Machine (RM) consists of two structural parts of bridge and trolley. The bridge structure is approximately 8.5 m long and 5 m wide and is primarily composed of two deep wide flange sections spanning the rector area at the operating level. The trolley is mounted on wheels that roll on the rails of the bridge. Vertical movements of trolley and bridge are restricted by guide rollers. In this paper, dynamic and structural analyses based on the earthquake spectrum are carried out to verify the structural integrity of advanced refueling machine. It is done by 3-dimensional finite element analysis using ANSYS software

  15. Chernobyl, 16 years later; Tchernobyl, 16 ans apres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-04-01

    This document on the Chernobyl site evolution is constituted around four main questions. What about the future of the Chernobyl site, the damaged reactor and the ''sarcophagus'' constructed around the reactor? What about the sanitary consequences of the accident on the liquidators asked to blot out the radiation and the around people exposed to radiation? What about the contaminated land around the power plant and their management? Concerning the France, what were the ''radioactive cloud'' sanitary consequences? (A.L.B.)

  16. Optical Density Control of Autoradiographs After Photographic Processing (Preliminary Results); Controle de la Densite Optique des Autoradiogrammes Apres Developpement Photographique. (Resultats Preliminaires); Regulirovanie opticheskoj plotnosti avtoradiogramm posle fotoobrabotki; Control de la Densidad Optica de las Autorradiografias Despues del Tratamiento Fotografico. (Resultados Preliminares)

    Energy Technology Data Exchange (ETDEWEB)

    Baptista, A. M. [Comissao de Estudos de Energia Nuclear, Instituto de Alta Cultura, Lisbon (Portugal); Terrinha, A. [Instituto Portugues de Oncologia, Lisbon (Portugal)

    1965-10-15

    In many applications of photographic emulsions it would be desirable to control the optical density after the photographic processing. This would be useful for instance in certain problems of photographic dosimetry and particularly in many applications of autoradiography in medicine and biology. It would then be possible to recover information lost by overexposure as it frequently occurs unavoidably particularly in cases where important grain density variations are observed in the same autoradiograph specimen. The authors report the first results of an attempt to control the grain density after development and fixation of the photographic material by attacking the processed emulsion with diluted solutions of trypsin. By changing concentrations and temperature the attack can be made to proceed at any desirable speed so the trypsin solution acts like an ultra microtome removing very thin layers of the photographic emulsion. More important, the process could be followed continuously under the microscope by using a suitable chamber. Results are presented which suggest that this technique can give a rough idea of the incorporation with time of the radionuclide in the biological structure under observation. (author) [French] Dans diverses applications d'emulsions photographiques, il serait souhaitable de controler la densite optique apres avoir procede au developpement. Cette methode serait utile, par exemple pour resoudre certains problemes de dosimetrie photographique, et notamment dans maintes applications medicales et biologiques de l'autoradiographie. Il serait alors possible de recuperer les indications perdues en raison d'une surexposition, souvent inevitable, surtout dans les cas ou la densite du grain varie tres sensiblement dans un meme specimen autoradiographique. Les auteurs signalent les premiers resultats qu'ils ont pu obtenir en cherchant a controler la densite du grain, apres developpement et fixation de la substance photographique, en attaquant l

  17. Pulse-form discrimination in organic scintillation crystals; Discrimination d'apres la forme de l'impulsion dans les cristaux organiques de scintillation; Diskriminatsiya formy impul'sov v organicheskikh stsintillyatsionnykh kristallakh; Discriminacion de la forma de los impulsos en los cristales de compuestos organicos para contadores de centelleo

    Energy Technology Data Exchange (ETDEWEB)

    De Vries, L J; Udo, F [Instituut voor Kernphysisch Onderzoek, Amsterdam (Netherlands)

    1962-04-15

    Presented is a proton-electron discrimination circuit, based on the pulse-form differences between proton and electron-induced scintillation light pulses in stilbene. The circuit is stable and resolves proton from electron pulses down to a proton energy of 300 keV. The discrimination circuit, which contains only linear elements, is sensitive to pile-up-induced errors for only 0.1 {mu}s after the arrival of a pulse. The described circuit has now been used in a 1-30 MeV neutron spectrometer based on proton-recoil between two silbene crystals. A resolution of 10% at 14 MeV neutron energy was obtained with a detection efficiency of 1.3 x 10{sup -4}. A neutron monitor, also based on linear pulse-form discrimination, could be used to measure a neutron dose of 10% of the maximum permissible dose in the presence of a gamma flux of 4 times the maximum permissible dose. (author) [French] Le memoire decrit un circuit de discrimination proton/electron dont le principe repose sur les differences de forme entre les impulsions lumineuses dans du stilbene, produites par des protons, d'une part, et des electrons, d'autre part. Le circuit est stable et permet de separer les impulsions protoniques des impulsions electroniques, a partir d'une energie protonique de 300 keV. Ce circuit, qui ne contient que des elements lineaires, n'est sujet a des erreurs dues a l'accumulation que pendant 0,1 {mu}s apres l'arrivee de l'impulsion. Il a ete utilise dans un spectrometre neutronique de 1-30 MeV, fonde sur le recul des protons entre deux cristaux de stilbene. On a obtenu une resolution de 10% pour une energie neutronique de 14 MeV, avec une efficacite de detection de 1,3x10{sup -4}. Un detecteur de neutrons procedant egalement par discrimination d'apres la forme des impulsions, pourrait servir a mesurer une dose de neutrons representant 10% de la dose maximum admissible, en presence d'un flux gamma correspondant a une dose quatre fois superieure a la dose maximum admissible. (author

  18. 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

  19. Étude qualitative sur les perceptions à propos de la capacité des organisations à promouvoir l’activité physique au Canada et à propos de l’influence de ParticipACTION cinq ans après sa relance

    Directory of Open Access Journals (Sweden)

    Subha Ramanathan

    2018-01-01

    Full Text Available Introduction. ParticipACTION est un organisme canadien de communication et de marketing social faisant la promotion de l’activité physique qui a été relancé en 2007. Notre étude visait à évaluer de manière qualitative le pouvoir d’action des organisations canadiennes en matière de promotion de l’activité physique ainsi que l’influence de ParticipACTION sur ce pouvoir cinq ans après sa relance. Méthodologie. Des entrevues téléphoniques semi-structurées ont été réalisées auprès de 44 informateurs clés sélectionnés par échantillonnage dirigé. Les informateurs étaient représentatifs d’organismes nationaux, provinciaux et locaux ayant un mandat en matière de promotion de l’activité physique. Les données tirées des entrevues ont été analysées par thèmes. Résultats. Depuis la relance de ParticipACTION, le pouvoir d’action en matière de partenariats et de collaborations ainsi que le climat général dans le domaine de la promotion de l’activité physique se sont améliorés. Bien que diverses contraintes financières aient réduit la capacité des organisations à remplir leur mandat, leur impact a été atténué par des facteurs internes comme la présence d’employés compétents et les partenariats ainsi que par des facteurs externes comme les progrès technologiques dans les communications et les échanges d’information. Les avis étaient mitigés en ce qui concerne la contribution de ParticipACTION à l’amélioration de ce pouvoir d’action. Bien que ParticipACTION ait attiré l’attention sur l’inactivité, sa contribution a surtout été perçue comme complémentaire aux activités déjà en place. Certains organismes ont considéré que la relance de ParticipACTION avait accru la compétition pour le financement et l’accès aux médias populaires, tandis que d’autres étaient d’avis qu’il s’agissait d’une opportunité d’établir des partenariats officiels pour des

  20. Aspects architecturaux de la transformation de Hà Nội après le Đổi mới (1986 : contradictions, phantasmes, espoirs Architectural Aspects of Hà Nội’s Transformation after Đổi mới (1986: Contradictions, Fantasies, Hopes

    Directory of Open Access Journals (Sweden)

    Heinz Schütte

    2009-06-01

    Full Text Available Depuis le Đổi mới, c’est-à-dire depuis la progressive libéralisation de l’économie vietnamienne, Hà Nội a connu de profondes mutations. Après des décennies de guerres et l’échec de la mise en place d’un système économique socialiste, des changements radicaux se sont opérés dans le paysage urbain de Hà Nội. Ces modifications sont visibles dans le bâti urbain pour tout visiteur de la ville. Cet article tente de montrer que, contrairement aux apparences, ce processus de transformation n’est ni aléatoire ni chaotique, mais qu’il suit une logique historique et culturelle, et qu’il ne peut être réduit à un phénomène de globalisation. Les riches villas du Lac de l’Ouest sont représentatives des valeurs d’une nouvelle classe sociale qui a émergé suite au Đổi mới. Les mutations architecturales de la ville reflètent les changements sociaux : la ville tend à devenir un lieu de consommation alors que les riches villas se bâtissent à sa périphérie, bouleversant ainsi l’organisation de l’espace traditionnel.Ever since Đổi mới, the arrival of capitalist market forms, and the evolution of corresponding social relations, Hà Nội has undergone a dramatic upheaval. After revolutions, wars and the failure of centralized economy, we are currently witnessing a radical change from pre-modernity to the modernity of a globalized age. The consequences are perceptible when strolling through Hà Nội’s streets and talking to the capital’s inhabitants. This article attempts to demonstrate that the process of transformation is not as random or chaotic, as it may seem, but that it follows a logic that can be historically categorized. The posh new villas on West Lake and their upwardly mobile owners represent new, syncretic values; the origins of family businesses are carefully hidden; the individual activities in the 36 guild streets of the Old Quarter; these are all testaments to change that

  1. Study of optically stimulated luminescence (OSL) for radiation detection. Application to an optical fibre {gamma}-radiation sensor; Etude de la luminescence stimulee optiquement (OSL) pour la detection de rayonnements: application a un capteur a fibre optique de rayonnement {gamma}

    Energy Technology Data Exchange (ETDEWEB)

    Roy, O. [CEA Saclay, 91 - Gif-sur-Yvette (France). Dept. d`Electronique et d`Instrumentation Nucleaire]|[Paris-7 Univ., 75 (France)

    1998-12-31

    This work shows up the usefulness of the Optically Stimulated Luminescence (OSL) to resolve radioprotection problems. We study the use of OSL as a gamma dosimetric technique with respect to the ALARA`s concept (As Low As Reasonably Achievable). A new approach based on optical fibers and luminescent materials showing OSL properties (closely related to Thermoluminescence phenomena) is presented in order to improve the remote real time dosimetry monitoring. Like thermoluminescent materials (TLD), OSL materials can trap charges under an irradiation (UV, X, {gamma},...). Instead of heating, the charges trapped are released by light stimulation and produce a visible luminescence which amount is proportional to trap the `data stored` left by irradiation, enabling the dose measurement. The OSL phenomenon offers the same advantages as TLD plus the interesting possibility of a remote optical stimulation. The end-user objective deals with the development of a {gamma}-radiation Optical FIber Sensor (OFS) for dose measurement which can offer new functionalities based on OSL materials coupled with an optical fiber. Rare earth doped Alkaline Earth Sulphides (AES), BAFX:EU{sup 2+} (X = Cl, Br, I) and halogen alkaline have been studied (crystalline form, synthesis techniques, influence of dopants and color centers). Their characteristics are presented and extensively discussed. A specific experimental set-up to characterise various OSL phosphors has been developed. It allows the study of sensitivity, linearity, time decay behaviour of OSL signal and zeroing time. A joint study of OSL and TL has shown the technical limitations as well as the thermal fading and the origin of the long zeroing time. An Optical Fiber Sensor (OFS) based on OSL and using MgS:Sm has been developed for practical applications on nuclear fields. Its specifications are presented and discussed, moreover improvements are proposed. (author) 320 refs.

  2. Organisation et mise en oeuvre d'une infrastructure reglementaire nationale chargee de la protection contre les rayonnements ionisants et de la surete des sources de rayonnements. Rapport interimaire pour observations

    International Nuclear Information System (INIS)

    2001-11-01

    A number of IAEA Member States are undertaking to strengthen their radiation protection and safety infrastructures in order to facilitate the adoption of the requirements established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Standards). In this connection, the IAEA has developed a technical co-operation programme (Model Project on Upgrading Radiation Protection Infrastructure) to improve radiation protection and safety infrastructures in 51 Member States, taking into account national profiles and needs of the individual participating, countries. The present report deals with the elements of a regulatory infrastructure for radiation protection and safety and intends to facilitate the, implementation of the Basic Safety Standards in practice. It takes into account the proposals in an earlier report, IAEA-TECDOC-663, but it has been expanded to include enabling legislation and modi