WorldWideScience

Sample records for est-elle justifiee apres

  1. Le criquet du Mato Grosso : l'agriculture est-elle responsable ?

    Directory of Open Access Journals (Sweden)

    Lecoq, M.

    1995-01-01

    Full Text Available Le criquet du Mato Grosso : l'agriculture est-elle responsable ?. Investigations through bibliographical references and among the local population provided a collection of documents and evidences showing without any doubt that Rhammatocerus schistocercoides (ReHN, 1906 [Orth. Acrididae Gomphocerinae] outbreaks in Mato Grosso (Brazil are not a new event neither by nature nor by magnitude. Therefore, the present conception on the origin of those outbreaks need to be drastically revised. The previous hypotheses, implying an overrated agricultural development of concerned areas since 1980, must then be rejected.

  2. La metaphore est-elle la marque de l’insuffisance de l’esprit?

    Directory of Open Access Journals (Sweden)

    Isabelle Oliveira

    2010-01-01

    Full Text Available L’une des caractéristiques les plus communément reconnues à la discipline de la terminologie est sa conceptualité. Au contraire de l’opinion émise sur la métaphore, la terminologie s’efforce de travailler à partir de notions précises dont le sens doit être délimité et l’articulation à d’autres notions explicitée afin de bannir les ambiguïtés et les fausses évidences qu’elles véhiculent. Elle se distingue aussi du texte poétique caractérisé en particulier par la richesse des images et le jeu sur les signifiants. On comprend dès lors pourquoi la métaphore apparaît de prime abord comme une ennemie du champ de la terminologie qu’il faudrait bannir à tout prix. Cette figure de rhétorique consistant en un transport de sens risque à tout moment de rendre inopérant l’effort d’univocité et de rigueur du travail du terminologue. Mais la métaphore n’est pourtant pas absente des textes de spécialité. Il faut dès lors se demander si cette présence est « accidentelle”, contingente, ou si elle est incontournable et signifiante. Pour cela, il nous faudra étudier à la fois la place de la métaphore dans le texte de spécialité, et le discours des scientifiques portant sur elle. Mais une telle démarche nous laisse prisonnier de la dichotomie entre concept et métaphore et masque peutêtre une parenté inaperçue entre eux. Si le concept est habité par la métaphore, qu’en est-il du discours de spécialité? N’est-il pas réduit à n’être qu’un vaste poème qui ne s’avouerait pas comme tel? Est-elle seulement une figure de style ou aurait-elle un impact qui outrepasseraitsa modeste fonction discursive ? Il semble bien, même si le débat sur la métaphore et son usage est loin d’être clos. Notre théorie s’inscrit plutôt dans le sens d’une réévaluation du sens, d’une extension toujours plus grande de l’impact de ce trope qui, plus qu’une simple finalité esthétique, aurait une

  3. La violence sexuelle envers les enfants est-elle en baisse au Canada? Résultats d’enquêtes rétrospectives représentatives à l’échelle nationale

    Directory of Open Access Journals (Sweden)

    M. Shields

    2016-01-01

    Full Text Available Introduction : Selon de nombreuses sources de données, la violence sexuelle envers les enfants (VSE est en baisse aux États-Unis depuis le début des années 1990. Il semble par ailleurs qu’elle ait connu une hausse après la Seconde Guerre mondiale. Cette étude a pour but de faire l’examen des estimations de prévalence des cas de violence sexuelle durant l’enfance (VSdE signalés rétrospectivement dans le cadre de deux enquêtes nationales représentatives menées auprès de la population canadienne. Méthodologie : Les données proviennent de 13 931 répondants de 18 à 76 ans interrogés dans le cadre de l’enquête GENACIS (Gender, Alcohol and Culture: An International Study – Canada de 2004-2005 et de 22 169 résidents âgés de 18 ans et plus ayant participé à l’Enquête sur la santé dans les collectivités canadiennes – Santé mentale (ESCC – Santé mentale de 2012. Nous présentons des comparaisons de la prévalence de la VSdE par sexe et par groupe d’âge à la fois entre ces deux enquêtes et au sein de chacune. Résultats : Les résultats des deux enquêtes indiquent une baisse de la VSE depuis 1993, qui va de pair avec la baisse observée aux États-Unis. Il ressort également des résultats que le risque de VSE était plus élevé entre 1946 et 1992 qu’avant 1946. Les données sont plus solides pour les femmes. Conclusion : Constater une baisse de la VSE au Canada depuis le début des années 1990 est encourageant, étant donné les effets débilitants à long terme qui sont associés à la VSE. Une surveillance continue est essentielle. Ces effets négatifs à long terme sont la preuve de l’importance de poursuivre sur cette lancée, pour passer d’un risque faible à un risque nul.

  4. 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,...

  5. La féte est-elle un jeu?

    Directory of Open Access Journals (Sweden)

    Fribourg, Jeanine

    1999-12-01

    Full Text Available One may ask, are feasts games? Both feasts and games have characteristics in common: both are playful, involve voluntary acts, require rituals and a specific time and space. However, feasts and games also differ. In games, rules are explicit; in feasts, they are implicit. Some games need a single player only, whereas feasts are all collective performances. In a game, the player strives to win, but, in a feast, the participant has something else in his or her mind. Although rituals of a feast may include games, a feast is always more than a game or a set of games; before all else, it is a celebration or a commemoration: of a saint, of an historical event, etc. Furthermore, a feast includes roles that reinforce group identity and cohesión; these roles are lacking in games.Puede uno preguntarse ¿la fiesta es un juego?, pues ambos gozan de características comunes (lúdicas, acto voluntario, precisa ritualidad, espacio y tiempo concretos, etc.. La fiesta, no obstante, difiere del juego, pues mientras las reglas de éste son explícitas, las de la fiesta son implícitas, y hay juegos que pueden realizarse en solitario y la fiesta no; el objetivo de la fiesta no es vencer. La fiesta es más que un juego, por más que dentro de su ritualidad haya numerosos juegos, la fiesta es sobre todo una celebración o conmemoración (fiesta patronal, fiesta histórica..., además en ella existen roles importantes que no tiene el juego (refuerzo de la cohesión y de la identidad del grupo....

  6. 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

  7. 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.

  8. 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

  9. 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.

  10. 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

  11. 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)

  12. L'innovation est-elle sexiste ? Journée internationale de la femme ...

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

    24 avr. 2017 ... Tabitha Gathoni Mundia attribue ces statistiques au manque de modèles féminin dans le domaine des sciences et à la perception négative des femmes dans les domaines des STIM. Le président du CRDI, Jean Lebel, a accueilli environ 90 personnes à la rencontre D'un point de vue culturel, elle affirme ...

  13. Une sociologie de l’existence est-elle possible ?

    Directory of Open Access Journals (Sweden)

    Danilo Martuccelli

    2011-10-01

    Full Text Available En partant du diagnostic d’une affirmation croissante des questions existentielles dans les sociétés contemporaines, l’article interroge les manières dont la sociologie peut les aborder. Il revient dans une première partie sur les grands principes de la philosophie de l’existence, mais surtout sur l’œuvre de Jean-Paul Sartre qui a, plus que tout autre, explicitement marqué les principaux essais d’une sociologie existentialiste et les impasses de ces tentatives. Dans la seconde partie, en s’appuyant sur les conclusions précédentes, l’article développe les raisons d’une montée des thèmes socio-existentiels dans la modernité et répond à la question de savoir pourquoi, et surtout comment, l’analyse sociologique peut et doit étudier les questions existentielles.Is a sociology of existence possible?Starting from the diagnosis of an increasing assertion of existential questions in contemporary societies, this article interrogates ways that sociology can address them. In the first part, it comes back to the great principles of existential philosophy particularly on Sartre’s work, that has, more than anyone else, explicitly marked the major essays of an existentialist sociology as well as the dead ends of these attempts. In the second part, relying on the previous conclusions, this article will develop the reasons of the rise of socio-existential themes in modernity, and it will answer the question of why, and especially how, sociological analysis can and must study existential questions.¿Es posible una sociología de la existencia?A partir del diagnóstico según el cual emergen en la sociedad actual cuestiones de índole existencial, en este artículo se expone como la sociología puede abordarlas. Parte en la primera parte de los grandes principios de la filosofía existencial, especialmente de Sartre que más que ningún otro ha introducido una aproximación sociológico-existencialista y ha subrayado sus límites. En la segunda parte, apoyándose en las conclusiones precedentes, el artículo explica las razones de este aumento del cuestionamiento socio-existencial en la modernidad y responde a la pregunta del porqué y del como el análisis sociológico puede y debe interesarse por la temática existencial.

  14. Diffusion libre du droit est-elle acquise... pour de bon? | IDRC ...

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

    Depuis, un mouvement de la diffusion libre du droit, soutenu par les instituts ... des documents juridiques des documents du domaine public, consultables en ligne ... International Water Resources Association, in close collaboration with IDRC, ...

  15. L'entreprise publique est-elle nécessairement moins efficace?

    OpenAIRE

    Gérard Charreaux

    1997-01-01

    L'objectif de cet article est de réexaminer la question de l'inefficience des entreprises publiques à la lumière de la théorie de la gouvernance des entreprises. Deux questions principales sont posées. Quelles sont les différences principales entre les systèmes de gouvernance des entreprises publiques et des entreprises privées? Dans quelle mesure et par quelles voies ces différences de systèmes peuvent-elles expliquer les écarts de performance? La réflexion est notamment articulée autour de ...

  16. Antimatière Est-elle la clé de l'Univers?

    CERN Multimedia

    Grousson, Mathieu

    2009-01-01

    "De quoi est fait l'Univers? De matière ordinaire et, selon la théorie actuelle, de matière noire et d'énergie noire... dont nul ne sait rien! Et s'il s'agissait plutôt d'antimatière? Car elle permet de réécrire l'histoire du cosmos sans déroger à ses lois et, cette fois, sans nulle zone d'ombre. Reste à vérifier qu'elle antigravite bien..." (14 pages)

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. 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...

  2. 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.

  3. 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.

  4. 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

  5. À quelles conditions une charte est-elle efficace ? What are the conditions for an efficient charter?

    Directory of Open Access Journals (Sweden)

    Emmanuelle Danblon

    2010-04-01

    Full Text Available Dans cet article, on soutient que la déclaration des droits de l’homme constitue un genre rhétorique dont les conditions d’efficacité peuvent s’analyser à trois niveaux : les conventions, les fictions et les motivations. Sa visée est la création d’un monde commun. On montre à travers l’exemple de la déclaration pour le droit des animaux comment une charte échoue à réaliser cette visée.In this paper, it is argued that the Declaration of Human Right is a rhetorical genre that is efficient if three conditions are fullfilled: the expression of conventions, of fictions and of motivations. The aim of such a genre is to create a common world. It is shown with the Declaration for Animals’ Rights how such a charter can fail to achieve this purpose.

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. 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

  18. 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

  19. 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 ...

  20. 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.

  1. 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 ...

  2. 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.

  3. 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)

  4. 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

  5. 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

  6. 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)

  7. 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 ...

  8. 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)

  9. 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 ...

  10. 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...

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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

  19. 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...

  20. 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...

  1. 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

  2. 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.

  3. 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

  4. 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

  5. 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...

  6. 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.

  7. 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.

  8. 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.

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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)

  14. La régulation bancaire dans l'Union économique et monétaire ouest-africaine est-elle efficace ?

    OpenAIRE

    Pascal H. Dannon; Frédéric Lobez

    2014-01-01

    This paper investigates empirically the impact of bank regulation on the risk of default of WAEMU banks over the period 2000-2010. Our results suggest that banks which have relatively high capital ratios, those focusing on loans as well as large banks have a lower risk of default. However, WAEMU banks seem to finance riskier and more profitable assets to offset the extra cost of subordinated debt. Favorable macroeconomic conditions are factors reducing the risk of default while a high share o...

  15. Why is Dawsonite Absent in CO2 Charged Reservoirs? Pourquoi la dawsonite est-elle absente des réservoirs chargés en CO2 ?

    OpenAIRE

    Hellevang H.; Declercq J.; Aagaard P.

    2011-01-01

    Growth of the sodiumaluminium-hydroxy carbonate dawsonite (NaAl(OH)2CO3) after charging saline aquifers with CO2 has been assumed in a plethora of numerical simulations at different mineralogies, aqueous solutions, pressures and temperatures. It appears however that dawsonite is less abundant than expected in natural CO2 storage analogues if we take into account the thermodynamic stability alone. We have mapped the thermodynamic stability of dawsonite relative to mineral phases like al...

  16. Is acidification still a major air pollution concern?; L`acidification est-elle encore un probleme majeur de pollution atmospherique?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    Although other forms of long-range air pollution are gaining attention, acidification remains an important issue in certain parts of Europe as well as in other continents. In spite of the European 88/609 directive limiting acid emissions from large fuel burning plants, a large part of Europe soils receives acid deposits superior to the tolerance threshold, known as critical loads. Thus, the European Union is considering several new measures, such as a more drastic 88/609 directive, the limitation of emissions country by country, the limitation of sulfur content in heavy fuels, etc. Emission inventories, evaluation tools, long range transfrontier pollution models, integrated assessment, etc. are presented, together with the positions of various French governmental departments, public authorities and industries concerning the european strategy against acidification

  17. Politique nationale et coopération européenne: La méthode ouverte de coordination ouverte est-elle devenue plus contraignante? (1)

    NARCIS (Netherlands)

    Vanhercke, B.; Hamel, M.P.

    2008-01-01

    De récentes « évaluations » de différentes MOC ont décrié ces processus de coordination, les qualifiant de « purement rhétoriques et de peu de valeur », de « lointains et peu pertinents », voire pire, de « diversion à la mode ». Les auteurs rejettent ce point de vue qui considère la MOC comme de la

  18. Is acidification still a major air pollution concern?; L`acidification est-elle encore un probleme majeur de pollution atmospherique

    Energy Technology Data Exchange (ETDEWEB)

    Le Bellac, C. [INES, 75 - Paris (France)

    1997-12-31

    The issue of acid emissions from district space heating systems, which burn heavy fuels and coal, is discussed: it is shown that nitrogen oxide emissions are relatively low; for sulfur dioxide, three solutions are possible: switching to natural gas, but peak periods would require stored fuels; reducing the sulfur content in fuels, but its prices are too erratic; and de-sulfurizing the combustion smokes, but it does not appears as economically sustainable, as the prices for quality fuels and difficult fuels are close and low. It is reminded that district space heating is more especially aimed at council buildings

  19. 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...

  20. 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

  1. 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

  2. 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.

  3. 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...

  4. 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...

  5. 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)

  6. 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)

  7. 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

  8. 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.

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. 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…

  14. 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)

  15. 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)

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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).

  1. 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.

  2. 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

  3. 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...

  4. 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...

  5. 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

  6. [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.

  7. 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.

  8. 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

  9. 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.

  10. 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)

  11. 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)

  12. 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.

  13. 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

  14. 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.

  15. 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.

  16. 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

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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.

  9. 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.

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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.

  16. 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.

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. 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

  5. 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.

  6. 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.

  7. 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.

  8. 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

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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 ...

  15. 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

  16. 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

  17. 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...

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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.

  4. 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.

  5. 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

  6. 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)

  7. 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

  8. 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

  9. 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…

  10. 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

  11. 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

  12. 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

  13. L'organisation territoriale en Colombie et les compétences des collectivités territoriales. Une action internationale est-elle possible depuis le contexte local?

    Directory of Open Access Journals (Sweden)

    Angel Tuirán Sarmiento

    2010-01-01

    Full Text Available Para entender con mayor claridad la forma como está construido el edificio de la organización territorial y las facultades de que gozan los entes territoriales en Colombia se hace necesario definir de antemano los conceptos de República unitaria, descentralización y autonomía. La autonomía otorgada por la descentralización a las colectividades territoriales ha traído consigo un aumento significativo en las competencias y facultades de los gobiernos locales, que están siendo confrontados a nuevas responsabilidades, viéndose en la necesidad de reforzar su capacidad de respuesta frente a las demandas y necesidades locales. Por tal motivo, las colectividades territoriales colombianas han trascendido sus fronteras en búsqueda de herramientas que posibiliten una mejor gestión de los asuntos locales; es así como las colectividades territoriales vienen interactuando en el escenario internacional con otros gobiernos locales, aprovechando la autonomía otorgada por el proceso de descentralización y las ventajas estratégicas que ofrece hoy día la globalización.

  14. La question de l’autosuffisance protéique est-elle définitivement obsolète pour l’Union Européenne ?

    Directory of Open Access Journals (Sweden)

    Mahé Louis-Pascal

    2005-05-01

    Full Text Available Is the issue of European self-sufficiency in vegetal proteins definitely obsolete? The issue is reviewed from two standpoints: economic relevance and political feasibility in regards to international relations. Self sufficiency has a cost in terms of global welfare. Be it defined at the aggregate for food, or even for a core input of the European animal sector such as feed proteins, full self sufficiency is not seen as defensible from an economic standpoint. However food security may be a legitimate objective. It should be pursued by many tools and should first resort to the most efficient ones. Self supply is just one among several. A sensible criterion for a target degree of self sufficiency is when the marginal welfare cost of self sufficiency balances the welfare gain in terms of food security. Given the very low level of coverage of the European demand by domestic sources (20% and due to other risk factors, it seems plausible that an increase in self sufficiency would be appropriate. The political feasibility is low, due to the built-in bias of the CAP in favour of grains. The zero bound tariff in the first GATT round, the Blair House agreement in the Uruguay round have kept the EU in a straight jacket. In the Agenda 2000, the Commission has even anticipated the pressure of the US, probably excessively in view of the extension of flexibility payments to Soya in the 2002 US Farm Act. The concern for increased self sufficiency seems now to have faded away. What is left is mostly a strategy of security through a reliable rule-based trading system. The club of multifunctionnal countries should press exporters to concede the end the derogation to the GATT Article XI which allows them to restrain export in case of shortage. If a crisis on world markets would occur, followed as in the past by embargoes or other export restraints, the issue of self sufficiency would come back to the front scene.

  15. Tu m'as donné ta boue et j'en ai fait de l'or ou l'écriture poétique en classe de langues est-elle transgression ?

    Directory of Open Access Journals (Sweden)

    Marie André-Milesi

    2015-05-01

    Full Text Available Notre propos souhaite éclairer la notion de transgression dans le cadre des cours de langues avec l'aide des outils d'analyse du philosophe humaniste Paul Ricœur. Le jeu sémantique en donnant l'impression aux apprenants de sortir du sillon scolaire permet-il de penser soi-même comme un autre, d'ouvrir des axes de réflexion et de créativité dans le respect du Cadre Européen de Référence pour les Langues ? From rags to riches or transforming mud into gold : how and why poetry writing in the language classroom is a form of transgression? Abstract: Our analysis aims at enriching the notion of transgression with the analytical tools of the philosopher-cum-humanist Paul Ricœur. We may wonder if the semantic work at play with words giving learners the impression to walk out of the commonly established path allows to think oneself as another and to open new vistas for learners in the respect of the Common European Framework of Reference for Languages?

  16. Is the nuclear phaseout compatible with the respect of the Kyoto protocol? The example of Belgium; La sortie du nucleaire est-elle compatible avec le respect du protocole de Kyoto? l'exemple de la Belgique

    Energy Technology Data Exchange (ETDEWEB)

    Berger, A

    2008-12-15

    This document provides data and operations needed to evaluate the impacts of the nuclear phaseout on the respect of the Kyoto protocol. The data are based on the belgium electricity production. The author concludes that the nuclear power plants shutdown will lead to a non respect of the kyoto protocol in unacceptable limits. To respect the protocol, he presents two possibilities: the today nuclear park and the use of 1600 wind turbines of 2 MW, or the improvement of the energy efficiency of the thermal power plants. (A.L.B.)

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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.

  4. 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

  5. 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)

  6. 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)

  7. 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

  8. 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.

  9. 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.

  10. 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)

  11. 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

  12. 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

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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 ...

  19. 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 ...

  20. 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.

  1. 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.

  2. 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.

  3. 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)

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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.

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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 ...

  5. 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...

  6. 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

  7. 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)

  8. 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.

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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.

  18. 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.

  19. 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

  20. 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

  1. 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

  2. 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.

  3. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    Energy Technology Data Exchange (ETDEWEB)

    Ualikhan Zhiyenbayev [KAIST, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether.

  4. Veselības aprūpes iemaņas pusaudžiem bērnu namā

    OpenAIRE

    Zūpe, Daira

    2008-01-01

    Pētniecības darbā „Veselības aprūpes iemaņas pusaudžiem bērnu namā” autore Daira Zūpe izpēta un analizē vienu no bērnu namu aktuālajām problēmām veselības profilakses veicināšanā – veselības aprūpes iemaņu attīstīšanu. Pētījumā uzmanība pievērsta māsas lomai bērnu nama pusaudžu veselības aprūpes procesā, kur akcentēta veselības aprūpes pamatiemaņu nozīme veselības vecināšanā - fiziskās aktivitātes, ēšanas paradumi, kaitīgie ieradumi un higiēnas iemaņas. Pētniecības darba zinātniskā vadītā...

  5. The role of the Northern Sea Route in the development of floating nuclear power sources and prospects of cooperation with the EU countries, BRICS and APR

    International Nuclear Information System (INIS)

    Shadrin, A.P.; Ignat'ev, V.S.; Ivanov, V.A.

    2015-01-01

    The report discusses the construction of a transportable nuclear reactor, which will become the basis for the development of floating nuclear power sources on the Northern Sea Route. In this regard, the prospects of cooperation with the countries of the European Union, BRICS and APR [ru

  6. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    International Nuclear Information System (INIS)

    Ualikhan Zhiyenbayev; Chung, Dae Wook

    2015-01-01

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether

  7. Aprūpes īpatnības bērniem ar Dauna sindromu stacionārā

    OpenAIRE

    Lūse, Ērika

    2015-01-01

    Bakalaura darba tēma – Aprūpes īpatnības bērniem ar Dauna sindromu stacionārā. Tēmas aktualitāte pievērst uzmanību bērna ar Dauna sindroma aprūpei, kā arī mazināt stereotipus par šiem bērniem. Darba mērķis ir izpētīt Dauna sindromu un māsas lomu šo bērnu aprūpē, kā arī aprūpes īpatnības. Pētniecības uzdevumi ir veikt zinātniskās literatūras analīzi, pētījuma atbilstošas māszinību teorijas atlasi, izstrādāt anketu, veikt pilot pētījumu, iegūto datu apkopošanu, analīze un secinājumu veikšana. I...

  8. 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

  9. Browse Title Index

    African Journals Online (AJOL)

    Vol 38, No 1-2 (2015), Complications thromboemboliques apres catheterisme veineux femoral pour hemodialyse, Abstract .... Vol 34, No 1-2 (2011), La tomodensitométrie est-elle indiquée dans la prise en charge des douleurs lombaires à Ouagadougou au Burkina Faso : résultats d'une étude rétrospective de 164 cas ...

  10. 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

  11. 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

  12. 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.

  13. 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.)

  14. 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

  15. 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

  16. 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.

  17. 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...

  18. 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...

  19. 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.

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. 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.

  6. 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

  7. 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.

  8. 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.

  9. 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....

  10. 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 ...

  11. 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.

  12. 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.

  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. 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.

  15. 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)

  16. 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)

  17. 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.

  18. 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...

  19. 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...

  20. 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.)

  1. 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.

  2. 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.

  3. Position des lignes temporales sur le cranium de «Mrs » Ples (A.africanus) : une attribution sexuelle est-elle possible ?Possible position of the temporal lines on the cranium of 'Mrs' Ples (A. africanus): is sexual determination possible?

    Science.gov (United States)

    Prat, Sandrine; Thackeray, John Francis

    2001-03-01

    The cranium and associated matrix of Sts 5, a cranium of Australopithecus africanus is re-examined in the context of an unfused sagittal suture and the position of the temporal lines. These lines are not developed as a sagittal crest although they are close to the mid-sagittal line. A comparative study of the presence of sagittal crests in male, female, juvenile and adult specimens of extant great apes ( Gorilla, Pan, Pongo) suggests that the existence of a sagittal crest is influenced to a greater extent by anatomical age rather than by the sex of the individuals.

  4. Confined prostate cancer treated by conformational irradiation with intensity modulation with or without echography repositioning: is the dose received equivalent to the prescribed dose?; Cancer prostatique localise traite par irradiation conformationnelle avec modulation d'intensite avec ou sans repositionnement echographique: la dose recue est-elle equivalente a la dose prescrite?

    Energy Technology Data Exchange (ETDEWEB)

    Arnaud, A.; Peignaux, K.; Brenier, J.P.; Truc, G.; Naudy, S.; Maingon, P.; Crehange, G. [Centre Georges-Francois Leclerc, Dept. de Radiotherapie, 21 - Dijon (France); Regis, A. [CHU le Bocage, Service de Radiodiagnostic, 21 - Dijon (France); Deville, C.; Bonnetain, F. [Centre Georges-Francois Leclerc, Dept. de Biostatique, 21 - Dijon (France)

    2006-11-15

    The results suggest it would be possible to dispense a homogenous dose in agreement with the ICRU recommendations, nearer than the forward looking dose when the daily echographic repositioning is applied. This repositioning does not influence significantly the dosimetry for the risk organs. These results will validated in a bigger population. (N.C.)

  5. UNE MYTHOCRITIQUE DE LA CHANSON DE GUILLAUME EST-ELLE POSSIBLE ? DU VISIBLE À L’INVISIBLE DANS LA GESTE DE GUILLAUME D’ORANGE ET DE SES COMPAGNONS DE GUERRE (Is The Song of William susceptible to myth criticism? From the visible to the invisible in the Old French epic of William of Orange and his companions in arms

    Directory of Open Access Journals (Sweden)

    Ján Živčák

    2015-06-01

    Full Text Available The main aim of the present study is to examine the appropriateness of myth criticism methods in the context of medieval French literature. The first part of the essay is conceived as a brief confrontation, opposing the theory of Mircea Eliade concerning the repetition of the Hero Archetype in traditional epics to some textual elements in the chansons de geste, analogous to “visible mythemes” which tend to appear in popular epic poetry. Through a series of comparisons, we come to the conclusion that the interpretation to which the “eliadian” scheme leads us expands the boundaries of a literary myth (an academic invisible and rather aspires to a “theology of text” (a lived invisible. The second part of the article provides the reader with a practical application of the results of the preceding reflections, and includes an interpretation of the story of Vivien based on the Christian concept of Imitatio Christi.

  6. Urinary tract infection in childhood: lower or upper level? DMSA scintigraphic validation of a new clinical risk index; Infection urinaire de l'enfant: est-elle haute ou basse? proposition d'un score diagnostique valide par la scintigraphie renale au DMSA

    Energy Technology Data Exchange (ETDEWEB)

    Bayet-Papin, B.; Decomps-Hofmann, A.; Bovier-Lapierre, M. [Centre Hospitalier, Service de Medecine Nucleaire, 73 - Chambery (France)

    2001-04-01

    Urinary tract infection in children can be limited most of time at the lower level of the urinary tractus but an extension to the upper level of the tractus should not be neglected due to the asymptomatic nature of the disease. In our study, we suggest a new graph to predict the probability of acute pyelonephritis only if the bacteriological urinary analyse were obtained in good conditions and without any treatment. In the other cases, a DMSA scintigram should be proposed at the earlier phase of the diagnosis not to underestimate the risk of asymptomatic pyelonephritis. (authors)

  7. 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

  8. Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Park, Rae-Joon, E-mail: rjpark@kaeri.re.kr; Ha, Kwang-Soon; Rhee, Bo-Wook; Kim, Hwan Yeol

    2016-03-15

    Highlights: • Ex-vessel core catcher of PECS is installed in EU-APR1400. • CE-PECS has been conducted to test a cooling capability of the PECS. • Two phase flow in CE-PECS and PECS was analyzed using RELAP5/MOD3. • RELAP5 results are very similar to the CE-PECS data. • The super-step design is suitable for steam injection into the downcomer in PECS. - Abstract: The ex-vessel core catcher of the PECS (Passive Ex-vessel corium retaining and Cooling System) is installed to retain and cool down the corium in the reactor cavity of the EU (European Union)-APR (Advanced Power Reactor) 1400. A verification experiment on the cooling capability of the PECS has been conducted in the CE (Cooling Experiment)-PECS. Simulations of a two-phase natural circulation flow using the RELAP5/MOD3 computer code in the CE-PECS and PECS have been conducted to predict the two-phase flow characteristics, to determine the natural circulation mass flow rate in the cooling channel, and to evaluate the scaling in the experimental design of the CE-PECS. Particularly from a comparative study of the prototype PECS and the scaled test facility of the CE-PECS, the orifice loss coefficient in the CE-PECS was found to be 6 to maintain the coolant circulation mass flux, which is approximately 273.1 kg/m{sup 2} s. The RELAP5 results on the coolant circulation mass flow rate are very similar to the CE-PECS experimental results. An increase in the coolant injection temperature and the heat flux lead to an increase in the coolant circulation mass flow rate. In the base case simulation, a lot of vapor was injected into the downcomer, which leads to an instability of the two-phase natural circulation flow. A super-step design at a downcomer inlet is suitable to prevent vapor injection into the downcomer piping.

  9. Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

    International Nuclear Information System (INIS)

    Park, Rae-Joon; Ha, Kwang-Soon; Rhee, Bo-Wook; Kim, Hwan Yeol

    2016-01-01

    Highlights: • Ex-vessel core catcher of PECS is installed in EU-APR1400. • CE-PECS has been conducted to test a cooling capability of the PECS. • Two phase flow in CE-PECS and PECS was analyzed using RELAP5/MOD3. • RELAP5 results are very similar to the CE-PECS data. • The super-step design is suitable for steam injection into the downcomer in PECS. - Abstract: The ex-vessel core catcher of the PECS (Passive Ex-vessel corium retaining and Cooling System) is installed to retain and cool down the corium in the reactor cavity of the EU (European Union)-APR (Advanced Power Reactor) 1400. A verification experiment on the cooling capability of the PECS has been conducted in the CE (Cooling Experiment)-PECS. Simulations of a two-phase natural circulation flow using the RELAP5/MOD3 computer code in the CE-PECS and PECS have been conducted to predict the two-phase flow characteristics, to determine the natural circulation mass flow rate in the cooling channel, and to evaluate the scaling in the experimental design of the CE-PECS. Particularly from a comparative study of the prototype PECS and the scaled test facility of the CE-PECS, the orifice loss coefficient in the CE-PECS was found to be 6 to maintain the coolant circulation mass flux, which is approximately 273.1 kg/m"2 s. The RELAP5 results on the coolant circulation mass flow rate are very similar to the CE-PECS experimental results. An increase in the coolant injection temperature and the heat flux lead to an increase in the coolant circulation mass flow rate. In the base case simulation, a lot of vapor was injected into the downcomer, which leads to an instability of the two-phase natural circulation flow. A super-step design at a downcomer inlet is suitable to prevent vapor injection into the downcomer piping.

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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 ...

  19. 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.

  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. 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)

  8. 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

  9. Operational experience of the Marcoule reactors; Experience d'exploitation des reacteurs de Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Conte, F [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1963-07-01

    The results obtaining from three years operation of the reactors G-2, G-3 have made it possible to accumulate a considerable amount of operational experience of these reactors. The main original points: - the pre-stressed concrete casing - the possibility of loading while under power - automatic temperature control have been perfectly justified by the results of operation. The author confirms the importance of these original solutions and draws conclusions concerning the study of future nuclear power stations. (author) [French] Les resultats atteints apres trois ans de fonctionnement des reacteurs G-2/G-3 permettent une accumulation considerable de l'experience d'exploitation de ces reacteurs. Les principales originalites: - caisson en beton precontraint - chargement en marche - surveillance automatique des temperatures sont largement justifiees par l'exploitation actuelle. L'auteur confirme l'interet de ces solutions d'avant-garde et en tire des conclusions pour les etudes de futures centrales nucleaires. (auteur)

  10. Réutilisation d'argiles très plastiques (A4) en remblai : Suivi du comportement après trois ans de réalisation

    OpenAIRE

    BERCHE, Véronique; ROBERT, Nicolas; BOUSSAFIR, Yasmina; FERBER, Valéry

    2013-01-01

    Cet article présente la réalisation de remblais en argile très plastiques en 2003 sur l'A34 dans les Ardennes (France) ainsi que les résultats du suivi du comportement de ces remblais dans le temps. Après un bref rappel des conditions de réalisation de ces remblais, un résumé des résultats de portance et de densité à court et moyen terme sera exposé. Dans un deuxième temps, des résultats de densité (double sonde Gamma et passage au banc Gamma) et essais Dynaplaque réalisés en 2006 seront c...

  11. PRIMA-1 and PRIMA-1Met (APR-246: From Mutant/Wild Type p53 Reactivation to Unexpected Mechanisms Underlying Their Potent Anti-Tumor Effect in Combinatorial Therapies

    Directory of Open Access Journals (Sweden)

    Anne Perdrix

    2017-12-01

    Full Text Available p53 protects cells from genetic assaults by triggering cell-cycle arrest and apoptosis. Inactivation of p53 pathway is found in the vast majority of human cancers often due to somatic missense mutations in TP53 or to an excessive degradation of the protein. Accordingly, reactivation of p53 appears as a quite promising pharmacological approach and, effectively, several attempts have been made in that sense. The most widely investigated compounds for this purpose are PRIMA-1 (p53 reactivation and induction of massive apoptosis and PRIMA-1Met (APR-246, that are at an advanced stage of development, with several clinical trials in progress. Based on publications referenced in PubMed since 2002, here we review the reported effects of these compounds on cancer cells, with a specific focus on their ability of p53 reactivation, an overview of their unexpected anti-cancer effects, and a presentation of the investigated drug combinations.

  12. 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.

  13. 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

  14. 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

  15. 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.

  16. [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.

  17. 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 ...

  18. 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.

  19. 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

  20. 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

  1. 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.)

  2. 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

  3. 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

  4. 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.

  5. 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)

  6. 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).

  7. 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

  8. La nouvelle confiance en soi de la Turquie

    OpenAIRE

    Leguil-Bayart, Jean-François

    2011-01-01

    La Turquie est-elle en passe de surmonter son vieux complexe obsidional – ce que l’on appelle le « syndrome de Sèvres », par référence au traité avorté de 1920 qui prévoyait son démantèlement final et que rejeta Mustapha Kemal pour reprendre les négociations en position de force, après sa victoire militaire sur la Grèce – et sa sensibilité tiers mondiste d’écorchée vive, de mal aimée de l’Europe ? Le style personnel, à la fois ferme, visionnaire et bonhomme, d’Ahmet Davutoğlu, le nouveau mini...

  9. 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

  10. 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

  11. 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

  12. 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...

  13. 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 ».

  14. Burned after reading: the so-called list of Alexandrian librarians in P. Oxy. X 1241 Brûlée après lecture : la liste dite des Bibliothécaires d'Alexandrie dans le P.Oxy. X 1241 Burned after reading; la cosiddetta lista di bibliotecari alessandrini in P.Oxy. X 1241

    Directory of Open Access Journals (Sweden)

    Jackie Murray

    2012-06-01

    Full Text Available Cet article remet en question la valeur et la fiabilité du contenu du P.Oxy. X 1241, la liste dite des Bibliothécaires d’Alexandrie. Plutôt que de traiter de la liste des grammairiens des colonnes i.5.-ii.30 pour elle-même, comme les savants l’ont fait depuis que le papyrus a été publié, cet article prend en considération le document dans son intégralité. Cette lecture plus attentive du P.Oxy. X 1241 démontre qu’il y a une évidente continuité thématique entre la liste des grammairiens et les catalogues militaires qui suivent, qui n’a jamais été observée précédemment parce que les deux parties du document ont été traitées séparement. Il en découle des questions concernant trois hypothèses essentielles émises par les éditeurs originaux, B. P. Grenfell et A. S. Hunt : (1 la liste des col. i.5-ii.30 est-elle en réalité une liste des Bibliothécaires en chef de la Bibliothèque d’Alexandrie ? (2 le document est-il une copie ou une compilation de quelque œuvre savante qui remonte à la période hellénistique, et non la production d’un savant/grammairien du deuxième siècle de notre ère environ ? (3 Est-ce que les contenus du papyrus reflètent l’œuvre d’un savant/grammairien compétent qui était suffisamment informé sur la chronologie de la période ptolémaïque pour donner un décompte historiquement exact de la succession d’individus liés à la cour des Ptolémées et à la Bibliothèque d’Alexandrie ? S’il est vrai que dans son contenu et son utilisation de citations savantes le P.Oxy. X 1241 partage de nombreux points communs avec les catalogues en prose des époques hellénistique et impériale, les stratégies du discours savant déployées par l’auteur dans le catalogue militaire ne sont pas conformes aux normes des exemples scientifiques fiables. En conséquence, la valeur du texte comme preuve documentaire de l’histoire de la Bibliothèque d’Alexandrie a besoin d

  15. Compactification de la Supergravite 10-D Sur les Varietes de Calabi-Yau

    Science.gov (United States)

    Gagnon, Michel

    Les varietes de Calabi-Yau permettent une description relativement simple et assez juste de la realite. Recemment, de nombreuses equipes de recherche s'y sont interessees, en particulier P. Candelas, A. M. Dale, C. A. Lutken et R. Schimmrigk (13) qui ont propose une liste de 7868 configurations distinctes. Toutefois, nous croyons que certaines des techniques qui sont exploitees pour construire cette liste ne sont pas suffisamment justifiees et ont pour effet de soustraire a nos investigations bon nombre de configurations potentiellement interessantes. Ainsi, nous produisons, sans utiliser ces techniques simplificatrices, une liste de 97360 configurations. Ensuite, dans le cadre des modeles a 4 generations, nous appliquons un ensemble de criteres, fondes sur les symetries discretes, pour delimiter le domaine des configurations phenomenologiquement viables. Finalement, apres avoir fixe notre choix sur une configuration particuliere, nous essayons de montrer tout l'interet physique des varietes de Calabi-Yau en exposant certains aspects de la phenomenologie a basse energie, notamment les nombres quantiques, les spectres fermioniques, la brisure intermediaire du groupe de jauge et la duree de vie du proton.

  16. 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)

  17. 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

  18. 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

  19. 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.

  20. 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

  1. 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 ...

  2. 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 ...

  3. 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 ...

  4. 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

  5. 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.)

  6. 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).

  7. 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].

  8. 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.

  9. 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.

  10. 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.

  11. 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.)

  12. 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

  13. 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.)

  14. 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...

  15. 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

  16. 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 ...

  17. 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, ...

  18. 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

  19. 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)

  20. 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 ...

  1. 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 ...

  2. 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

  3. 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.)

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. La particule de Dieu à la découverte du boson de Higgs

    CERN Document Server

    Baggott, Jim

    2013-01-01

    De quoi le monde est-il constitué? Des questions aussi simples que celle-ci ont taraudé l'esprit de l'Homme depuis les origines. Même si les raisonnements sont devenus de plus en plus complexes au fil du temps, au fond, cette question centrale reste très basique. Ce livre raconte la quête des scientifiques pour élaborer un modèle permettant d'expliquer la structure de la matière à son niveau le plus élémentaire, jusqu'à l'annonce de la découverte du fameux boson de Higgs, au LHC, le 4 juillet 2012. Qu'est-ce que le boson de Higgs et en quoi sa découverte est-elle si importante? La réponse à cette question réside dans l'histoire du modèle standard de la physique des particules. Ce modèle, élaboré découverte après découverte, depuis le début du XXe siècle, recense toutes les particules constitutives de l'univers. Il prédisait jusqu'ici l'existence d'un champs dit de Higgs indispensable pour donner leur masse aux autres particules du modèle. Sans le boson de Higgs, l'univers ne pouv...

  10. Autonomie du groupe restreint et performance

    Directory of Open Access Journals (Sweden)

    Elke Nissen

    2005-09-01

    Full Text Available Un groupe est autonome lorsqu'il prend lui-même en charge sa gestion (Abric, 1996 et lorsque celle-ci fonctionne bien. L'autonomie du groupe restreint est une caractéristique revendiquée dans le cadre actuel de l'expansion de dispositifs collaboratifs à distance entre apprenants. La question qui se pose alors est de savoir si un groupe restreint autonome est plus performant qu'un groupe moins autonome. L'autonomie d'un groupe d'apprentissage en ligne est-elle en relation avec la qualité de la réalisation de la tâche ? Est-elle en relation avec les progrès réalisés par les membres du groupe ? Dans le cadre de notre étude expérimentale, menée dans deux dispositifs pédagogiques différents (l'environnement d'apprentissage Babbelnet et une formation sur la plate-forme Acolad, des étudiants ont réalisé en groupes restreints, avec l'accompagnement d'un tuteur, une tâche de type actionnel – en l'occurrence une rédaction en langue étrangère (allemand ou anglais. Pour ce faire, ils disposaient d'aides méthodologiques et linguistiques dans l'environnement pédagogique en ligne. Ils ont interagi par le biais d'Internet au moyen de différents outils de communication. Une analyse de l'interaction qui a eu lieu dans chaque groupe, l'évaluation des rédactions réalisées conjointement, deux tests réalisés respectivement avant et après la phase de travail en groupe ainsi qu'un formulaire auto-administré nous permettent de mettre en lien l'autonomie des groupes, d'une part, et leur performance, voire leur apprentissage, d'autre part. Au vu de cette étude, il apparaît que l'autonomie du groupe n'a pas d'influence directe sur l'apprentissage des groupes restreints. En revanche, un rapport est visible entre l'appréciation du fonctionnement du groupe par ses membres et l'évolution de la performance des groupes.

  11. Culture inavouée dans la nature, nature soumise dans la culture

    Directory of Open Access Journals (Sweden)

    Claude Rivière

    2001-12-01

    Full Text Available On peut tirer de l'idée que l'on se fait de la nature, soit une apologie de l'ordre dans le cosmos, soit un argument pour justifier l'existence d'un Dieu maître de la foudre et des saisons, soit l'enchantement d'un retour à l'état de nature supposé non conflictuel, soit enfin une conviction matérialiste selon laquelle l'homme doit dompter sa gourmandise et assurer la survie optimale de l'environnement sans le polluer. La société n'est pas à penser comme une modalité d'oubli de la nature mais en rapport d'inclusion dans la nature. Après périple philosophique de Platon à Moscovici, on déviera dans le champ des artistes peignant d'après nature et dans celui des linguistes analysant ce qui est dit contre nature. C'est la culture qui oppose nature et convention, fait et norme, matière et liberté humaine. C'est elle aussi qui nous fournit notre vocabulaire, nos classifications et nos jugements de valeur à propos de la nature. Récemment un courant écologiste se pose en protecteur sourcilleux de l'environnement et en organisateur d'un développement durable, mais dans la deep ecology, on glisse vers le culte d'une biosphère de rêve.

  12. L'esprit de sel science, culture, politique

    CERN Document Server

    Lévy-Leblond, Jean-Marc

    1984-01-01

    L'esprit de sel. Activité de recherche, la science est-elle nécessairement productrice de connaissances ? Y a-t-il de nouvelles formes et normes du savoir ? Qu'est la science pour la science ? Activité intellectuelle. la science est-elle aussi une activité culturelle ? La science moderne est-elle dans la culture. est-elle une nouvelle culture - devrait-elle l'être ? Qu'est la science pour la culture ? Activité sociale. la science est liée de façon complexe aux structures économiques et à la conjoncture politique. Quel rôle joue-t-elle, quels conditionnements subit-elle ? Qu'est la science pour la politique ? Voici un ensemble de contributions pour aiguiser ces questions cruciales et décaper les idées reçues.

  13. GeneXpert MTB/RIF dans le dépistage de la tuberculose pulmonaire à l’Hôpital Provincial Général de Référence de Bukavu, à l’Est de la République Démocratique du Congo: quelles leçons tirées après 10 mois d’utilisation?

    Science.gov (United States)

    Lupande, David; Kaishusha, David; Mihigo, Carine; Itongwa, Moise; Yenga, Gustave; Katchunga, Philippe

    2017-01-01

    Introduction En Afrique subsaharienne, les méthodes de diagnostic de la tuberculose sont insuffisantes et reposent essentiellement sur la microscopie. Elles constituent un réel frein pour le contrôle de la tuberculose. La présente étude voudrait évaluer les performances du GeneXpert MTB/RIF vis à vis de la microscopie classique de Ziehl-Neelsen à l’Hôpital Provincial Général de Référence de Bukavu, à l’Est de la République Démocratique du Congo après 10 mois d’utilisation. Méthodes Les résultats de la coloration au Ziehl-Neelsen et de la biologie moléculaire sur GeneXpert MTB/RIF de 452 patients suspects de tuberculose ont été colligés. La validité d’un test par rapport à l’autre dans la détection de la tuberculose a été étudiée. Résultats Dans le groupe entier, la fréquence de la tuberculose pulmonaire était de 16.3%. La positivité était significativement plus élevée pour le GeneXpert MTB/RIF que pour le Ziehl-Neelsen dans le groupe entier (15.9% vs 9.3%, p= 0.03) et chez les séropositifs pour le VIH (52.0% vs 24.0%; p = 0.007). Cependant, la sensibilité de GeneXpert MTB/RIF comparé au Ziehl-Neelsen n’était pas maximale (95.2%). Enfin, GeneXpert MTB/RIF a détecté 20.8% de résistance à la rifampicine. Conclusion La présente étude confirme la supériorité de GeneXpert MTB/RIF sur la coloration de Ziehl-Neelsen dans la détection de la tuberculose et dans la prédiction de la multi résistance. Son utilisation systématique couplée au Ziehl-Neelsen permettrait de mieux contrôler la tuberculose en Afrique subSaharienne. PMID:29187929

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

    OpenAIRE

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

    2013-01-01

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

  15. 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

    electrons de 15 MeV emis par un betatron. Les auteurs presentent les resultats d'une etude autoradiographique sur le comportement de differentes categories de cellules de thymus chez la souris, etude dans laquelle ils ont utilise de la thymidine tritiee comme precurseur de l'ADN. Les donnees sont fonction des modifications du nombre relatif des diverses categories de cellules (par taille), ainsi que du poids de l'organe. Apres irradiation, la proportion des grandes cellules par rapport aux petites augmente; l'incorporation de thymidine tritiee diminue au niveau des grands et petits lymphocytes. Dans la phase aiguee, on n'observe aucune difference notable entre l'effet des rayons X et celui des electrons sur les dimensions des cellules et sur le marquage des grandes cellules. Une modification relative apparait pour le marquage des petites cellules; ce phenomene, qui peut avoir un rapport avec les valeurs EBR des electrons rapides, concorde avec les donnees relatives au poids de l'organe. Pendant la regeneration, les cellules moins differenciees presentent une proliferation active, mais le pourcentage des lymphocytes arrives a maturation reste faible. Apres exposition a des electrons de 15 MeV, la proliferation des grandes cellules est plus active, suivant les courbes d'atrophie du thymus en fonction du temps. D'apres les resultats ci-dessus, il semblerait que le pouvoir de regeneration depende de l'importance des lesions subies par les cellules primitives; pour une dose donnee, ces lesions semblent plus marquees apres exposition aux rayons X qu'apres exposition aux electrons. (author) [Spanish] El mecanismo de restauracion de las radiolesiones agudas puede estudiarse utilizando dos tipos de radiaciones que presentan escasas diferencias en cuanto a la intensidad de la EBR, pero que difieren notablemente en lo que respecta a los efectos durante la fase de restauracion. Como se ha observado en experimentos anteriores, ello puede lograrse comparando los efectos producidos en los

  16. IAEA Newsbriefs. V. 14, no. 2(83). Apr-May 1999

    International Nuclear Information System (INIS)

    1999-01-01

    This issue gives brief information on the following topics: Nuclear Safety: States Taking 'Steps in Right Direction', Contracting Parties to Convention on Nuclear Safety, Nuclear Power Worldwide, Nuclear's Future: Director General Address in Japan, Year 2000 Programme and Budget Goes Before IAEA Board, The IAEA and Y2K Issues: Reports, Workshops, Internet Links, Strengthened Safeguards System: Status of Additional Protocols, States Join International Conventions in Nuclear Fields, IAEA International Scientific Symposia and Seminars in 1999, In Memoriam: Munir Ahmad Khan, and other short information

  17. LHC Beam Splash seen by the ATLAS detector, 7 Apr 2015 - Run 260466 - event 22425

    CERN Multimedia

    Adam Bourdarios, Claire

    2015-01-01

    Event display of one of the collimator "splash" event seen by the ATLAS experiment in LHC Run-2 , on Tuesday April the 7th : event 22425, run 260466. The collimator position is 140m in front of the ATLAS interaction point. The spray of particles enters ATLAS from the left hand side of the picture. The length of the yellow bars indicates the energy deposited in the ATLAS calorimeter.

  18. Annual report of the Japan Atomic Energy Research Institute, Apr. 1987 - Mar. 1988

    International Nuclear Information System (INIS)

    1988-01-01

    In fiscal 1987, the Atomic Energy Commission of Japan revised the 'Long term program for development and utilization of nuclear energy', which is done every five years. It determined the future direction of the research and development in JAERI. Three basic objectives are indicated in it, that is, to qualitatively upgrade nuclear technology, to tackle the frontiers of the technology, and to promote international collaboration. The new 'Long term task plan' of JAERI based on the 'Long term program' was established in August, 1987. The integral experiment on loss of coolant accident, the test on reactivity-initiated accident, the irradiation and post-irradiation examination of fuel, the development of safety analysis codes, the design and safety analysis of the Nuclear Fuel Cycle Safety Engineering Research Facility, the treatment and disposal of radioactive wastes, the preparatory work for constructing the High Temperature Engineering Test Reactor, the full scale plasma heating experiment with JT-60, the study on high efficiency confinement mode and current drive, the construction of the new home port for the nuclear ship 'Mutsu', the design of an advanced marine reactor, the reactor physics of FBRs and ATRs and other fundamental studies, and the operation of JRR-2, JRR-4 and JMTR are reported. (K.I.)

  19. Numerical analysis of APR1400 Steam Generator by CUPID/MARS heat structure coupling

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Ryong Lee; Lee, Seung Jun; Pakr, Ik Kyu; Yoon, Han Young [KAERI, Daejeon (Korea, Republic of); Cho, Hyoung Kyu [Seoul National University, Seoul (Korea, Republic of)

    2015-05-15

    To design and analyze steam generators, many computer codes have been developed and used around the world. In this study, the coupled CUPID and MARS code was used for the simulation of boiler side of the PWR steam generator. This paper presents the description of the coupling method, validation for porous media approach against the rod bundle experiment and the preliminary simulation results of PWR steam generator using the coupled code. In the present study, the multi-scale thermal-hydraulic analysis method using the coupled CUPID/MARS code was applied for the simulation of the steam generator. The primary side of the steam generator and other RCS was simulated by MARS and the secondary side was calculated by CUPID with porous media approach. For coupled simulation, the porous medium was applied in order to take into account the effect of the U-tube bundle and other supporting structure which play a role to be a flow resistance. More realistic physical model such as moisture separator slug behavior should be developed for the near future. The application of the coupled simulation should be extended to the accident scenario.

  20. Imaging of the lumbar spine after diskectomy; Imagerie du rachis lombaire apres discectomie

    Energy Technology Data Exchange (ETDEWEB)

    Laredo, J.D.; Wybier, M. [Hopital Lariboisiere, 75 - Paris (France)

    1995-12-31

    The radiological investigation of persistent or recurrent sciatica after lumbar diskectomy essentially consists of demonstrating recurrent disk herniation. Comparison between plain and contrast enhanced CT or MR examinations at the level of the diskectomy is the main step of the radiological survey. The meanings of the various radiological findings are discussed. Other lesions that may induce persistent sciatica after lumbar diskectomy include degenerative narrowing of the lateral recess, spinal instability, stress fracture of the remaining neural arch, pseudo-meningomyelocele after laminectomy. (authors). 34 refs., 5 tabs.

  1. IAEA Newsbriefs. V. 11, no. 2(71). Apr-May 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This issue gives brief information on the following topics: Chernobyl Conference sums up Scientific Understanding, International Forum on the Safety of RBMK Reactors, IAEA Board of Governors, Radiological Study of the Mururoa and Fangataufa Atolls, Safeguards Support, Workshop on Modelling Methods for Water Systems, Uranium Market Trends, Security Council Resolution on Iraq, South East Asian NWFZ, Radioactive Waste Management, Nuclear Seminar in Poland, and other short information

  2. State of the Art Report for Development of Control Element Drive Mechanism of the APR+ Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Seon; Choi, Suhn; Song, Chul Hwa

    2008-10-15

    Recently newly-developed nuclear reactors with increased safety and enhanced performance by developed countries in the nuclear area are competing in the global nuclear market. Several reactors, for example AP600 and AP1000 by Westinghouse Electric Co. in USA, EPR by Areva in Europe, APWR by Mitsubishi Heavy Industry in Japan in the pressurized power reactor, are competing to preoccupy the nuclear market during Nuclear Renaissance. Dedicated control element drive mechanism with enhanced performance and increased safety are developed for these new reactors. And load follow capability is required, and it is estimated that load follow requirement make design requirement of a control element drive mechanism harsh. It is necessary to review the current technical state of a control element drive mechanism. This work is aimed to review the design characteristics of a past and current control element drive mechanism for a nuclear reactor and to check the direction and goal of CEDM design development recently.

  3. Study on the VFD (Variable Frequency Drive) for RCP (Reactor Coolant Pump) Motors of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jung Ha; Robert, M. Field; Kim, Tae Ryong [Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    Most industrial facilities are continually searching for ways to reduce energy costs while increasing or maintaining current production. In terms of electric motors, Variable Frequency Drive (VFD) units represent a critical opportunity for energy savings. Currently, VFDs are used on about ten (10) percent of industrial process motors, and this percentage is increasing every year. Properly applied VFDs have been documented to save as much as fifty percent of the energy consumed by certain industrial processes. Nuclear Power - Power plants in general and Nuclear Power Plants (NPPs) in particular are slow to adopt new technology. The nuclear power industry requires a nearly absolute demonstration through operating experience in other industries in which the new approach will result in a net improvement in plant reliability without any surprises. Only recently has the nuclear industry begun to adapt VFD units for large motors. Specifically, there are several examples in the Boiling Water Reactor (BWR) fleet of replacing Motor-Generator (M-G) sets with VFD units for Reactor Recirculation (RR) pump motor service. At one station, VFD units were introduced upstream of the Circulating Water (CWP) pump motors to address environmental issues. They units are taking advantage of VFD technology whose benefits include increased reliability, reduction in electrical house load, improved flow control, and reduced maintenance. RCP Application - In the case of new generation, it has been reported that the Westinghouse AP1000 will make use of VFD units for the Reactor Coolant Pump (RCP) motors.

  4. La femme et sa destinée d'après Edith Stein

    Directory of Open Access Journals (Sweden)

    Philippe Lauria

    2014-12-01

    Full Text Available Woman's Destiny according Edith Stein The following essay aims to show that Edith Stein's conception of women was a feminist and a traditionalist one. This could be interpreted by some philosophers as a sort of contradiction. Thus the author presents the different arguments detecting such  a conflict between feminism and traditionalism. These arguments are based in fact on the opposition between nature or essence, on the one hand, and freedom, on the other hand. The thesis of the author is that there is not necessarily a conflict between essence and freedom, and that essence is not a fiction but an ontological reality which, interpreted in the way of Edith Stein, makes it possible to conceive sexual difference in a perfect synthesis between the Christian tradition and gender equality.

  5. Proliferation after the Iraq war; La proliferation apres la guerre d'Irak

    Energy Technology Data Exchange (ETDEWEB)

    Daguzan, J.F

    2004-09-15

    This article uses the Iraq war major event to analyze the approach used by the US to fight against proliferation. It questions the decision and analysis process which has led to the US-British intervention and analyzes the consequences of the war on the proliferation of other countries and on the expected perspectives. Finally, the future of proliferation itself is questioned: do we have to fear more threat or is the virtuous circle of non-proliferation well started? (J.S.)

  6. Acute exercise does not induce an acute phase response (APR) in Standardbred trotters

    DEFF Research Database (Denmark)

    Kristensen, Lena; Buhl, Rikke; Nostell, Katarina

    2014-01-01

    ), and iron], muscle enzymes [creatinine kinase (CK) and aspartate transaminase (AST)], and hemoglobin were assessed in 58 Standardbred trotters before and after racing. Hemoglobin levels increased and iron levels decreased 12 to 14 h after racing and haptoglobin concentrations, white blood cell counts......, and iron levels were decreased 2 and/or 7 d after racing. Concentrations of CK, AST, SAA, and fibrinogen were unaltered in response to racing. Acute strenuous exercise did not elicit an acute phase reaction. The observed acute increase in hemoglobin levels and decreases in haptoglobin and iron levels may...

  7. 15 CFR 781.1 - Definitions of terms used in the Additional Protocol Regulations (APR).

    Science.gov (United States)

    2010-01-01

    ..., corporation, partnership, firm, association, trust, estate, public or private institution, any State or any... and the mine or its infrastructure is not capable of further operation. Uranium Hard-Rock Mine... (Suspended). A uranium hard-rock mine where ore production has ceased, but the mine and its infrastructure...

  8. People and things. CERN Courier, Apr 1991, v. 31(3)

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: ; In 1992 the XVth International Conference on High Energy Accelerators will be held from 20-24 July at the Congress Centrum, Hamburg, Germany. ; The 100 or so places for the CERN Accelerator School's 'Radiofrequency Engineering for Particle Accelerators' course in Oxford from 3-10 April were sold out well in advance. ; A Symposium on Quantum Physics, in memory of John Stewart Bell who died on 1 October 1990 will be held at CERN on 2-3 May

  9. Construction of APR1000 nuclear power information management system based on international standards

    International Nuclear Information System (INIS)

    Choi, Seung Hwan; Song, Deok Yong; Han, Byung Sub; An, Kyung Ik; Hwang, Jin Sang

    2010-01-01

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model

  10. Post-external radiotherapy hypothyroidism: 15 cases; Hypothyroidie apres radiotherapie externe. A propos de 15 cas

    Energy Technology Data Exchange (ETDEWEB)

    Kaffel, N.; Mnif, M.; Abid, M. [Centre Hospitalier Universitaire Hedi Chaker, Sfax (Tunisia); Daoud, J. [Centre Hospitalier Universitaire Habib Bourguiba, Sfax (Tunisia)

    2001-06-01

    Post-external radiotherapy hypothyroidism: 15 cases. Hypothyroidism frequency is estimated to be between 10 and 45% after radiotherapy alone, and 40 to 67% after radiotherapy associated with thyroidectomy. This hypothyroidism is infra-clinical in 60% of the cases. Our study concerned 15 cases of hypothyroidism after external radiotherapy delivered between and 1991 and 1999. An irradiation of the cervical, cerebral and thorax regions was indicated for different types of cancers. Larynx carcinoma epidermoid was the most frequent cancer (seven cases); the radiation treatment used cobalt 60 with conventional fractionation, i.e., 2 Gy per treatment, five treatments a week. In nine cases, the hypothyroidism was discovered during a systematic examination; it was clinically evident in the six remaining cases. Hypothyroidism appeared after an irradiation dose average of 50 Gy (extremes 30-65 Gy). The average duration of the irradiation was about 7 weeks and the hypothyroidism appeared in a mean 22 months. In all cases, the substituting treatment was initiated with a favorable progression. Faced with the risk of hypothyroidism, it is necessary to check patients who have undergone external irradiation of the neck. (authors)

  11. National and Global Infrastructure of the Arctic Zone of the APR: New Challenges

    Directory of Open Access Journals (Sweden)

    Boris Khananovich Krasnopolskiy

    2015-06-01

    Full Text Available The article addresses issues of formation of the national and global infrastructure in the Arctic and its Asia-Pacific zone in the context of the new challenges in the development of the region, associated mainly with the political and military deterioration of relations between Russia and the United States. The study also characterizes international experience in the area of infrastructure researches and presents strategic documents of both countries in the sphere of the study and development of the Arctic and its territories. The author concludes that research organizations need to overcome their passivity to strengthen cooperation between these structures from both sides, which is absolutely essential for the development of a global scientific and other kinds of infrastructure and for the further successful, rational and effective exploitation of the Arctic areas

  12. Development of new port in Minahasa Utara: A-pre feasibility study

    Science.gov (United States)

    Hamzah, Suharman; Abdurahman, Asad; Saputra, Reza; Aprianti, Evi

    2017-11-01

    In order to support Indonesian Government priority sector to build toll maritime in conjunction to connect "nusantara" as an archipelago country, and also to develop the frontier area of Indonesia, the existence of a port should get more in attention as the gate of Indonesia. A port has significant role in changing of transport mode and at the end as catalyst of economic growth. An important thing from pre-feasibility studies is the priority factor will clearly shown wheather it is good or fair. As a supporting to service passenger moving, container, general cargo and also bulk, a port is necessary to have an excellent design and planning. A pre-feasibility study is required to obtain a scientific basis based on value of interest and the necessity of the region. A pre-feasibility study in this paper aims to identify potential support of the region and giving priority location of development of new port in Minahasa Utara regarding to spatial, government issues, transportation aspect, regional economics, environmental aspect and technical aspect consideration. Experimental Method used are qualitative and quantitative, going through to the data obtained and supported by interview on the spot as well as questionnaire surveys. Result of this paper showing that there are 5 locations suitable with the requirements. Based on the level of priority, high (Kema, Likupang), moderate (Linuhu, Kahuku) and low (Gangga 1).

  13. Apres le Deluge at State U: A Comprehensive Public University Responds to the Great Recession

    Science.gov (United States)

    Skinner, Richard A.; Miller, Emily R.

    2013-01-01

    In this article, the authors describe one institution--East Carolina University--that they think is representative of an important type and a large proportion of American universities, the comprehensive public university, and its responses to the lingering Great Recession. As a group, comprehensives handle almost 40 per cent of the total student…

  14. Après nous, le déluge / Toomas Hendrik Ilves

    Index Scriptorium Estoniae

    Ilves, Toomas Hendrik, 1953-

    2006-01-01

    Euroopa Liidu põhiseadusliku leppe läbikukkumisest, vanade liikmesriikide suhtumisest uutesse, Venemaa lootusest Euroopa Liidu nõrgenemisele. Eesti peaks tihendama koostööd teiste uute liikmesriikidega oma ühishuvide kaitsel. Ilmunud ka: Sirp : Diplomaatia 8. juuli 2005 nr. 22/23, lk. 2-4

  15. People and things. CERN Courier, Apr 1986, v. 26(3)

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. A Summer Study to be held in Snowmass, Colorado, from 23 June to 11 July will allow the US particle physics community to critically evaluate all aspects of the proposed US Superconducting Super Collider (SSC) in the light of conceptual design, progress in accelerator technology, new developments in collider physics, and innovations in instrumentation. Organized jointly by the European Committee for Future Accelerators (ECFA) and the Rheinisch-Westfälische Technische Hochschule in Aachen, a 'LEP 200' Workshop is being arranged from 29 September to 1 October to work out the physics objectives and experimental requirements for running LEP at around 100 GeV per beam. A four-day practical course on microelectronics is being hosted by CERN and the International School of Geneva

  16. People and things. CERN Courier, Apr 1986, v. 26(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1986-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. A Summer Study to be held in Snowmass, Colorado, from 23 June to 11 July will allow the US particle physics community to critically evaluate all aspects of the proposed US Superconducting Super Collider (SSC) in the light of conceptual design, progress in accelerator technology, new developments in collider physics, and innovations in instrumentation. Organized jointly by the European Committee for Future Accelerators (ECFA) and the Rheinisch-Westfälische Technische Hochschule in Aachen, a 'LEP 200' Workshop is being arranged from 29 September to 1 October to work out the physics objectives and experimental requirements for running LEP at around 100 GeV per beam. A four-day practical course on microelectronics is being hosted by CERN and the International School of Geneva.

  17. State of the Art Report for Development of Control Element Drive Mechanism of the APR+ Reactor

    International Nuclear Information System (INIS)

    Lee, Jae Seon; Choi, Suhn; Song, Chul Hwa

    2008-10-01

    Recently newly-developed nuclear reactors with increased safety and enhanced performance by developed countries in the nuclear area are competing in the global nuclear market. Several reactors, for example AP600 and AP1000 by Westinghouse Electric Co. in USA, EPR by Areva in Europe, APWR by Mitsubishi Heavy Industry in Japan in the pressurized power reactor, are competing to preoccupy the nuclear market during Nuclear Renaissance. Dedicated control element drive mechanism with enhanced performance and increased safety are developed for these new reactors. And load follow capability is required, and it is estimated that load follow requirement make design requirement of a control element drive mechanism harsh. It is necessary to review the current technical state of a control element drive mechanism. This work is aimed to review the design characteristics of a past and current control element drive mechanism for a nuclear reactor and to check the direction and goal of CEDM design development recently

  18. Thermionics. A bibliography with abstracts. Search period covered: 1970--Apr 1975. [190 references

    Energy Technology Data Exchange (ETDEWEB)

    Grooms, D.W.

    1975-04-01

    Research on thermionic power generation, power plant design, converter design, and basic research on thermionic materials are cited in the bibliography. Spacecraft applications are included. (Contains 190 abstracts).

  19. Symposium on Electromagnetic Launcher Technology, 5th, Sandestin, FL, Apr. 3-5, 1990, Proceedings

    Science.gov (United States)

    Gooden, Clarence E.

    1991-01-01

    The present conference on electromagnetic accelerators (EMAs) and railguns (RGs) discusses active-current management for four-rail RGs, the design of a compulsator-drive 60-caliber RG, EMA studies with augmented rails, muzzle-shunt augmentation of conventional RGs, effect of in-bore gas on RG performance, the distributed-energy store RG, plasma diagnostics for high power ignitron development, a review of EMA armature research, RG hybrid armatures, a new solid-armature design concept, and the electrodynamics of RG plasma armatures. Also discussed is RG modeling at speed using three-dimensional finite elements, power supply technology for EMAs, rotating machine power supplies for next-generation EMAs, advanced EMA power supplies with magnetic-flux compression, metal-to-metal switches for large currents, lightweight high-effiency energy-storage transformers, hypervelocity projectile development for EMAs, structural design issues for EMA projectiles, stiff RGs, a reinforced Al conductor for cryogenic applications, mass-stabilized projectile designs for EMA launch, indictively-commutated coilguns, an actively switched pulsed induction accelerator, a plasma gun-augmented electrothermal accelerator, a symmetrical rail accelerator, and a travelling-wave synchronous coil gun.

  20. IAEA Newsbriefs. V. 10, no. 1(67). Mar-Apr 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This issue gives brief information on the following topics: IAEA Board to Consider Proposal on Safeguards, IAEA Director General to Address NPT Conference in mid-April, IAEA Hosts UN System-Wide Meeting, Joint IAEA/EC/WHO Conference on Chernobyl Announced, IAEA Concludes Post-Chernobyl Research Project, Uranium Data in Environmental Monitoring, Director General Address in Chile, South Africa, the Philippines Host Nuclear Information Seminars, Upcoming IAEA Conferences, Symposia and Seminars, Isotopes in Water Resources Management, Environmental Impacts of Radioactive Releases, Joint FAO/IAEA Symposium on Crop Improvement, Other Conferences, Symposia and Seminars in 1995, Safeguards and Non-Proliferation Developments (IAEA Safeguards Agreements, New NPT Members), Handbook on Nuclear Communications, SIT Campaign in Zanzibar, and other short information

  1. Conflit, déplacements et reconstruction après-guerre : le cas de ...

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

    30 nov. 2015 ... La guerre cause des pertes aux personnes, aux familles et aux collectivités. Les survivants ont souvent perdu terre, foyer, biens, moyen de subsistance et réseau. Ils ont de la difficulté à obtenir du crédit, des soins de santé, de la formation, des services sanitaires et d'autres services afin de rebâtir leur vie.

  2. People and things. CERN Courier, Apr-May 1995, v. 35(3)

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: Spokesmen at the CDF experiment at Fermilab's tevatron protonantiproton collider serve two-year terms. Most recently Mel Shochet (Chicago) and Bill Carithers ( LBL ) were co-spokesmen. Before the recent round of elections, Mel declared that he did not want to run again, having served for six and a half years (following the departure of Roy Schwitters to the SSC). Bill Carithers (who replaced Alvin Tollestrup two years ago) did decide to run again. Through a complicated process, a long list of nominees was narrowed to six candidates and an election held via the World Wide Web. Results were announced on January 19: Bill Carithers was reelected for another term, and Giorgio Bellettini (Pisa) becomes his new cospokesman. (see Top discovery' - page 1). Career milestone - Lucien Montanet: Officially 'retiring' from CERN is Lucien Montanet, whose impressive career spans a wide range of physics interests and is characterized by his ebullient enthusiasm. Joining CERN in 1957 for cosmic ray experiments, he went on to participate in pioneer CERN investigations using bubble chambers and using antiprotons, going on in the 1960s to play a prominent role in the discovery and investigation of hadron resonances, and becoming a key figure in the international Particle Data Group. His objective review talks on the complex hadron resonance scene became a feature at international meetings. In the 1970s he pushed the development of the European Hybrid Spectrometer project and went on to join the L3 and Crystal Barrel collaborations at LEP and LEAR respectively. As well as experimental physics, he has also contributed to theoretical work (with Francis Low) and phenomenology (with Leon van Hove). In 1985 he became the CERN-Russia coordinator, a demanding responsibility now inherited by Jim Allaby as coordinator of CERN Non-Member State affairs

  3. 78 FR 37531 - Agency Information Collection Activities; Comment Request; Annual Performance Reporting (APR...

    Science.gov (United States)

    2013-06-21

    ... these ten NIDRR grant programs: Rehabilitation Research Training Centers (RRTCs); Rehabilitation Engineering Research Centers (RERCs); Field Initiated Research Projects (FIPs); Advanced Rehabilitation... National Institute on Disability and Rehabilitation Research (NIDRR) of the Department of Education...

  4. Monthly results of measurements: Apr 1997; Tableaux mensuels des mesures. Avril 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    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.

  5. Engineer: The Professional Bulletin of Army Engineers, Jan-Apr 2010

    Science.gov (United States)

    2010-04-01

    Dornstadter 51 Transformation in Korea By Major Rafael Pazos and Captain Miguel Uc Headquarters, Department of the ArmyVolume 40 PB 5-10-1...States with an By Major Rafael Pazos and Captain Miguel Uc January-April 201052 Engineer initial grant of 205 acres at USAG–Humphreys, allowing the...the quality of life of our Service members. Major Pazos is the deputy commander of the United States Army Corps of Engineers (USACE), Gulf Region

  6. IAEA Newsbriefs. V. 12, no. 2(75). Apr-May 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This issue gives brief information on the following topics: IAEA safeguards inspectorate granted broader rights, Conferences on nuclear liability, waste safety in early September, States set nuclear safety review meeting, Statements of IAEA Director General, Namibia joins anti-trafficking programme, Symposium on desalination in Republic of Korea, Energy issues on agenda of nuclear fuel cycle symposium in June, IAEA seminars and symposia this autumn, Recent IAEA publications, Atoms for animal health and productivity, Studying the past to learn about the future, Nuclear power status around the world, and other short information

  7. Physics in a spin. CERN Courier, Apr 1987, v. 27(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1987-04-15

    The biennial international high energy spin physics meetings (Lausanne, 1980; Brookhaven, 1982; Marseille, 1984) provide a useful focus of attention for the enthusiastic community of followers of a sector of physics rarely lacking in interest and where the unexpected is increasingly expected.

  8. Security communication systems for nuclear fixed site facilities. Technical report Jan 77-Apr 80

    International Nuclear Information System (INIS)

    Howington, L.C.; Taylor, L.L.

    1980-07-01

    This report presents a basic discussion of communication techniques and factors relevant to designing communication systems for nuclear fixed site facility security systems. The reader is provided communication fundamentals, design considerations, and specification techniques. Copious references and an annotated bibliography are provided for individuals who desire to delve deeper than the limits and areas of study of this report. Ease of reading and use of this report are enhanced by relegating detailed communication design treatise to the Appendices. Sample procurement specifications are provided throughout the report for various communication system components and are distinguished from the regular text by using a smaller type

  9. The high latitude heliosphere. Proceedings. 28. ESLAB Symposium, Friedrichshafen (Germany), 19 - 21 Apr 1994.

    Science.gov (United States)

    Marsden, R. G.

    1995-04-01

    The following topics were dealt with: high latitude heliosphere, Ulysses mission, corona, spectra, coronal holes, composition, solar wind, He, plasma, streams, interplanetary magnetic field, plasma waves, radio bursts, energetic particles, cosmic rays, and interstellar gas.

  10. People and things. CERN Courier, Mar-Apr 1995, v. 35(2)

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: Khosrow Chadan, former director of Orsay's Laboratoire de Physique théorique et particules élémentaires has been nominated Chevalier of the Legion of Honour. R. Vinh Mau, main author of the 'Paris' nucleon-nucleon potential, has been nominated and promoted Officer of the French Ordre du Mérite. Tom Roser is Head of the Accelerator Division in the Alternating Gradient Synchrotron Department at Brookhaven, succeeding Bill Weng. We apologize for the unfortunate misprint in the December issue, page 27. Academician Moisei Alexandrovich Markov died on 1 October. Although basically a theorist, he made major contributions to the development and infrastructure of Russian experimental physics. After graduating from Moscow in 1930, he went on to join the new Lebedev Institute. His initial interests were in the problem of infinities in quantum field theory, carrying out pioneer work on the idea of nonlocality, a regular theme during his career. In the 1960s he turned to fundamental questions at the interface between particle physics and cosmology. With the advent of major accelerators in the post-war period, he was a staunch promoter of experiments at these machines, first for the Lebedev electron machine, and subsequently for the Dubna proton synchrotron. After milestone contributions to the study of weak interactions, he stressed the importance of underground or underwater detectors for cosmic rays and neutrinos, leading to the establishment of the Baksan neutrino observatory. From 1967-88, as head of the Nuclear Physics Department of the Academy of Sciences, he oversaw the establishment of major new projects, including the Moscow meson factory as well as Baksan, while continually providing new stimulation for the research community. For many years he was the USSR representative in the Pugwash movement which provided a useful international forum during a difficult period

  11. The Erika tanker shipwreck, one year later. synthesis; Naufrage du petrolier Erika, un an apres. synthese

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    In december 1999 the Erika tanker shipwreck broke along the Brittany coast leading to the most important sea pollution by hydrocarbons, since the Amoco-Cadiz. One year after this accident the Ministry of the territory management and of the environment takes stock on the actions carried on after the shipwreck: the management of the POLMAR fund, the shoreline cleaning, the land and water ecosystems restoration, the wastes storage and processing, the ecological consequences. A special part is devoted to the maritime transport regulations and safety and to the victims compensation. (A.L.B.)

  12. Ultraviolet technology II; Proceedings of the Meeting, Orlando, FL, Apr. 4, 5, 1988

    International Nuclear Information System (INIS)

    Huffman, R.E.

    1988-01-01

    The conference presents papers on the chemical analysis of UV rocket plume signatures, the determination of daytime midlatitude electron density profiles from satellite UV and in-situ data, and the application of CCD detectors to UV imaging from a spinning satellite. Other topics include a middle atmosphere high-resolution spectrograph, very large format pulse-counting UV detectors, optical filters for high-resolution UV imaging systems, and synthetic dayglow spectra and the Rayleigh scattering background from the FUV to the visible. Consideration is also given to image motion compensation using a photon-counting UV/visible detector, UV/ozone removal of contaminants in spacecraft environments, and decoding techniques for fine-fine geometry multianode microchannel arrays

  13. LHC Beam Splash seen by the ATLAS detector - 5 Apr 2015 - run 260272 - event 6539

    CERN Multimedia

    ATLAS Collaboration

    2015-01-01

    Event display of one of the collimator "splash" events seen by the ATLAS experiment in LHC Run-2, on Tuesday April the 5th : run 260272, event 6539 . The collimator position is 140m in front of the ATLAS interaction point.

  14. La formule des traces tordue d’après le Friday Morning Seminar

    CERN Document Server

    Labesse, Jean-Pierre

    2013-01-01

    La formule des traces pour un groupe réductif connexe arbitraire est due à James Arthur. Le cas tordu a fait l'objet du Friday Morning Seminar à l'Institute for Advanced Study de Princeton pendant l'année académique 1983-1984. Lors de ce séminaire, des exposés ont été présentés par Laurent Clozel, Jean-Pierre Labesse et Robert Langlands. Les notes de ces exposés, rédigées dans l'urgence, avaient besoin d'être revues et complétées. L'ambition des auteurs du présent ouvrage est de donner, en s'appuyant sur ces notes, une preuve complète pour la formule des traces tordue, dans sa version primitive i.e. sa forme non invariante. Ceci est la première étape du projet de l'équipe parisienne animée par Laurent Clozel et Jean-Loup Waldspurger, dont le but est de donner une preuve complète de la stabilisation de la formule des traces tordue, qui est l'outil fondamental utilisé par J. Arthur dans son livre à paraître sur l'endoscopie tordue pour le groupe linéaire avec application aux groupes ...

  15. People and things. CERN Courier, Apr 1990, v. 30(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1990-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: ; In a January 31 test at the Continuous Electron Beam Accelerator Facility (CEBAF) under construction at Newport News, Virginia, a beam from the injector's 500 keV room temperature section was accelerated to 2.5 MeV in one cavity of the quarter-cryomodule containing the injector's initial superconducting accelerating cavity pair. ; To explore in detail and update the physics possibilities for the Large Hadron Collider (LHC) project at CERN, the European Committee for Future Accelerators (ECFA) is now preparing for an LHC Workshop to be held in Aachen from 5-10 October. ; The 1990 CERN School of Computing, organized in collaboration with the Inter-University Institute for High Energies, VUB-ULB, Brussels, will take place from 2-15 September at Nieuwpoort, Belgium. ; To reinforce the increased spirit of cooperation resulting from CERN's growing attraction for scientists from all over Europe and from further afield, the Laboratory embarked last year on a programme of drawing up bilateral agreements to put ongoing collaboration on a firmer footing.

  16. Advances in optical structure systems; Proceedings of the Meeting, Orlando, FL, Apr. 16-19, 1990

    Science.gov (United States)

    Breakwell, John; Genberg, Victor L.; Krumweide, Gary C.

    Various papers on advances in optical structure systems are presented. Individual topics addressed include: beam pathlength optimization, thermal stress in glass/metal bond with PR 1578 adhesive, structural and optical properties for typical solid mirror shapes, parametric study of spinning polygon mirror deformations, simulation of small structures-optics-controls system, spatial PSDs of optical structures due to random vibration, mountings for a four-meter glass mirror, fast-steering mirrors in optical control systems, adaptive state estimation for control of flexible structures, surface control techniques for large segmented mirrors, two-time-scale control designs for large flexible structures, closed-loop dynamic shape control of a flexible beam. Also discussed are: inertially referenced pointing for body-fixed payloads, sensor blending line-of-sight stabilization, controls/optics/structures simulation development, transfer functions for piezoelectric control of a flexible beam, active control experiments for large-optics vibration alleviation, composite structures for a large-optical test bed, graphite/epoxy composite mirror for beam-steering applications, composite structures for optical-mirror applications, thin carbon-fiber prepregs for dimensionally critical structures.

  17. Thermosense XIII; Proceedings of the Meeting, Orlando, FL, Apr. 3-5, 1991

    Science.gov (United States)

    Baird, George S.

    The present conference on thermosensing technologies discusses topics in predictive maintenance, architectural and structural applications, product and processing applications, material diagnostics, and laboratory researches. Attention is given to IR thermography for pipeline leak detection, thermal analyses of masonry block buildings during construction, thermography for electronic component lifetime prediction, time-resolved videothermography, and vibrothermographic-thermoelastic NDE of advanced composites. Also discussed are pulse-video thermography, time-resolved IR radiometry, quantitative thermal gradient imaging, automated image processing of IR thermography, and algorithms for IR pyrometry.

  18. Data structures and target classification; Proceedings of the Meeting, Orlando, FL, Apr. 1, 2, 1991

    Science.gov (United States)

    Libby, Vibeke

    1991-08-01

    The present conference discusses topics in multisensor fusion and signal processing, data structures in distributed environments, computational methods and architectures, and automatic target recognition. Attention is given to the adaptive selection of sensors, multisensor imagery fusion based on target motion, multisensor imaging technology for airborne surveillance, optimal topology communications networks, scanning strategies for target detection, VLSI fuzzy-logic controller design, an optical pattern recognizer, radar-based target recognition techniques, and algorithms for radar clutter statistical classification.

  19. Acquisition, tracking, and pointing; Proceedings of the Meeting, Orlando, FL, Apr. 3, 4, 1986

    Science.gov (United States)

    Auelmann, Richard R. (Editor); Richard, Herbert L. (Editor)

    1987-01-01

    The present conference discusses the effect of target signatures on active tracking, the high resolution obtainable with a two-degrees-of-freedom angle sensor having a high update rate, solar object tracking for the Hubble Space Telescope, scaled experiments for the assessment of precise active tracking, and large aperture high-accuracy satellite laser tracking. Also discussed are laboratory test results for the Spaceborne Geodynamic Ranging System's high speed optical tracking system, jitter stabilization for precise optical pointing, scan stabilization and jitter control for an airborne telescope, a simulation of the Solar Optical Telescope's pointing performance, a microprocessor-based dual-speed angle converter, and image localization for alignment by means of adaptive preprocessing.

  20. Grazing incidence optics; Proceedings of the Meeting, Orlando, FL, Apr. 3, 4, 1986

    Science.gov (United States)

    Osantowski, John F. (Editor); Van Speybroeck, Leon (Editor)

    1986-01-01

    Papers are presented on the diffraction-limited performance of grazing incidence optical systems; transverse ray aberrations of Wolter type 1 telescopes; hybrid X-ray telescope systems; surface characterization of grazing incidence optics in the extreme UV and X-ray regions; and the surface roughness properties of synchrotron radiation optics. Topics discussed include the simulation of free-abrasive grinding of grazing incidence mirrors with vertical-honing and flexible blades; mirrors for the Extreme Ultraviolet Explorer; the design and development of conical X-ray imaging mirrors; thermal loading considerations for synchrotron radiation mirrors; and grazing incidence optics for synchrotron radiation insertion-device beams. Consideration is given to the interpretation of glancing incidence scattering measurements; damage processes in short wavelength coated FEL optics; the replication of grain incidence optics; and the assembly and alignment of the Technology Mirror Assembly.

  1. Infrared detectors and arrays; Proceedings of the Meeting, Orlando, FL, Apr. 6, 7, 1988

    International Nuclear Information System (INIS)

    Dereniak, E.L.

    1988-01-01

    The papers contained in this volume provide an overview of recent advances in theoretical and experimental research related to IR detector materials and arrays. The major subject areas covered include IR Schottky barrier silicide arrays, HdCdTe developments, SPRITE technology, superlattice or bandgap-engineered devices, extrinsic silicon technology, indium antimonide technology, and pyroelectric arrays. Papers are presented on time division multiplexed time delay integration, spatial noise in staring IR focal plane arrays, pyroelectrics in a harsh environment, and testing of focal plane arrays

  2. Remote sensing of the biosphere; Proceedings of the Meeting, Orlando, FL, Apr. 19, 20, 1990

    Science.gov (United States)

    Smith, James A. (Editor)

    1990-01-01

    The global context and monitoring of the biological aspects relevant to the EOS program are addressed, the large-scale regional field experiments required to understand ecosystem functioning in more detail and to calibrate the application of remote-sensing techniques for extracting flux and state information are covered, and sensors of the proposed EOS platform are discussed. Attention is given to terrestrial productivity, both tropical-forest and semiarid environments, coastal environments, and global oceanic productivity. Focus is placed on the First International Field Experiment (FIFE) in Kansas, the HAPEX field experiment in France, the ABLE-2 experiment in the Amazon, and the Forest Ecosystem Study in Maine. The proposed electro-optical instruments for EOS including both MODIS-N and MODIS-T, the AIRS and MISR instruments, the ITIR, and ERBE calibration issues are considered.

  3. Visual information processing; Proceedings of the Meeting, Orlando, FL, Apr. 20-22, 1992

    Science.gov (United States)

    Huck, Friedrich O. (Editor); Juday, Richard D. (Editor)

    1992-01-01

    Topics discussed in these proceedings include nonlinear processing and communications; feature extraction and recognition; image gathering, interpolation, and restoration; image coding; and wavelet transform. Papers are presented on noise reduction for signals from nonlinear systems; driving nonlinear systems with chaotic signals; edge detection and image segmentation of space scenes using fractal analyses; a vision system for telerobotic operation; a fidelity analysis of image gathering, interpolation, and restoration; restoration of images degraded by motion; and information, entropy, and fidelity in visual communication. Attention is also given to image coding methods and their assessment, hybrid JPEG/recursive block coding of images, modified wavelets that accommodate causality, modified wavelet transform for unbiased frequency representation, and continuous wavelet transform of one-dimensional signals by Fourier filtering.

  4. Infrared readout electronics; Proceedings of the Meeting, Orlando, FL, Apr. 21, 22, 1992

    Science.gov (United States)

    Fossum, Eric R.

    The present volume on IR readout electronics discusses cryogenic readout using silicon devices, cryogenic readout using III-V and LTS devices, multiplexers for higher temperatures, and focal-plane signal processing electronics. Attention is given to the optimization of cryogenic CMOS processes for sub-10-K applications, cryogenic measurements of aerojet GaAs n-JFETs, inP-based heterostructure device technology for ultracold readout applications, and a three-terminal semiconductor-superconductor transimpedance amplifier. Topics addressed include unfulfilled needs in IR astronomy focal-plane readout electronics, IR readout integrated circuit technology for tactical missile systems, and radiation-hardened 10-bit A/D for FPA signal processing. Also discussed are the implementation of a noise reduction circuit for spaceflight IR spectrometers, a real-time processor for staring receivers, and a fiber-optic link design for INMOS transputers.

  5. Earth and atmospheric remote sensing; Proceedings of the Meeting, Orlando, FL, Apr. 2-4, 1991

    Science.gov (United States)

    Curran, Robert J. (Editor); Smith, James A. (Editor); Watson, Ken (Editor)

    1991-01-01

    The papers presented in this volume address the technical aspects of earth and atmospheric remote sensing. Topics discussed include spaceborne and ground-based applications of laser remote sensing, advanced applications of lasers in remote sensing, laser ranging applications, data analysis and systems for biospheric processes, measurements for biospheric processes, and remote sensing for geology and geophysics. Papers are presented on a space-qualified laser transmitter for lidar applications, solid state lasers for planetary exploration, automated band selection for multispectral meteorological applications, aerospace remote sensing of natural water organics, and remote sensing of volcanic ash hazards to aircraft.

  6. Controls for optical systems; Proceedings of the Meeting, Orlando, FL, Apr. 21, 22, 1992

    Science.gov (United States)

    Breakwell, John

    1992-07-01

    The present conference discusses the control and actuator design for a precision magnetic suspension linear bearing, image-rotation in plane-mirror optical systems, a linear analysis for optomechanical systems, the phasing of a space-based segmented sub-mm wavelength telescope using focal plane measurements, and a fiber-optic-based position sensor immune to temperature variations. Also discussed are the dynamic simulation of precision optical systems, active damping with a reaction-mass actuator, the status of a wide-field integrated beam-control demonstration, an integrated multidisciplinary analysis of segmented reflector telescopes, and spatial filters for shape control.

  7. Small-satellite technology and applications; Proceedings of the Meeting, Orlando, FL, Apr. 4, 5, 1991

    Science.gov (United States)

    Horais, Brian J.

    Remote sensing applications and systems, small satellites for sensing missions, and supporting technologies are the broad topics discussed. Particular papers are presented on small satellites for water cycle experiments, low-cost spacecraft buses for remote sensing applications, Webersat (a low-cost imaging satellite), DARPA initiatives in small-satellite technologies, a solid-state magnetic azimuth sensor for small satellites, and thermal analysis of a small expendable tether satellite package. (For individual items see A93-24152 to A93-24175)

  8. Atmospheric propagation and remote sensing; Proceedings of the Meeting, Orlando, FL, Apr. 21-23, 1992

    Science.gov (United States)

    Kohnle, Anton; Miller, Walter B.

    Topics addressed include modeling aerosol extinction in a coastal environment, a specific marine boundary layer aerosol model, light scattering of fractal aerosol aggregates using a T-matrix method, a lidar inversion technique using total attenuation and the lidar system constant, a comparison of two retrieval methods for ground reflectance, a two-wavelength lidar inversion technique, and conceptual design of a spaceborne radar for rain and cloud sensing. Also discussed are an energy balance model for imagery and electromagnetic propagation, short-exposure imaging of nonisoplanatic objects through turbulence, atmospheric modeling with an intent of training a neural net wavefront sensor, effect of random layers on atmospheric propagation, atmospheric effects on laser radar performance at 2 microns, the adjacency-blurring effect of scenes modeled by the radiosity method, atmospheric transmittance measurements of CO2 and near-IR laser radiation over 8.6 km, and a comparison of turbulence modulation transfer function (MTF) and aerosol MTF.

  9. Acquisition, tracking, and pointing IV; Proceedings of the Meeting, Orlando, FL, Apr. 19, 20, 1990

    Science.gov (United States)

    Gowrinathan, Sankaran

    1990-09-01

    Various papers on acquisition, tracking, and pointing are presented. Individual topics addressed include: backlash control techniques in geared servo mechanics; optical fiber and photodetector array for robotic seam tracking; star trackers for spacecraft applications; Starfire optical range tracking system for the 1.5 m telescope; real-time video image centroid tracker; optical alignment with a beamwalk system; line-of-sight stabilization requirements for target tracking system; image quality with narrow beam illumination in an active tracking system; IR sensor data fusion for target detection, identification, and tracking; target location and pointing algorithm for a three-axis stabilized line scanner. Also discussed are: adaptive control system techniques applied to inertial stabilization systems; supervisory control of electrooptic tracking and pointing; position loop compensation for flex-pivot-mounted gimbal stabilization systems; advanced testing methods for acquisition, tracking, and pointing; development of kinmatics for gimballed mirror systems.

  10. Small satellite technologies and applications II; Proceedings of the Meeting, Orlando, FL, Apr. 21, 22, 1992

    Science.gov (United States)

    Horais, Brian J.

    The present conference on small satellite (SS) systems and their supporting technologies discusses the Medsat SS for malaria early warning and control, results of the Uosat earth-imaging system, commercial applications for MSSs, an SS family for LEO communications, videosignal signature-synthesis for fast narrow-bandwidth transmission, and NiH battery applications in SSs. Also discussed are the 'PegaStar' spacecraft concept for remote sensing, dual-cone scanning earth sensor processing algorithms, SS radiation-budget instrumentation, SDI's relevance to SSs, spacecraft fabrication and test integration, and cryocooler producibility. (For individual items see A93-28077 to A93-28100)

  11. Remote sensing; Proceedings of the Meeting, Orlando, FL, Apr. 3, 4, 1986

    Science.gov (United States)

    Menzies, Robert T. (Editor)

    1986-01-01

    Advances in optical technology for remote sensing are discussed in reviews and reports of recent experimental investigations. Topics examined include industrial applications, laser diagnostics for combustion research, laser remote sensing for ranging and altimetry, and imaging systems for terrestrial remote sensing from space. Consideration is given to LIF in forensic diagnostics, time-resolved laser-induced-breakdown spectrometry for rapid analysis of alloys, CARS in practical combustion environments, airborne inertial surveying using laser tracking and profiling techniques, earth-resources instrumentation for the EOS polar platform of the Space Station, and the SAR for EOS.

  12. Acquisition, tracking, and pointing V; Proceedings of the Meeting, Orlando, FL, Apr. 3-5, 1991

    Science.gov (United States)

    Masten, Michael K.; Stockum, Larry A.

    1991-08-01

    The present conference discusses the Starlab control system, an angular positioning mechanism for a UV coronagraph spectrometer, a second-generation laser tracking system, the optimization of a gimbal-scanned IR seeker, design considerations for an airborne electrooptic sensor, the effects of atmospheric turbulence on a relay mirror experiment, and the sensor fusion approach to optimization for human perception. Also discussed are target detection with a co-occurrence matrix segmentation, imaging autotracker technology for guided missile systems, a fuzzy logic approach to multitarget tracking in clutter, salient contour extraction for target recognition, accelerometer-based platform stabilization, a low-drift fiber-optic gyro for earth-rate applications, and velocity profiling in linear and rotational systems. (No individual items are abstracted in this volume)

  13. Design of optical instruments; Proceedings of the Meeting, Orlando, FL, Apr. 22-24, 1992

    Science.gov (United States)

    Aikens, David M.; Genberg, Victor L.; Krumweide, Gary C.; Thomas, Michael J.

    1992-09-01

    Topics discussed in this volume include optical system design, recent application of composite materials to precision optical instrument structure, development of composite mirrors and reflectos, development of composite materials for dimensionally stable structures, and structural mechanics. Papers are presented on adjustable distortion correctors, the optical design for the ATLAS multispectral scanner, an internal thermal emission analysis of an IR seeker, recent developments with the Mars Observer Camera graphite/epoxy structure, and moisture effects and control for the Ultraviolet Coronagraph Spectrograph composite structure. Attention is also given to composite materials for precision space reflector panels, the structural design and analysis for an ultralow-CTE optical bench for the Hubbale Space Telescope corrective optics, the evaluation of high-modulus pitch/cyanate material systems for dimensionally stable structures, weight minimization of an active mirror, and a compliant optical mount design. (For individual items see A93-29782 to A93-29798)

  14. Hybrid image and signal processing III; Proceedings of the Meeting, Orlando, FL, Apr. 23, 24, 1992

    Science.gov (United States)

    Casasent, David P.; Tescher, Andrew G.

    1992-07-01

    The present conference discusses the optical Gabor and wavelet transforms for image analysis, image segmentation via optical wavelets, semidifferential invariants, object labeling via convolution, tactile pattern recognition with complex linear morphology, a hybrid six-degree-of-freedom tracking system, and a hazard detection/avoidance sensor for NASA planetary landers. Also discussed are layered optical processing architectures, optoelectronic wide-world personality ROMs for high-speed control, a GaAs-based photorefractive time-integrating correlator, multispectral lossy data compression using vector quantization, broad vector quantization for transform image coding, and a mixed vendor computer architecture for precision image analysis. (For individual items see A93-27933 to A93-27940)

  15. Imaging spectroscopy of the terrestrial environment; Proceedings of the Meeting, Orlando, FL, Apr. 16, 17, 1990

    Science.gov (United States)

    Vane, Gregg

    1990-09-01

    Topics presented include the evolution of the Airborne Visible/Infrared Imaging Spectrometer flight and ground data processing system, direct mineral identification with Geoscan Mk II Advanced Multispectral Scanner, a new approach to imaging spectroscopy, and a linear-wedge spectrometer. Also presented are the effects of moisture content and chemical composition on the near-infrared spectra of forest foliage, change detection in vegetation using 1989 AVIRIS data, and the inversion of high-spectral-resolution data.

  16. Sensors and sensor integration; Proceedings of the Meeting, Orlando, FL, Apr. 4, 1991

    Science.gov (United States)

    Dean, Peter D.

    Consideration is given to adaptive control of propellant slosh for launch vehicles, a lidar for expendable launch vehicles, a high-resolution airborne multisensor system, an optical velocity sensor for air data applications, and use of absorption spectroscopy for refined petroleum product discrimination. Attention is also given to edge effects in silicon photodiode arrays, sensing and environment perception for a mobile vehicle, distributed-effect optical fiber sensors for trusses and plates, and instrumentation concepts for multiplexed Bragg grating sensors. (For individual items see A93-21962 to A93-21972)

  17. Remote sensing of atmospheric chemistry; Proceedings of the Meeting, Orlando, FL, Apr. 1-3, 1991

    Science.gov (United States)

    McElroy, James L.; McNeal, Robert J.

    The present volume on remote sensing of atmospheric chemistry discusses special remote sensing space observations and field experiments to study chemical change in the atmosphere, network monitoring for detection of stratospheric chemical change, stratospheric chemistry studies, and the combining of model, in situ, and remote sensing in atmospheric chemistry. Attention is given to the measurement of tropospheric carbon monoxide using gas filter radiometers, long-path differential absorption measurements of tropospheric molecules, air quality monitoring with the differential optical absorption spectrometer, and a characterization of tropospheric methane through space-based remote sensing. Topics addressed include microwave limb sounder experiments for UARS and EOS, an overview of the spectroscopy of the atmosphere using an FIR emission experiment, the detection of stratospheric ozone trends by ground-based microwave observations, and a FIR Fabry-Perot spectrometer for OH measurements. (For individual items see A93-31377 to A93-31412)

  18. Surveillance technologies II; Proceedings of the Meeting, Orlando, FL, Apr. 21-23, 1992

    Science.gov (United States)

    Gowrinathan, Sankaran; Shanley, James F.

    1992-08-01

    Topics addressed include sensor systems and algorithm development; detectors, focal planes, and components; law enforcement technologies; airborne/tactical surveillance sensors; stable optics for geostationary remote sensors; and spaceborne surveillance. Particular attention is given to near-ultraviolet/near-infrared image mixing, ocean topography experiment star tracker performance data, a programmable timing generator for focal plane array testing and operation, a PC-based focal plane evaluation system, augmentation of image resolution for law enforcement, an integrated geophysical approach to the detection of buried objects and clandestine tunnels, the signal attenuation dependence on a segmented window structure, thermal design and performance of the visible ultraviolet experiment sensor, dimensionally stable graphite-fiber-reinforced composite mirror technology, modeling the effects of IR subpixel nonuniformities on sensor performance, and a global vision electrooptical system. (For individual items see A93-29981 to A93-29996)

  19. Infrared detectors and focal plane arrays; Proceedings of the Meeting, Orlando, FL, Apr. 18, 19, 1990

    Science.gov (United States)

    Dereniak, Eustace L.; Sampson, Robert E.

    1990-09-01

    The papers contained in this volume provide an overview of recent advances and the current state of developments in the field of infrared detectors and focal plane arrays. Topics discussed include nickel silicide Schottky-barrier detectors for short-wavelength infrared applications; high performance PtSi linear and focal plane arrays; and multispectral band Schottky-barrier IRSSD for remote-sensing applications. Papers are also presented on the performance of an Insi hybrid focal array; characterization of IR focal plane test stations; GaAs CCD readout for engineered bandgap detectors; and fire detection system for aircraft cargo bays.

  20. Optical pattern recognition III; Proceedings of the Meeting, Orlando, FL, Apr. 21, 22, 1992

    Science.gov (United States)

    Casasent, David P. (Editor); Chao, Tien-Hsin (Editor)

    1992-01-01

    Consideration is given to transitioning of optical processing into systems (TOPS), optical correlator hardware, phase-only optical correlation filters, optical distortion-invariant correlation filters, and optical neural networks. Particular attention is given to a test target for optical correlators, a TOPS electronic warfare channelizer program, a portable video-rate optical correlator, a joint transform correlator employing electron trapping materials, a novelty filtered optical correlator using a photorefractive crystal, a comparison of correlation performance of smart ternary phase-amplitude filters with gray-scale and binary input scenes, real-time distortion-tolerant composite filters for automatic target identification, landscaping the correlation surface, fast designing of a circular harmonic filter using simulated annealing, feature-based correlation filters for distortion invariance, automatic target recognition using a feature-based optical neural network, and a holographic inner-product processor for pattern recognition.

  1. Structures sensing and control; Proceedings of the Meeting, Orlando, FL, Apr. 2, 3, 1991

    Science.gov (United States)

    Breakwell, John; Varadan, Vijay K.

    Papers are presented on smart skins and structures and on controls for optical systems. Particular attention is given to polyimide-coated embedded optical fiber sensors, a comparison of analog and digital strategies for automatic vibration control of lightweight space structures, high-bandwidth control for low-area-density deformable mirrors, and optimal control/structure integrated design of a flexible space platform with articulated appendages. (For individual items see A93-22002 to A93-22025)

  2. Surveillance technologies; Proceedings of the Meeting, Orlando, FL, Apr. 2-5, 1991

    Science.gov (United States)

    Gowrinathan, Sankaran; Mataloni, Raymond J., Sr.; Schwartz, Stanley J.

    The present conference discusses a CCD for a space telescope imaging spectrograph, a space-based surveillance experiment, a signal processor for space-based visible sensing, space-based sensing of atmospheric conditions over data-void regions, a highly compact imaging Fourier transform spectrometer, optical filters for a wind imaging interferometer, and a graphical interface for multispectral simulation. Also discussed are an error analysis for stereo-optical-flow passive ranging, low-cost space platforms for detection and tracking technologies, a high performance InSb IR camera, U.S. fisheries remote sensing requirements, remote spectral fingerprinting, and data-fusion systems for the U.S. Customs Service. (For individual items see A93-27713 to A93-27716)

  3. People and things. CERN Courier, Apr-May 1995, v. 35(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1995-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: Spokesmen at the CDF experiment at Fermilab's tevatron protonantiproton collider serve two-year terms. Most recently Mel Shochet (Chicago) and Bill Carithers ( LBL ) were co-spokesmen. Before the recent round of elections, Mel declared that he did not want to run again, having served for six and a half years (following the departure of Roy Schwitters to the SSC). Bill Carithers (who replaced Alvin Tollestrup two years ago) did decide to run again. Through a complicated process, a long list of nominees was narrowed to six candidates and an election held via the World Wide Web. Results were announced on January 19: Bill Carithers was reelected for another term, and Giorgio Bellettini (Pisa) becomes his new cospokesman. (see Top discovery' - page 1). Career milestone - Lucien Montanet: Officially 'retiring' from CERN is Lucien Montanet, whose impressive career spans a wide range of physics interests and is characterized by his ebullient enthusiasm. Joining CERN in 1957 for cosmic ray experiments, he went on to participate in pioneer CERN investigations using bubble chambers and using antiprotons, going on in the 1960s to play a prominent role in the discovery and investigation of hadron resonances, and becoming a key figure in the international Particle Data Group. His objective review talks on the complex hadron resonance scene became a feature at international meetings. In the 1970s he pushed the development of the European Hybrid Spectrometer project and went on to join the L3 and Crystal Barrel collaborations at LEP and LEAR respectively. As well as experimental physics, he has also contributed to theoretical work (with Francis Low) and phenomenology (with Leon van Hove). In 1985 he became the CERN-Russia coordinator, a demanding responsibility now inherited by Jim Allaby as coordinator of CERN Non-Member State affairs.

  4. Development of an improved installation procedure and schedule of RVI modularization for APR1400

    International Nuclear Information System (INIS)

    Ko, Do Young

    2011-01-01

    The construction technology for reactor vessel internals (RVI) modularization is one of the most important factors to be considered in reducing the construction period of nuclear power plants. For RVI modularization, gaps between the reactor vessel (RV) core-stabilizing lug and the core support barrel (CSB) snubber lug must be measured using a remote method from outside the RV. In order to measure RVI gaps remotely at nuclear power plant construction sites, certain core technologies must be developed and verified. These include a remote measurement system to measure the gaps between the RV core-stabilizing lug and the CSB snubber lug, an RVI mockup to perform the gap measurement tests, and a new procedure and schedule for RVI installation. A remote measurement system was developed previously, and a gap measurement test was completed successfully using the RVI mockup. We also developed a new procedure and schedule for RVI installation. This paper presents the new and improved installation procedure and schedule for RVI modularization. These are expected to become core technologies that will allow us to shorten the construction period by a minimum of two months compared to the existing installation procedure and schedule

  5. People and things. CERN Courier, Apr 1987, v. 27(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1987-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. On Friday February 13, bulldozers began clearing a 200 acre (80 hectare) site at Newport News, Virginia, for the proposed US Continuous Electron Beam Accelerator Facility (CEBAF) to provide high energy electron beams for nuclear physics. The XI International Workshop on Weak Interactions will be held in Santa Fe, New Mexico, from 14- 19 June. Discussion sessions covering current topics in weak interaction physics will allow active participation by workshop attendees. The Division of Particles and Fields of the American Physical Society and the Central Design Group of the proposed US SSC Superconducting Supercollider are organizing a Workshop on Experiments, Detectors and Experimental Areas for the SSC, to be held at Berkeley from 7-17 July. As southern hemisphere astronomers witnessed a gigantic supernova explosion towards the end of February, underground neutrino detectors all over the world picked up bursts of particles.

  6. Mathematical aspects of vortex dynamics; Proceedings of the Workshop, Leesburg, VA, Apr. 25-27, 1988

    International Nuclear Information System (INIS)

    Caflisch, R.E.

    1989-01-01

    Various papers on the mathematical aspects of vortex dynamics are presented. Individual topics addressed include: mathematical analysis of vortex dynamics, improved vortex methods for three-dimensional flows, the relation between thin vortex layer and vortex sheets, computations of broadband instabilities in a class of closed-streamline flows, vortex-sheet dynamics and hyperfunction theory, free surface vortex method with weak viscous effects, iterative method for computing steady vortex flow systems, invariant measures for the two-dimensional Euler flow, similarity flows containing two-branched vortex sheets, strain-induced vortex stripping, convergence of the vortex method for vortex sheets, boundary conditions and deterministic vortex methods for the Navier-Stokes equations, vorticity creation boundary conditions, vortex dynamics of stratified flows, vortex breakdown, numerical studies of vortex reconnection, vortex lattices in theory and practice, dynamics of vortex structures in the wall region of a turbulent boundary layer, and energy of a vortex lattice configuration

  7. System Function Evaluation due to Hardware Failure of NSSS Control Systems in the APR1400

    International Nuclear Information System (INIS)

    Kim, Juyoung; Ahn, Myunghoon; Kim, Woogoon; Yim, Hyeongsoon

    2016-01-01

    As the performance and failure modes of the control systems may affect the plant response to accidents or disturbances, an evaluation is done to identify potential control system failure modes resulting from single hardware failures. These failure modes are for use in the analytical evaluations that will be performed to assess the plant responses to various disturbances from the viewpoint of postulated system malfunctions. Failure modes that fall into any of the above categories will affect the performance of the control system and should be considered in the analytical evaluation of the NSSS responses to disturbances. An evaluation was performed to identify the failure modes of the NSSS Control Systems, caused by a hardware component, a common sensing device, and a common power supply. The multiple failure modes across the NSSS control Systems are limited by the improved design features, redundancy within each systems, and segmentation between systems. Also, the effects from the failure modes are expected to be acceptably terminated by the Plant Protection System. The failure modes derived through this evaluation will be further considered in the analytical evaluation of the NSSS responses to disturbances in order to identify the single failures which could create the most adverse conditions during a given transient

  8. Evolution du front wuotidien du dessechemet des sols apres une pluie

    African Journals Online (AJOL)

    Farm machinery cost is among the most important factors that influence increases in crop production. Therefore, it is essential to discriminate those that are really needed, instead of choosing just by chance. Unfortunately, data needed to determine the really needed machines such as the available time for field operations in ...

  9. Atmospheric processes in reaction of Northern Sumatra Earthquake sequence Dec 2004-Apr 2005

    Science.gov (United States)

    Ouzounov, D.; Pulinets, S.; Cervone, G.; Singh, R.; Taylor, P.

    2005-05-01

    This work describes our first results in analyzing data from different and independent sources ûemitted long-wavelength radiation (OLR), surface latent heat flux (SHLF) and GPS Total Electron Content (TEC) collected from ground based (GPS) and satellite TIR (thermal infra-red) data sources (NOAA/AVHRR, MODIS). We found atmosphere and ionosphere anomalies one week prior to both the Sumatra-Andaman Islands earthquake (Dec 26, 2004) and M 8.7 - Northern Sumatra, March 28, 2005. We analyzed 118 days of data from December 1, 2004 through April 1, 2005 for the area (0°-10°,north latitude and 90°-100° east longitude) which included 125 earthquakes with M>5.5. Recent analysis of the continuous OLR from the Earth surface indicates anomalous variations (on top of the atmosphere) prior to a number of medium to large earthquakes. In the case of M 9.0 - Sumatra-Andaman Islands event, compared to the reference fields for the months of December between 2001 and 2004, we found strongly OLR anomalous +80 W/m2 signals (two sigma) along the epicentral area on Dec 21, 2004 five days before the event. In the case of M8.7 March 28, 2005 anomalues signatures over the epicenter appears on March 26 is much weaker (only +20W/m2) and have a different topology. Anomalous values of SHLF associated with M9.0 - Sumatra-Andaman Islands were found on Dec 22, 2005 (SLHF +280Wm2) and less intensity on Mar 23, 2005 (SLHF +180Wm2). Ionospheric variations (GPS/TEC) associated with the Northern Sumatra events were determine by five Regional GPS network stations (COCO, BAKO, NTUS, HYDE and BAST2). For every station time series of the vertical TEC (VTEC) were computed together with correlation with the Dst index. On December 22, four days prior to the M9.0 quake GPS/TEC data reach the monthly maximum for COCO with minor DST activity. For the M 8.7-March 28 event, the increased values of GPS/TEC were observed during four days (March 22-25) in quiet geomagnetic background. Our results need additional validation and the could be explained within the framework of a model of Lithosphere-Atmosphere-Ionosphere coupling, supporting the hypothesis of a relationship between a thermodynamic processes produced by increasing tectonic stresses in the Earth's crust and attendant electro-chemical interactions between the crust and the atmosphere/ionosphere.

  10. Preliminary Evaluations of CSPACE for a Station Blackout Transient in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Lee, T. B.; Lee, D. K.; Lee, H. S.; Lee, G. W.; Choi, T. S. [KEPCO, Daejeon (Korea, Republic of); Park, R. J.; Kim, D. H. [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    This paper discusses the preliminary results of the simulated station blackout (SBO) transients using the CSPACE code and presents the information pertinent to the related safety issues. CSPACE is a merged program of a master processer of Safety and Performance Analysis Code (SPACE) for nuclear power plants and a child processer of Core Meltdown Progression Accident Simulation Software (COMPASS) generated as a dynamic-link library (DLL) codes. It has been developed to predict the best-estimate transient in the pressurized water reactor (PWR) for severe accidents. SPACE and COMPASS codes take charge of the thermal-hydraulic response of PWRs and the analysis of the severe accident progression in a vessel, respectively. The initial phase is estimated starting from time zero when the loss of off-site and on-site powers occurs simultaneously. Shortly after the RCS pressure initially falls and rises slightly due to the effects of the reactor and turbine trips, the RCS pressure declines in response to the cooling provided by heat removed to the SGs. During the period of the primary heat-up and boil-off, the RCS pressure increase is limited by two cycles of the POSRV. The RCS fluid mass is lost through the pressurizer POSRV and then the core uncovers and superheated steam flows out from the RV into the coolant loops starting at 5513.0 seconds.

  11. Special routing of spent fuel shipments. Final report Dec 79-Apr 81

    International Nuclear Information System (INIS)

    Berkowitz, R.L.; Shaver, D.K.; Rudd, T.J.

    1982-05-01

    Special rail routing of spent fuel shipments from commercial nuclear power plants to Away-From-Reactor (AFR) storage and disposal sites has been proposed as one means of reducing the consequences and severity of radioactive materials accidents in areas of high population density. Whether or not special rail routing of spent fuel shipments does indeed decrease radiation exposure levels under normal and accident transportation conditions and at what incremental cost forms the basis of this study funded by the Federal Railroad Administration. The study is divided into five areas: (1) developing analytical models for assessing the risks associated with both the normal and accident transport modes; (2) selecting representative origin to destination routing pairs using the normal transportation and accident risk models; (3) analyzing rail shipment costs for nuclear spent fuel; and (4) performing sensitivity analyses to identify parameters that critically affect the total exposure level. The major findings resulting from this study are: (1) the risk over the seven example routes is relatively small for the normal transport mode; (2) the risk associated with an accident is at least an order of magnitude larger than the normal transport dose in all cases and as such is the overriding contribution to the total expected transport dose; and (3) no beneficial cost versus dose reduction relationship was found for any of the routes studied

  12. People and thing. CERN Courier, Apr 1989, v. 29(3)

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. Lake Shore Cryotronics of Ohio has been granted exclusive rights to market a technique developed at Los Alamos for measuring the quality of new high temperature superconductors. Home to the world's largest single application of superconductivity - the four-mile Tevatron ring - Fermilab has been granted a patent for a new cryogenic support system developed at the Laboratory providing high structural strength with excellent thermal properties. Hadron 89, the Third International Conference on Hadron Spectroscopy, to take place in Ajaccio, Corsica, France, from 23-27 September, will cover the important developments since Hadron 87 (KEK Japan) and look to the future

  13. People and things. CERN Courier, Apr 1984, v. 24(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1984-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. The CERN Accelerator School, in collaboration with the Orsay and Saclay Laboratories, is organizing a 'General Accelerator Physics' course at the Ecole Supérieure d'Electricité, Gif-sur-Yvette, France, from 3-14 September.The Scottish Universities Summer School in Physics will be held in St. Andrews from 12 August to 1 September. This is the twenty-seventh school in a series of NATO Advanced Study Institutes organized by the Scottish Universities.From 10-14 September, Geneva University will host the first of a planned biennial series of scientific lectures, sponsored by Dudley Wright. A Conference on the Intersections between Particle and Nuclear Physics' will be held from 23-30 May in Steamboat Springs, Colorado, USA. The meetings will focus on the physics interests of the many diverse groups who work in Particle and/or Nuclear Physics.

  14. People and thing. CERN Courier, Apr 1989, v. 29(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1989-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. Lake Shore Cryotronics of Ohio has been granted exclusive rights to market a technique developed at Los Alamos for measuring the quality of new high temperature superconductors. Home to the world's largest single application of superconductivity - the four-mile Tevatron ring - Fermilab has been granted a patent for a new cryogenic support system developed at the Laboratory providing high structural strength with excellent thermal properties. Hadron 89, the Third International Conference on Hadron Spectroscopy, to take place in Ajaccio, Corsica, France, from 23-27 September, will cover the important developments since Hadron 87 (KEK Japan) and look to the future.

  15. People and things. CERN Courier, Apr 1991, v. 31(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1991-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: ; In 1992 the XVth International Conference on High Energy Accelerators will be held from 20-24 July at the Congress Centrum, Hamburg, Germany. ; The 100 or so places for the CERN Accelerator School's 'Radiofrequency Engineering for Particle Accelerators' course in Oxford from 3-10 April were sold out well in advance. ; A Symposium on Quantum Physics, in memory of John Stewart Bell who died on 1 October 1990 will be held at CERN on 2-3 May.

  16. People and things. CERN Courier, Apr 1988, v. 28(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1988-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. The 5th Workshop on Nonlinear Evolution Equations and Dynamical Systems (NEEDS '89) will be held in Kolymbari, near Chania, Crete, from 2-19 July 1989. This year's DESY Theory Workshop ('Flavor Physics') will be held in Hamburg from 28-30 September. In conjunction with Daresbury Laboratory, the CERN Accelerator School is organizing a course on synchrotron radiation and free electron lasers in Chester, UK, from 6-12 April 1989. The topic for this year's SLAC Summer Institute is 'Probing the Weak Interaction: CP Violation and Rare Decays', The dates of the Institute are July 18th - 29th, 1988. The 1988 Summer Study on High Energy Physics in the 1990s will be held in Snowmass, Colorado, from 27 June to 15 July. The aim is to examine and evaluate the opportunities for high energy physics in the 1990s, including the possibilities with existing facilities, the proposed US Superconducting Super Collider (SSC), new accelerator technology, nonaccelerator experiments, special purpose facilities, and innovations in instrumentation and detector technology.

  17. People and things. CERN Courier, Apr 1987, v. 27(3)

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. On Friday February 13, bulldozers began clearing a 200 acre (80 hectare) site at Newport News, Virginia, for the proposed US Continuous Electron Beam Accelerator Facility (CEBAF) to provide high energy electron beams for nuclear physics. The XI International Workshop on Weak Interactions will be held in Santa Fe, New Mexico, from 14- 19 June. Discussion sessions covering current topics in weak interaction physics will allow active participation by workshop attendees. The Division of Particles and Fields of the American Physical Society and the Central Design Group of the proposed US SSC Superconducting Supercollider are organizing a Workshop on Experiments, Detectors and Experimental Areas for the SSC, to be held at Berkeley from 7-17 July. As southern hemisphere astronomers witnessed a gigantic supernova explosion towards the end of February, underground neutrino detectors all over the world picked up bursts of particles

  18. Qualite de vie apres un accident vasculaire cerebral au Senegal: a ...

    African Journals Online (AJOL)

    The accident was ischemic in 70% of cases, hemorrhagic in 30% of cases. 66% had a Barthel index between (60-100), 6% were between (0-20). The score was significantly better in young series (15-34), which all have a Barthel index between (60-100), more over 50% of patients in the portion above 75 years were in the ...

  19. People and things. CERN Courier, Apr 1985, v.25(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1985-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. To commemorate the 25th anniversary of Austria's joining CERN and the forming of the first high energy physics group in the country, a celebration took place last November in the Auditorium of the old University of Vienna. From 25-28 February next year, another (the fourth) Vienna Wire Chamber Conference will take place. The fifth US Summer School on High Energy Particle Accelerators is to be held at the Stanford Linear Accelerator Center from 15-26 July.

  20. SAJAA MarApr 40-4 Con.fh9

    African Journals Online (AJOL)

    Studio G5

    both ventilation and oxygenation became increasingly difficult. Close to completion of .... shifts as the patient changes position.57 These clinical signs may be difficult to elicit in .... to advance the safety of anaesthesia practice.87. References. 1.

  1. Intermetallic matrix composites; Proceedings of the MRS Symposium, San Francisco, CA, Apr. 18-20, 1990

    International Nuclear Information System (INIS)

    Anton, D.L.; Martin, P.L.; Miracle, D.B.; Mcmeeking, R.

    1990-01-01

    The present volume on intermetallic matrix composites discusses the modeling, processing, microstructure/property relationships, and compatibility of intermetallic matrix composites. Attention is given to models for the strength of ductile matrix composites, innovative processing techniques for intermetallic matrix composites, ductile phase toughening of brittle intermetallics, and reactive synthesis of NbAl3 matrix composites. Topics addressed include solidification processing of NbCr2 alloys, Ta and Nb reinforced MoSi2, the microstructure and mechanical behavior of Ni3Al-matrix composites, and ductile-phase toughening of Cr3Si with chromium. Also discussed are dislocation morphologies in TiB2/NiAl, the development of highly impact resistant NiAl matrix composites, the effect of notches on the fatigue life of the SCS-6Ti3Al composite, and the chemical stability of fiber-metal matrix composites

  2. Femmes cinéastes en France : l'après-mai 68

    OpenAIRE

    ROLLET, Brigitte

    2006-01-01

    Agnès Varda, Coline Serreau, Nelly Kaplan, trois noms parmi des dizaines qui illustrent chacun à leur manière une nouvelle façon de faire du cinéma : même si la carrière de la première est antérieure à mai 68, son nom comme celui des autres est lié à ce qu’on appellera dans les années 1970 le « cinéma des femmes ». Cet article propose une interrogation sur ce cinéma au féminin, afin d’envisager à la fois le contexte particulier dans lequel il émerge, les problématiques qu’il soulève, et ce en...

  3. Croatie: le tourisme avant et après la guerre

    Directory of Open Access Journals (Sweden)

    Snezana PROKIC

    1998-09-01

    Full Text Available Les conflits armés ont profondément modifié l'espace touristique croate. Par rapport à l'espace touristique de référence (avant 1991, l'article montre les changements dans les lieux, leur capacité d'accueil, la nature et l'ampleur de la fréquentation touristique, et identifie les logiques d'atteintes (spatiales et matérielles qui en modifient la structure.

  4. Pathfinder, v6 n2, Mar/Apr 2008. Strengthening NGA Partnerships Around the World

    Science.gov (United States)

    2008-04-01

    Office of International Affairs and Policy. What’s Next In fiscal year 2008, NGA plans to con- duct a gravity survey in an extremely remote and void...observer on Escudo de Veraguas Island. Perdue soon moved to Colombia as part of a team running a geodetic level line between Cali and Cartagena, walking

  5. Pathfinder, v6 n2, Mar/Apr 2008. Strengthening NGA Partnerships Around the World

    National Research Council Canada - National Science Library

    2008-01-01

    .... Several of the agency's foreign partnerships are explored in these pages. Clive Lines, Director of Australia's Defence Imagery and Geospatial Organisation, discusses several of the GEOINT benefits that our relationships provide. "Our Heritage...

  6. Advances in fatigue lifetime predictive techniques; Proceedings of the Symposium, San Francisco, CA, Apr. 24, 1990

    International Nuclear Information System (INIS)

    Mitchell, M.R.; Landgraf, R.W.

    1992-01-01

    Recent progress in the development of methods to predict fatigue performance of materials and structures is reviewed. Attention is given to general approaches to fatigue mechanics, elevated temperature phenomena, spectrum loading, the multiaxial behavior, and applications. Particular attention is given to a fracture-mechanics-based model for cumulative damage assessment, thermo-mechanical fatigue life prediction methods, a probabilistic fracture mechanics approach for structural reliability assessment of space flight systems, a multiaxial fatigue life estimation technique, plasticity and fatigue damage modeling of severely loaded tubing, damage evaluation in composite materials using thermographic stress analysis, and fatigue lifetime monitoring in power plants

  7. Reliability Centered Maintenance (RCM) Methodology and Application to the Shutdown Cooling System for APR-1400 Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Faragalla, Mohamed M.; Emmanuel, Efenji; Alhammadi, Ibrahim; Awwal, Arigi M.; Lee, Yong Kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    Shutdown Cooling System (SCS) is a safety-related system that is used in conjunction with the Main Steam and Main or Auxiliary Feedwater Systems to reduce the temperature of the Reactor Coolant System (RCS) in post shutdown periods from the hot shutdown operating temperature to the refueling temperature. In this paper RCM methodology is applied to (SCS). RCM analysis is performed based on evaluation of Failure Modes Effects and Criticality Analysis (FME and CA) on the component, system and plant. The Logic Tree Analysis (LTA) is used to determine the optimum maintenance tasks. The main objectives of RCM is the safety, preserve the System function, the cost-effective maintenance of the plant components and increase the reliability and availability value. The RCM methodology is useful for improving the equipment reliability by strengthening the management of equipment condition, and leads to a significant decrease in the number of periodical maintenance, extended maintenance cycle, longer useful life of equipment, and decrease in overall maintenance cost. It also focuses on the safety of the system by assigning criticality index to the various components and further selecting maintenance activities based on the risk of failure involved. Therefore, it can be said that RCM introduces a maintenance plan designed for maximum safety in an economical manner and making the system more reliable. For the SCP, increasing the number of condition monitoring tasks will improve the availability of the SCP. It is recommended to reduce the number of periodic maintenance activities.

  8. Dynamique de la côte apres la realisation des epis, ouvrages de ...

    African Journals Online (AJOL)

    The results showed that an average of 8.50 m/year before the completion of the headlands, the advancing sea has been a brake after implantation, causing significant accretion. This feeder is not always observed linearly each year. Downstream of the headland 7, the evaluation of the erosion rate of the coast line shows ...

  9. Space astronomical telescopes and instruments; Proceedings of the Meeting, Orlando, FL, Apr. 1-4, 1991

    Science.gov (United States)

    Bely, Pierre Y.; Breckinridge, James B.

    The present volume on space astronomical telescopes and instruments discusses lessons from the HST, telescopes on the moon, future space missions, and mirror fabrication and active control. Attention is given to the in-flight performance of the Goddard high-resolution spectrograph of the HST, the initial performance of the high-speed photometer, results from HST fine-guidance sensors, and reconstruction of the HST mirror figure from out-of-focus stellar images. Topics addressed include system concepts for a large UV/optical/IR telescope on the moon, optical design considerations for next-generation space and lunar telescopes, the implications of lunar dust for astronomical observatories, and lunar liquid-mirror telescopes. Also discussed are space design considerations for the Space Infrared Telescope Facility, the Hubble extrasolar planet interferometer, Si:Ga focal-plane arrays for satellite and ground-based telescopes, microchannel-plate detectors for space-based astronomy, and a method for making ultralight primary mirrors.

  10. Improvements in Logic Diagram of Computerized Procedure System of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Sungkweon; Seong, Nokyu [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The Computerized Procedure System (CPS) has been improved since it is installed in Shin-Kori 3 and 4 Nuclear Power Plants. It is one of operating support systems of digital Main Control Room (MCR) and provides many functions to operators in executing the procedure. CPS can effectively remove the human errors by supporting the procedure flow and logic diagram. This paper describes the logic diagram of CPS of reference power plant and shows the improved logic diagram of CPS of Shin-Kori unit 5 and 6. This paper describes the current logic diagram of CPS and suggests improved design for logic diagram. The improved logic diagram shall be validated through human factors engineering verification and validation. The improved design will help operators execute the computerized procedure fast and remove the human error.

  11. Les transitions énergétiques après les COP 21 et 22

    OpenAIRE

    Balibar , Sebastien

    2017-01-01

    International audience; How far are we in the urgent fight against the climate change? This article starts with a short analysis of the results of COP21 and COP22, the two “conferences of parties” where goals have been defined. Now, to define goals is one thing, but to reach these goals is another thing. In its second part, this article analyzes the energy transition that has been voted by France in 2015, and compares it to what is planned in other countries, especially in Germany.; Où en som...

  12. Drieledig personalisme : Ricoeur als personalist après-la-lettre

    NARCIS (Netherlands)

    Deweer, Dries

    2017-01-01

    The (continued) success of personalist philosophy in moral theology and politics is in stark contrast with the response within the field of philosophy itself. After a period of intense flowering between 1930-1950, a deafening silence soon descended. In this article, I will use Paul Ricoeur to guide

  13. Le syndrome de sevrage nicotinique après chirurgie cardiaque: à ...

    African Journals Online (AJOL)

    L'agitation post-opératoire constitue une pathologie extrêmement fréquente. Les étiologies à évoquer en réanimation sont nombreuses. Le syndrome de sevrage à la nicotine est une cause possible mais rarement évoquée. Nous rapportons le cas d'un patient tabagique qui a été admis en unité de soins intensifs pour un ...

  14. People and things. CERN Courier, Apr 1984, v. 24(3)

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. The CERN Accelerator School, in collaboration with the Orsay and Saclay Laboratories, is organizing a 'General Accelerator Physics' course at the Ecole Supérieure d'Electricité, Gif-sur-Yvette, France, from 3-14 September.The Scottish Universities Summer School in Physics will be held in St. Andrews from 12 August to 1 September. This is the twenty-seventh school in a series of NATO Advanced Study Institutes organized by the Scottish Universities.From 10-14 September, Geneva University will host the first of a planned biennial series of scientific lectures, sponsored by Dudley Wright. A Conference on the Intersections between Particle and Nuclear Physics' will be held from 23-30 May in Steamboat Springs, Colorado, USA. The meetings will focus on the physics interests of the many diverse groups who work in Particle and/or Nuclear Physics

  15. Conceptual Design of Condenser using PCM as PCCS for APR1400

    International Nuclear Information System (INIS)

    Jung, Hwa-Young; Ko, A-Reum; Lee, Jeong Ik; Yoon, Ho Joon

    2016-01-01

    In this study, the conceptual design of the condenser using the phase change material (PCM) is proposed as another PCCS concept for PWRs. It is possible to install the condenser for the existing nuclear power plants under operation without PCCS. Most of all, this condenser has to be designed to reduce the pressure and temperature in the containment until the containment spray system is available. A feature of the condenser as shown in Fig. 2 is the composition of PCM and wire mesh connected with the fins to improve heat transfer. As the first step, a preliminary study was conducted to find the optimum design of the part at which the condensation occurs under the given conditions. The results show that the fin base area as well as the total heat transfer area of fins are generally in inversely proportional to the average condensation heat transfer coefficient. Also, the point at which the gradient is changed is when the flow regime is changed from wavy flow to turbulent flow. However, the number of fins shows the different trend. Thus, in order to achieve better average condensation heat transfer coefficient under the identical heat capacity condition, the shorter the fin length and the more fins are necessary for the optimum design the condenser in wavy flow region

  16. Conceptual Design of Condenser using PCM as PCCS for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Hwa-Young; Ko, A-Reum; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [KUSTAR, Abu Dhabi (United Arab Emirates)

    2016-10-15

    In this study, the conceptual design of the condenser using the phase change material (PCM) is proposed as another PCCS concept for PWRs. It is possible to install the condenser for the existing nuclear power plants under operation without PCCS. Most of all, this condenser has to be designed to reduce the pressure and temperature in the containment until the containment spray system is available. A feature of the condenser as shown in Fig. 2 is the composition of PCM and wire mesh connected with the fins to improve heat transfer. As the first step, a preliminary study was conducted to find the optimum design of the part at which the condensation occurs under the given conditions. The results show that the fin base area as well as the total heat transfer area of fins are generally in inversely proportional to the average condensation heat transfer coefficient. Also, the point at which the gradient is changed is when the flow regime is changed from wavy flow to turbulent flow. However, the number of fins shows the different trend. Thus, in order to achieve better average condensation heat transfer coefficient under the identical heat capacity condition, the shorter the fin length and the more fins are necessary for the optimum design the condenser in wavy flow region.

  17. 16-APR-03 Final Release of ENDF/B-V for use with LLNL Codes

    International Nuclear Information System (INIS)

    Hill, T S; McNabb, D P; Hedstrom, G W; Beck, B; Hagmann, C A

    2003-01-01

    The new data files were prepared in two steps. First, the ENDF/B-V database was translated to an ENDL-format ascii database. The ENDL ascii format is a point-wise tabular storage scheme where intermediate values are extracted via interpolation. Sufficient point-wise information was generated in the translation to insure an extraction tolerance of 0.1% for most of the data. The only exception is along the incident neutron energy axis of the outgoing particle energy probability density function where a 0.5% tolerance was maintained. Second, processed files were generated from the translated database. Since the translated ENDF/B-V data is in ENDL-format, the standard processing codes were used to generate the new processed data files. To the best of our knowledge, these processed data files are accurate representations of the ENDF/B-V database to within the stated tolerances. However, there are several issues that users must be aware of and they are listed in this report

  18. People and things. CERN Courier, Apr 1985, v.25(3)

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. To commemorate the 25th anniversary of Austria's joining CERN and the forming of the first high energy physics group in the country, a celebration took place last November in the Auditorium of the old University of Vienna. From 25-28 February next year, another (the fourth) Vienna Wire Chamber Conference will take place. The fifth US Summer School on High Energy Particle Accelerators is to be held at the Stanford Linear Accelerator Center from 15-26 July

  19. Climate economics: post-Kyoto tracks; Economie du climat: pistes pour l'apres-Kyoto

    Energy Technology Data Exchange (ETDEWEB)

    Godard, Olivier; Ponssard, Jean-Pierre [Laboratoire d' Econometrie, Ecole Polytechnique, Route de Saclay, 91128 Palaiseau (France)

    2011-03-19

    Commitments obtained by the Kyoto protocol will end in 2012. An impressive series of conferences - Bali (2007), Copenhagen (2009), Cancun (2010) to mention the main ones - were organised to prepare the post-2012 regime. Everything was supposed to be decided at the Copenhagen meeting but the state representatives came up against the obstacle. The pre-Copenhagen hope has given place to disillusion and has led to a turn-off towards a weekly coordinated regime which requires a strategic revision of approaches. This book presents the lessons learnt from the relative failure of these negotiations and proposes new paths for the future. It puts forward some strategic stakes that have to be taken into account for the future: the equity between very heterogeneous countries and populations, the industrial competitiveness, the carbon leaks and the violation of the most ambitious climate policies due to the heterogeneity of commitment levels, and the geopolitical reality. The world will have to live for a long time with heterogeneous carbon prices, themselves reflecting heterogeneous commitment levels. New modalities have to be defined which would manage to combine justice and efficiency. Two complementary paths are developed in this book: the establishing of adjustment mechanisms at borders and of international sectoral agreements. (J.S.)

  20. ONRASIA Scientific Information Bulletin. Volume 17, Number 2, Apr-Jun 1992

    Science.gov (United States)

    1992-06-01

    tech- Dr. Masashi lizumi nology is now mature. The nuclear ship , Deputy Director General 0 Nuclear ship MUTSU , has been behind schedule Tokai Research...facility at the National Insti- side of the main (Honshu) island. Dr. Masayuki Akimoto tute of Standards and Technology Nuclear ship research occurs at...development of a new amorphous such as nuclear power plants, ships , oil reported in the next section of this (cobalt based?) metalwith much lower drilling

  1. Reconstruction après le tsunami dans un contexte de guerre | Page ...

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

    Le 26 décembre 2004, un tsunami a ravagé la majeure partie des régions côtières de la province d'Aceh, en Indonésie, ainsi que les côtes est et sud du Sri Lanka. La communauté internationale s'est mobilisée massivement pour secourir les populations en détresse et a acheminé une aide considérable aux zones ...

  2. Energie des particules émises après explosion coulombienne de l ...

    African Journals Online (AJOL)

    ةﺪﯾﺪﺷ ﺔﯿﻧﺎﺛﻮﺘﻤﻓ تارﺰﯿﻟ . Résumé. L'étude des clusters métalliques de Sodium (Na), contenant 5.103 atomes par agrégat, soumis à des champs laser femtosecondes intenses a conduit à une forte énergie d'excitation qui peut être l'origine des électrons de fortes énergies, des ions énergétiques de hautes charges ou des ...

  3. The Development of CPSES Plug-in(CPMP) for APR1400 Computerized Procedure Effective Maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Seong, No Kyu; Park, Jin Kyun; Jung, Yeon Sub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The Computerized Procedure System (CPS) is one of the Man Machine Interface (MMI) resources of the Shin-Kori 3 and 4 nuclear power plants. The CPS is a computerized operator support system that enables operating crew to execute procedures in an accurate and fast manner. The Computerized Procedure (CP) is the XML data file in executable format that can be installed in the Procedure eXecution System (PXS) for execution. The CP contains specific information related to a particular procedure (i.e. LOCA). These computerized procedures such as Alarm Response Procedures (ARP) are separated into individual alarm procedure to maximize function interface between CPS and DCS. E.g. 'Procedure open by alarm list'. The procedure writer's burden to manage many procedures has been increased because of separated procedures. This paper introduces Computerized Procedure System Engineering System (CPSES) plug-in that is computerized procedure management program (CPMP) to reduce procedure writer's burden. This paper introduces the main features of CPMP. CPMP reduces procedure writer's or CPX maintainer's burden. This program is implemented and tested by program design requirement.

  4. Assessment on Event Classification of One Steam Generator Tube Rupture in EU-APR

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

    The Fukushima Daiichi nuclear power plant accident showed the vulnerability of coping strategy to beyond design natural disaster such as beyond design earthquake and tsunami. In Korea, the government and industry performed comprehensive safety inspection on all domestic nuclear power plants against beyond design basis external events and fifty action items have been issued. In addition to post- Fukushima action items, the stress tests for all domestic nuclear power plants are on the way to enhance the safety of domestic nuclear power plants through finding the vulnerabilities in intentional stress conditions initiated by beyond design natural disaster. Recently, the stress tests for WOLSONG Unit 1 and KORI Unit 1 have been performed and their assessment results have been reviewed by Korean regulatory body. The assessment of the coping capability of KORI Unit 1 has been performed under simultaneous the extended loss of AC power and loss of ultimate heat sink initiated by beyond design natural disaster. It is concluded that KORI Unit 1 has the capability, in the event of loss of safety functions by beyond design natural disaster, to sufficiently cool down the reactor core without fuel damage, to keep pressure boundaries of the reactor coolant system in transient condition and to control containment and temperature to maintain the integrity of the containment buildings. The several additional items for safety improvement has been drawn to enhance the coping capability for loss of safety functions under beyond design natural disaster in addition to post Fukushima action items.

  5. Minimizing infarct size. Annual scientific report, 1 Jul 1975--15 Apr 1976

    International Nuclear Information System (INIS)

    Braunwald, E.

    1976-01-01

    Several goals were achieved during this period of 9 months, both in the experimental laboratory and in patients with acute myocardial infarction. (1) A study of the effects of aprotinin administration on myocardial ischemic injury, subsequent necrosis and collateral blood flow following acute coronary artery occlusion was carried out to completion. (2) A study of the effect of cobra venom factor on myocardial necrosis was completed and the factors responsible for its action were examined. (3) A comparison was made of the effects of nitroglycerin and nitroprusside on ischemic injury and regional myocardial blood flow in patients with acute myocardial infarction and in dogs with coronary occlusions. (4) A method of direct measurement of infarct size in the rat was developed. It consists of occlusion of the main left coronary artery and the histologic quantification of the infarct at 48 hours and 3 weeks later by serial histologic sections or alternatively by measuring total left ventricular myocardial creative phosphokinase activity. (5) New electrocardiographic methods have been developed in order to evaluate atraumatically the extent of myocardial infarction in patients. (6) Intravenous injection of (113)mIn-ENTMP and (99m)TcENTMP in dogs following coronary artery occlusion permitted a sequential double labeling of the damaged myocardium. (7) Since hyaluronidase is a very effective drug in reducing myocardial damage both in the experimental animal and in patients with acute myocardial infarction, a study was carried out to ascertain its effects on collateral flow

  6. Assessment on Event Classification of One Steam Generator Tube Rupture in EU-APR

    International Nuclear Information System (INIS)

    Kim, Ji Hwan; Kim, Yong Soo

    2016-01-01

    The Fukushima Daiichi nuclear power plant accident showed the vulnerability of coping strategy to beyond design natural disaster such as beyond design earthquake and tsunami. In Korea, the government and industry performed comprehensive safety inspection on all domestic nuclear power plants against beyond design basis external events and fifty action items have been issued. In addition to post- Fukushima action items, the stress tests for all domestic nuclear power plants are on the way to enhance the safety of domestic nuclear power plants through finding the vulnerabilities in intentional stress conditions initiated by beyond design natural disaster. Recently, the stress tests for WOLSONG Unit 1 and KORI Unit 1 have been performed and their assessment results have been reviewed by Korean regulatory body. The assessment of the coping capability of KORI Unit 1 has been performed under simultaneous the extended loss of AC power and loss of ultimate heat sink initiated by beyond design natural disaster. It is concluded that KORI Unit 1 has the capability, in the event of loss of safety functions by beyond design natural disaster, to sufficiently cool down the reactor core without fuel damage, to keep pressure boundaries of the reactor coolant system in transient condition and to control containment and temperature to maintain the integrity of the containment buildings. The several additional items for safety improvement has been drawn to enhance the coping capability for loss of safety functions under beyond design natural disaster in addition to post Fukushima action items

  7. IAEA Newsbriefs. V. 9, no. 2(64). Apr-May 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This issue gives brief information on the following topics: IAEA Board of Governor's Meetings in Early June, Nuclear Safety Convention, Monitoring and Verification in Iraq, Nuclear Power Regulation in China, Scientific Award for Marine Environment Programme, Assessing Radioactivity Levels at Sea, Safety at Chernobyl, An 'Energy-Ecology Dilemma', Safeguards at Nuclear Fuel Plant, Uranium Resources, Production, and Demand, Radioactive Waste Management, Global Climate Change Studies, Isotopes in Hydrology, Conference on Nuclear Power Option, Nuclear Fusion Research, Nuclear Techniques in Soil/Plant Studies, International Conference on Radiation and Society: Comprehending Radiation Risk, Experimental Fusion Reactor, Middle East NWFZ Concept Discussed, Symbolic Sculpture from South Africa, Update on Nuclear Electricity, and other short information

  8. Sexual dysfunctions after prostate cancer radiation therapy; Dysfonctions sexuelles apres irradiation pour cancer de la prostate

    Energy Technology Data Exchange (ETDEWEB)

    Droupy, S. [Service d' urologie-andrologie, CHU Caremeau, 30 - Nimes (France)

    2010-10-15

    Sexual dysfunctions are a quality of life main concern following prostate cancer treatment. After both radiotherapy and brachytherapy, sexual function declines progressively, the onset of occurrence of erectile dysfunction being 12-18 months after both treatments. The pathophysiological pathways by which radiotherapy and brachytherapy cause erectile dysfunction are multi-factorial, as patient co-morbidities, arterial damage, exposure of neurovascular bundle to high levels of radiation, and radiation dose received by the corpora cavernosa at the crurae of the penis may be important in the aetiology of erectile dysfunction. Diagnosis and treatment of postradiation sexual dysfunctions must integrate pre-therapeutic evaluation and information to provide to the patient and his partner a multidisciplinary sexual medicine management. (authors)

  9. Le drainage pelvien après adénometomie prostatique transvésicale ...

    African Journals Online (AJOL)

    O. Ghoundale

    Service d'Urologie, Hôpital Militaire Avicenne, Marrakech 40 000, Maroc. Reçu le 26 septembre 2012; reçu sous la forme révisée le 22 avril 2014; accepté le 29 avril 2014. MOTS CLÉS prostate; hyperplasie; adénomectomie; drainage; complication. Résumé. Objectif: La chirurgie ouverte garde encore sa place dans la prise ...

  10. The Port Moresby-Solomons Operation and the Allied Reaction, 27 Apr - 11 May 1942

    Science.gov (United States)

    2012-01-01

    started their attack, giving most of their attention to Lexington. Yorktown received one bomb hit, but Lexington was struck by two tor- pedoes and two...bombers, and thirty tor- pedo bombers) and 1,074 men; the Allies lost sixty-six aircraft and 543 men.235 One Japanese large carrier was heavily damaged

  11. Research and information needs for management of tar sands development. Interim report Apr-May 83

    Energy Technology Data Exchange (ETDEWEB)

    1983-05-01

    The report discusses important research and information needs for federal lease management of lands with tar sands resources. Short-term needs include more complete definition and characterization of deposits, hydrology, and regions downwind from tar sands areas. Longer-term needs include demonstration-scale operations to resolve production, waste management, and reclamation problems and to provide opportunities for measurement, analysis, and assessment of mining and processing wastes and emissions. Most of the known federal tar sands resource is in eastern Utah and contains about 25 billion barrels of bitumen. Recent legislation provides that existing mining claims and oil and gas leases may be converted to combined hydrocarbon leases including tar sands. Federal approval, which must be applied for by November 1983, is a condition for conversion.

  12. La materia de la rhétorique d’après Hermagoras de Temnos

    Directory of Open Access Journals (Sweden)

    Frédérique Woerther

    2011-08-01

    Full Text Available Several testimonia on Hermagoras (II B.C. imply that he defined the scope of rhetoric quite broadly, rather than narrowly as was normal in later rhetoricians: for such a definition, more theoretical than practical, the precedent was Aristotle in the Rhetoric, which Hermagoras can have known only indirectly.

  13. SAJAA MarApr 19-24 Con.fh9

    African Journals Online (AJOL)

    Studio G5

    J Clinical Anesth 2003 Aug;15(5):328–33. 5 Romano E. Anestesia generale e speciale; UTET Editori, Torino 1997:173–174. 6 Amici M, Eusebi F, Miledi R. Effects of the antibiotic gentamicin on nicotinic acetylcholine receptors. Neuropharmacology 2005 Oct 18, 102(42)15219–23. 7 Maidatsi PG, Zaralidou AT, Gorgias NK, ...

  14. Infrared, x-ray, and xuv astrophysics. Semiannual status report, 1 Apr.--30 Sep. 1975

    International Nuclear Information System (INIS)

    1975-01-01

    An observational program convering wavelengths from the near infrared to 1 millimeter is reviewed. The program of millimeter observations consisted largely of analyzing previous observations, since the summer humidity was too high for new observations. Maps of millimeter emission from W3, Sgr B2, W49, and M42 were made. Five extragalactic sources were detected and are discussed. Energy distributions of several of the discrete sources at the Galactic Center were studied. A 5-year visual/infrared program on Markarian galaxies is discussed which showed the presence of both thermal and nonthermal infrared radiation sources, and established correlations between the infrared sources and the emission line regions. The Nova Cygnus 1975, caught during its rise as well as subsequent dimming, is also discussed. Several other continuing programs are described, including studies of dark clouds and CO maser sources

  15. People and things. CERN Courier, Apr 1990, v. 30(3)

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events: ; In a January 31 test at the Continuous Electron Beam Accelerator Facility (CEBAF) under construction at Newport News, Virginia, a beam from the injector's 500 keV room temperature section was accelerated to 2.5 MeV in one cavity of the quarter-cryomodule containing the injector's initial superconducting accelerating cavity pair. ; To explore in detail and update the physics possibilities for the Large Hadron Collider (LHC) project at CERN, the European Committee for Future Accelerators (ECFA) is now preparing for an LHC Workshop to be held in Aachen from 5-10 October. ; The 1990 CERN School of Computing, organized in collaboration with the Inter-University Institute for High Energies, VUB-ULB, Brussels, will take place from 2-15 September at Nieuwpoort, Belgium. ; To reinforce the increased spirit of cooperation resulting from CERN's growing attraction for scientists from all over Europe and from further afield, the Laboratory embarked last year on a programme of drawing up bilateral agreements to put ongoing collaboration on a firmer footing

  16. IAEA Newsbriefs. V. 13, no. 2(79). Apr-May 1998

    International Nuclear Information System (INIS)

    1998-01-01

    This issue gives brief information on the following topics: IAEA Board Meetings Set in May and June, Database of the IAEA's International Nuclear Information Systems (INIS) is being made available over the Internet free of charge, Senior Expert Group Starts Review of IAEA Programmes, IAEA Reports to Security Council on Nuclear Inspections in Iraq, Parties Consider Extending Fusion Research through the ITER Project, Status of Joint Safety and Nuclear Liability Conventions, Proposed Global Convention Against Nuclear Terrorism, Upcoming Symposia and Conferences, New IAEA Books, Nuclear Data File, and other short information

  17. L’Albania apre agli accordi di collaborazione con i “nuovi culti”

    Directory of Open Access Journals (Sweden)

    Giovanni Cimbalo

    2011-10-01

    Full Text Available SOMMARIO: 1. Gli evangelici albanesi a favore della lingua, della cultura, dell’identità e dell’indipendenza - 2. La nuova Costituzione albanese e il ripristino della libertà religiosa - 3. Le trattative per la stipula dell’accordo di cooperazione - 4. I contenuti dell’accordo e i suoi effetti nel rapporto con la legislazione ordinaria a tutela della libertà religiosa - 5. La proiezione dell’efficacia degli accordi nell’area dell’Albania etnica – 6. Gli accordi di cooperazione: un modello esportabile?

  18. Green fuels, growth engines after petroleum; Les carburants verts, moteurs de la croissance apres le petrole

    Energy Technology Data Exchange (ETDEWEB)

    Mili, Dino

    2010-09-15

    The contribution of the new fuels to a greener environment is important and immediate. Thanks to clean novel technologies and to commercial plant projects in development, companies like Enerkem contribute to satisfy increasing global demand for clean energy. They stimulate local economies by creating jobs in an industry that offers real growth potential. Green fuels will gradually allow us to let go of non sustainable energy sources like oil to adopt a way of life based on sustainable development. They will also allow a shift towards a green economy. [French] La contribution des nouveaux carburants a un environnement plus vert est importante et immediate. Grace a des technologies propres novatrices et a des projets d'sines commerciales en developpement, des entreprises comme Enerkem contribuent a satisfaire a la demande mondiale croissante en energie propre. Elles stimulent les economies locales par la creation d'emplois dans une industrie qui offre un veritable potentiel de croissance. Les carburants verts permettront graduellement de nous affranchir des sources d'energie non renouvelables comme le petrole pour adopter un mode de vie base sur le developpement durable. Ils permettront aussi un virage vers une economie verte.

  19. People and things. CERN Courier, Apr 1988, v. 28(3)

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. The 5th Workshop on Nonlinear Evolution Equations and Dynamical Systems (NEEDS '89) will be held in Kolymbari, near Chania, Crete, from 2-19 July 1989. This year's DESY Theory Workshop ('Flavor Physics') will be held in Hamburg from 28-30 September. In conjunction with Daresbury Laboratory, the CERN Accelerator School is organizing a course on synchrotron radiation and free electron lasers in Chester, UK, from 6-12 April 1989. The topic for this year's SLAC Summer Institute is 'Probing the Weak Interaction: CP Violation and Rare Decays', The dates of the Institute are July 18th - 29th, 1988. The 1988 Summer Study on High Energy Physics in the 1990s will be held in Snowmass, Colorado, from 27 June to 15 July. The aim is to examine and evaluate the opportunities for high energy physics in the 1990s, including the possibilities with existing facilities, the proposed US Superconducting Super Collider (SSC), new accelerator technology, nonaccelerator experiments, special purpose facilities, and innovations in instrumentation and detector technology

  20. Construction of APR1000 nuclear power information management system based on international standards

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Seung Hwan [Korea Electric Power Research Institute, Daejeon (Korea, Republic of); Song, Deok Yong; Han, Byung Sub [Enesys Co., Daejeon (Korea, Republic of); An, Kyung Ik; Hwang, Jin Sang [PartDB Co., Daejeon (Korea, Republic of)

    2010-10-15

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model