Rigid cohomology over Laurent series fields

CERN Document Server

Lazda, Christopher

2016-01-01

In this monograph, the authors develop a new theory of p-adic cohomology for varieties over Laurent series fields in positive characteristic, based on Berthelot's theory of rigid cohomology. Many major fundamental properties of these cohomology groups are proven, such as finite dimensionality and cohomological descent, as well as interpretations in terms of Monsky-Washnitzer cohomology and Le Stum's overconvergent site. Applications of this new theory to arithmetic questions, such as l-independence and the weight monodromy conjecture, are also discussed. The construction of these cohomology groups, analogous to the Galois representations associated to varieties over local fields in mixed characteristic, fills a major gap in the study of arithmetic cohomology theories over function fields. By extending the scope of existing methods, the results presented here also serve as a first step towards a more general theory of p-adic cohomology over non-perfect ground fields. Rigid Cohomology over Laurent Series Fields...

Riesz Representation Theorem on Bilinear Spaces of Truncated Laurent Series

Directory of Open Access Journals (Sweden)

Sabarinsyah

2017-06-01

Full Text Available In this study a generalization of the Riesz representation theorem on non-degenerate bilinear spaces, particularly on spaces of truncated Laurent series, was developed. It was shown that any linear functional on a non-degenerate bilinear space is representable by a unique element of the space if and only if its kernel is closed. Moreover an explicit equivalent condition can be identified for the closedness property of the kernel when the bilinear space is a space of truncated Laurent series.

Diophantine non-integrability of a third-order recurrence with the Laurent property

International Nuclear Information System (INIS)

Hone, A N W

2006-01-01

We consider a one-parameter family of third-order nonlinear recurrence relations. Each member of this family satisfies the singularity confinement test, has a conserved quantity, and moreover has the Laurent property: all of the iterates are Laurent polynomials in the initial data. However, we show that these recurrences are not Diophantine integrable according to the definition proposed by Halburd (2005 J. Phys. A: Math. Gen. 38 L1). Explicit bounds on the asymptotic growth of the heights of iterates are obtained for a special choice of initial data. As a by-product of our analysis, infinitely many solutions are found for a certain family of Diophantine equations, studied by Mordell, that includes Markoff's equation. (letter to the editor)

Decision no 2010-DC-0182 by the Nuclear Safety Authority on the 18. of May 2010 specifying the limits of releases in the environment of liquid and gaseous effluents of civil base nuclear installations no 46, no 74 and no 100 operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan (Loir-et-Cher department)

International Nuclear Information System (INIS)

2010-01-01

This document contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of civil base nuclear installations operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan. Commented tables in appendix present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (boric acid, hydrazine, morpholine, phosphates, nitrates, various metals, and so on). The limits for thermal releases are also specified

Social and technical history of the electrification of the lower Saint Lawrence, 1888-1963. Histoire sociale et technique de l'electrification au Bas-Saint-Laurent, 1888-1963; Volume 1

Energy Technology Data Exchange (ETDEWEB)

Tremblay, Y

1993-06-01

The lower St. Lawrence region of Quebec is a rural area with little industry and does not possess important hydraulic resources. Electrification of this region progressed slowly and in an uneven manner. From 1888 to 1922, many local distributors, private or municipal, gave a mediocre quality of service to a small number of customers. A regional firm, the Compagnie de Pouvoir du Bas St-Laurent, followed in 1922 but its resources remained limited, and in a few years it passed under the control of American capitalists. The most rural sectors of the region were badly provided with electricity even in 1945, and the state, in the form of the Office de l'Electrification Rurale, had to intervene to remedy this situation. The Office took charge of organizing and financing electric power distribution cooperatives which ensured service in the most remote zones of Quebec. At the beginning of the 1960s, the inequalities in electric power rates in the region supplied a weighty argument to those in favor of nationalization of power companies. The Compagnie de Pouvoir was acquired by Hydro-Quebec in 1963 and the region was finally correctly integrated with the provincial grid. The cooperatives were also acquired by the Crown corporation a short time thereafter. Electrification was not only building power plants and distribution networks, but also involved development of consumption of electricity on farms and in homes. This made city comforts universal and modified rural life styles, for example by the introduction of electric appliances. 430 refs., 35 figs., 70 tabs.

Tensor integrand reduction via Laurent expansion

Energy Technology Data Exchange (ETDEWEB)

Hirschi, Valentin [SLAC, National Accelerator Laboratory,2575 Sand Hill Road, Menlo Park, CA 94025-7090 (United States); Peraro, Tiziano [Higgs Centre for Theoretical Physics, School of Physics and Astronomy,The University of Edinburgh,Edinburgh EH9 3JZ, Scotland (United Kingdom)

2016-06-09

We introduce a new method for the application of one-loop integrand reduction via the Laurent expansion algorithm, as implemented in the public C++ library Ninja. We show how the coefficients of the Laurent expansion can be computed by suitable contractions of the loop numerator tensor with cut-dependent projectors, making it possible to interface Ninja to any one-loop matrix element generator that can provide the components of this tensor. We implemented this technique in the Ninja library and interfaced it to MADLOOP, which is part of the public MADGRAPH5{sub A}MC@NLO framework. We performed a detailed performance study, comparing against other public reduction tools, namely CUTTOOLS, SAMURAI, IREGI, PJFRY++ and GOLEM95. We find that Ninja outperforms traditional integrand reduction in both speed and numerical stability, the latter being on par with that of the tensor integral reduction tool GOLEM95 which is however more limited and slower than Ninja. We considered many benchmark multi-scale processes of increasing complexity, involving QCD and electro-weak corrections as well as effective non-renormalizable couplings, showing that Ninja’s performance scales well with both the rank and multiplicity of the considered process.

A reactivity accidents simulation of the Fort Saint Vrain HTGR

International Nuclear Information System (INIS)

Fainer, Gerson

1980-01-01

A reactivity accidents analysis of the Fort Saint Vrain HTGR was made. The following accidents were analysed 1) A rod pair withdrawal accident during normal operation, 2) A rod pair ejection accident, 3) A rod pair withdrawal accident during startup operations at source levels and 4) Multiple rod pair withdrawal accident. All the simulations were performed by using the BLOOST-6 nuclear code The steady state reactor operation results obtained with the code were consistent with the design reactor data. The numerical analysis showed that all accidents - except the first one - cause particle failure. (author)

Order of the 17. of June 2010 approving the decision no 2010-DC-0182 by the Nuclear Safety Authority on the 18. of May 2010 specifying the limits of releases in the environment of liquid and gaseous effluents of civil base nuclear installations no 46, 74 and 100 operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan (Loir-et-Cher department)

International Nuclear Information System (INIS)

2010-01-01

This legal publication contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of civil base nuclear installations operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan. Tables present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (boric acid, hydrazine, morpholine, phosphates, nitrates, various metals, and so on). The limits for thermal releases are also specified

Operator modeling of a loss-of-pumping accident using MicroSAINT

International Nuclear Information System (INIS)

Olsen, L.M.

1992-01-01

The Savannah River Laboratory (SRL) human factors group has been developing methods for analyzing nuclear reactor operator actions during hypothetical design-basis accident scenarios. The SRL reactors operate at a lower temperature and pressure than power reactors resulting in accident sequences that differ from those of power reactors. Current methodology development is focused on modeling control room operator response times dictated by system event times specified in the Savannah River Site Reactor Safety Analysis Report (SAR). The modeling methods must be flexible enough to incorporate changes to hardware, procedures, or postulated system event times and permit timely evaluation. The initial model developed was for the loss-of-pumping accident (LOPA) because a significant number of operator actions are required to respond to this postulated event. Human factors engineers had been researching and testing a network modeling simulation language called MicroSAINT to simulate operators' personal and interpersonal actions relative to operating system events. The LOPA operator modeling project demonstrated the versatility and flexibility of MicroSAINT for modeling control room crew interactions

Return on experience on nuclear accidents

International Nuclear Information System (INIS)

Barre, Bertrand

2015-09-01

After a presentation of the International Nuclear and radiological Events Scale (INES scale), of its levels and criteria, this article proposes brief recalls of some nuclear accidents which occurred in nuclear reactors: Chalk River in Canada (1952), Windscale in England (1957), the universal Canadian reactor (NRU in 1958), the SL1 reactor of the Idaho National Laboratory in the USA (1961), the Swiss Lucens reactor (1969), Saint-Laurent des Eaux in France (1969 and 1980). More detailed descriptions are then given for the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima accident in 2011. The main causes of these accidents are identified: loss of control of chain reaction, cooling defect on a stopped reactor, cooling defect on an operated reactor. Some lessons are drawn from these facts, and some characteristics of the EPR are outlined with respect with problems encountered in these accidents

The Burning Saints

DEFF Research Database (Denmark)

Xygalatas, Dimitris

. Carrying the sacred icons of the saints, participants dance over hot coals as the saint moves them. The Burning Saints presents an analysis of these rituals and the psychology behind them. Based on long-term fieldwork, The Burning Saints traces the historical development and sociocultural context......, The Burning Saints presents a highly original analysis of how mental processes can shape social and religious behaviour....

On generalizations of the series of Taylor, Lagrange, Laurent and Teixeira

Directory of Open Access Journals (Sweden)

L. M. B. C. Campos

1990-01-01

Full Text Available The classical theorems of Taylor, Lagrange, Laurent and Teixeira, are extended from the representation of a complex function F(z, to its derivative F(ν(z of complex order ν, understood as either a ‘Liouville’ (1832 or a ‘Rieman (1847’ differintegration (Campos 1984, 1985; these results are distinct from, and alternative to, other extensions of Taylor's series using differintegrations (Osler 1972, Lavoie & Osler & Tremblay 1976. We consider a complex function F(z, which is analytic (has an isolated singularity at ζ, and expand its derivative of complex order F(ν(z, in an ascending (ascending-descending series of powers of an auxiliary function f(z, yielding the generalized Teixeira (Lagrange series, which includes, for f(z=z−ζ, the generalized Taylor (Laurent series. The generalized series involve non-integral powers and/or coefficients evaluated by fractional derivatives or integrals, except in the case ν=0, when the classical theorems of Taylor (1715, Lagrange (1770, Laurent (1843 and Teixeira (1900 are regained. As an application, these generalized series can be used to generate special functions with complex parameters (Campos 1986, e.g., the Hermite and Bessel types.

Risk Assessment: Democratic Republic of Congo Post-Laurent ...

African Journals Online (AJOL)

political system as opposed to the view that it was merely a power struggle between Kabila on the .... Local actors and international mining companies built alliances exploiting Congo's minerals to gain a ... They are preparing a contingency plan for their activities in the post-Laurent Kabila era, for ... small arms in the DRC.33.

Laurent Thévenot and the French Convention School

DEFF Research Database (Denmark)

Jagd, Søren

2004-01-01

The aim of this short introduction is to present some of the most important of Laurent Thévenot’s contritions. It is argued that one of the key contributions has been his elaboration on a sociological perspective for the study of economic action....

7 CFR 319.77-3 - Gypsy moth infested areas in Canada.

Science.gov (United States)

2010-01-01

...-Richelieu, Le Bas-Richelieu, Le Granit, Le Haut-Richelieu, Le Haut-Saint-Francois, Le Haut-Saint-Laurent, Le... Conception; and (8) That portion of the regional county municipality of Les Pays-d'en-Haut that includes the...

Feedback from dismantling operations (level 2) on EDF's first generation reactors

International Nuclear Information System (INIS)

West, J P.; Dionisio-Gomes, A.; Kus, J P.; Mervaux, P.; Bernet, P.; Dalmas, R.

2003-01-01

EDF's policy as regards the dismantling of the reactors that have ceased commercial operation, namely the eight power plants of the first generation and the Creys-Malville power plant, is explained. Generally speaking, prior to the year 2001, EDF had opted for the de-construction of these power plants to comply with a 'long wait' scenario, which consisted of waiting for a period of 5 to 10 years to achieve IAEA level 2 (partial release of the site), then postponing the total de-construction of the facilities for 25 to 50 years. Today, EDF has decided to undertake the total de-construction of these reactors, which have ceased commercial operation, over a period of 25 years. The purpose of this document is to present: - The reactors concerned, their background and their 'regulatory' situation, - The main operations performed and/or currently in progress, - The main elements of feedback from such operations, shedding light on the approach adopted in 2001. The installations concerned by the de-construction programme are as follows: - The 8 power plants of the first generation, which were built during the fifties and sixties and ceased commercial operation between 1973 and 1994, namely: Brennilis (industrial prototype using heavy water technology, jointly operated by EDF and CEA), the 6 power units of the NUGG type (natural uranium gas graphite) at Chinon, Saint-Laurent des Eaux and Bugey and the PWR reactor at Chooz A, - The storage silos at Saint-Laurent, where the sleeves for the fuel assemblies of reactors SLA1 and SLA2 are stored, corresponding to approximately 2000 tonnes of graphite, - The Creys-Malville reactor, FBR (fast breeder reactor) shut down in accordance with a government decision, which is currently undergoing decommissioning. At the current stage, our feedback from the dismantling operations carried out on nuclear facilities is based on (i) the work carried out or in progress that will make it possible to achieve the equivalent of IAEA level 2 in the

Nondestructive evaluation of the oxidation and strength of the Fort Saint Vrain HTGR support block

International Nuclear Information System (INIS)

Tingey, G.L.; Posakony, G.J.; Morgan, W.C.; Prince, J.M.; Hill, R.W.; Lessor, D.L.

1982-04-01

Non-destructive detection of changes in the strength of graphite support structures in a HTGR appears to be feasible using sonic velocity measurements where access for through transmission is possible. Therefore, future HTGR designs should consider providing such access. Where access is not available, strength changes can be correlated with oxidation profiles in the support member. These oxidation profiles can be determined non-destructively by a combination of eddy current measurements to detect near surface oxidation and sonic backscattering measurements designed to determine oxidation in depth. The Fort Saint Vrain reactor provides an operating reactor to test the applicability of the eddy current and sonic backscattering techniques for determination of oxidation in a support block. Furthermore, such tests in Fort Saint Vrain will supply base line data which will be useful in assuring an adequate strength of the support structure for the lifetime of the reactor. Equipment is, therefore, being developed for tests to be conducted during the next major refueling of the reactor

Human performance in an operational event - how to improve it? An initiative in a French NPP

International Nuclear Information System (INIS)

Meslin, M.

1998-01-01

In the case of the Saint-Laurent-des-Eaux French nuclear power station, the author comments the elements and principles of human factor policy which have been implemented, the organizational implications of this implementation (building up of an internal human factors network), and briefly evokes studies and initiatives aimed at improving the quality of operation from a general point of view and through projects aiming at analyzing and at a valorisation of human reliability in activities dealing with reactor operation. He also comments the perception and appropriation of quality in the different departments

MANHATTAN PROJECT B REACTOR HANFORD WASHINGTON [HANFORD'S HISTORIC B REACTOR (12-PAGE BOOKLET)

Energy Technology Data Exchange (ETDEWEB)

GERBER MS

2009-04-28

The Hanford Site began as part of the United States Manhattan Project to research, test and build atomic weapons during World War II. The original 670-square mile Hanford Site, then known as the Hanford Engineer Works, was the last of three top-secret sites constructed in order to produce enriched uranium and plutonium for the world's first nuclear weapons. B Reactor, located about 45 miles northwest of Richland, Washington, is the world's first full-scale nuclear reactor. Not only was B Reactor a first-of-a-kind engineering structure, it was built and fully functional in just 11 months. Eventually, the shoreline of the Columbia River in southeastern Washington State held nine nuclear reactors at the height of Hanford's nuclear defense production during the Cold War era. The B Reactor was shut down in 1968. During the 1980's, the U.S. Department of Energy began removing B Reactor's support facilities. The reactor building, the river pumphouse and the reactor stack are the only facilities that remain. Today, the U.S. Department of Energy (DOE) Richland Operations Office offers escorted public access to B Reactor along a designated tour route. The National Park Service (NPS) is studying preservation and interpretation options for sites associated with the Manhattan Project. A draft is expected in summer 2009. A final report will recommend whether the B Reactor, along with other Manhattan Project facilities, should be preserved, and if so, what roles the DOE, the NPS and community partners will play in preservation and public education. In August 2008, the DOE announced plans to open B Reactor for additional public tours. Potential hazards still exist within the building. However, the approved tour route is safe for visitors and workers. DOE may open additional areas once it can assure public safety by mitigating hazards.

Saints and Sainthood

DEFF Research Database (Denmark)

Bandak, Andreas

2018-01-01

Saints are central for personal devotion, as intercessors and mediators between humanity and God, and as models for emulation. Relationships with and images of saints and holy figures are by no means fixed, but have developed, mirrored and challenged different times and cultures. Sainthood is a p...... with him or her even if they never aspire to become a saint themselves. In this sense sainthood is a matter of social relationships—relationships which are perennially in the making....

Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Yoon, Ji Hyun; Lee, Bong Sang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-08-15

The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made of SA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR 50.61a matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better than did that of Regulatory Guide (RG) 1.99 Rev. 2. This is attributed to the fact that the prediction performance of 10 CFR 50.61a was enhanced by considering the difference in radiation embrittlement sensitivity among the different types of RPV materials.

Moeuudised

Index Scriptorium Estoniae

1998-01-01

Prantsuse moemaja Chloe peadisainer Stella McCartney aitas loomakaitseorganisatsioonil PETA teha dokumentaalfilmi, milles paljastatakse karusloomafarmide telgitaguseid. Chloe supelkostüümist, mida soovitatakse eeskujuks võtta endale bikiinide heegeldamisel. Yves Saint Laurenti moemaja korraldab gigantse moeshow jalgpallistaadionil, kus algab jalgpalli MM. Yves Saint Laurent on kavandanud MMi korraldajate-asjameeste kostüümid

Lobitööd pole vaja keelata / Idir Laurent Khiar ; intervjueerinud Priit Pruul

Index Scriptorium Estoniae

Khiar, Idir Laurent

2016-01-01

Lobitegevuse reguleerimisest. Intervjuu 2007.-2009. aastate finantskriisi ajal valitsus- ja tööstussuhete juhina rahvusvahelise kindlustusettevõtte juures töötanud Idir Laurent Khiariga lobitegevusest ning era- ja avalike huvide läbipõimunud suhetest

The reactor kinetics code tank: a validation against selected SPERT-1b experiments

International Nuclear Information System (INIS)

Ellis, R.J.

1990-01-01

The two-dimensional space-time analysis code TANK is being developed for the simulation of transient behaviour in the MAPLE class of research reactors. MAPLE research reactor cores are compact, light-water-cooled and -moderated, with a high degree of forced subcooling. The SPERT-1B(24/32) reactor core had many similarities to MAPLE-X10, and the results of the SPERT transient experiments are well documented. As a validation of TANK, a series of simulations of certain SPERT reactor transients was undertaken. Special features were added to the TANK code to model reactors with plate-type fuel and to allow for the simulation of rapid void production. The results of a series of super-prompt-critical reactivity step-insertion transient simulations are presented. The selected SPERT transients were all initiated from low power, at ambient temperatures, and with negligible coolant flow. Th results of the TANK simulations are in good agreement with the trends in the experimental SPERT data

Technical evolution and operation of French CO2 cooled reactors (UNGG)

International Nuclear Information System (INIS)

Berthion, Y.

1986-10-01

The technical evolution of the five French CO 2 cooled reactors (UNGG) from 1981 to 1986 needs to be outlined. These technical evolutions concerned the fuel element of Bugey 1 which is now slightly enriched, as well as the load reduction operation required by the grid. In addition work in underway to increase the safety at the two St Laurent units, or to repair the hot steel upper-structures of Chinon-3 unit

Kto jest kto v mire sovremennoi modõ

Index Scriptorium Estoniae

2002-01-01

Tutvustatakse kaasaja kuulsaid moekunstnikke: Stella McCartney (1972), Tom Ford Texasest, Tommy Hilfiger (1952), Vivienne Westwood (1941), Yves Saint-Laurent (1936). Algus ajalehes Molodjozh Estonii 4. juuni 2002

Gateway to the Syriac Saints: A Database Project

Directory of Open Access Journals (Sweden)

Jeanne-Nicole Mellon Saint-Laurent

2016-04-01

Full Text Available This article describes The Gateway to the Syriac Saints, a database project developed by the Syriac Reference Portal (www.syriaca.org. It is a research tool for the study of Syriac saints and hagiographic texts. The Gateway to the Syriac Saints is a two-volume database: 1 Qadishe and 2 Bibliotheca Hagiographica Syriaca Electronica (BHSE. Hagiography, the lives of the saints, is a multiform genre. It contains elements of myth, history, biblical exegesis, romance, and theology. The production of saints’ lives blossomed in late antiquity alongside the growth of the cult of the saints. Scholars have attended to hagiographic traditions in Greek and Latin, but many scholars have yet to discover the richness of Syriac hagiographic literature: the stories, homilies, and hymns on the saints that Christians of the Middle East told and preserved. It is our hope that our database will give scholars and students increased access to these traditions to generate new scholarship. The first volume, Qadishe or “saints” in Syriac, is a digital catalogue of saints or holy persons venerated in the Syriac tradition. Some saints are native to the Syriac-speaking milieu, whereas others come from other linguistic or cultural traditions. Through the translation of their hagiographies and the diffusion of saints’ cults in the late antique world, saints were adopted, “imported,” and appropriated into Syriac religious memory. The second volume, the BHSE, focuses on Syriac hagiographic texts. The BHSE contains the titles of over 1000 Syriac stories, hymns, and homilies on saints. It also includes authors’ or hagiographers’ names, the first and last lines of the texts (in Syriac, English, and French, bibliographic information, and the names of the manuscripts containing these hagiographic works. We have also listed modern and ancient translations of these works. All of the data in the Gateway to the Syriac Saints has been encoded in TEI, and it is fully

Hanford B Reactor Building Hazard Assessment Report

International Nuclear Information System (INIS)

Griffin, P. W.

1999-01-01

The 105-B Reactor (hereinafter referred to as B Reactor) is located in the 100 Area of the Hanford Site near Richland, Washington. The B Reactor is one of nine plutonium production reactors that were constructed in the 1940s during the Cold War Era. Construction of the B Reactor began June 7, 1943, and operation began on September 26, 1944. The Environmental Restoration Contractor was requested by RL to provide an assessment/characterization of the B Reactor building to determine and document the hazards that are present and could pose a threat to the environment and/or to individuals touring the building. This report documents the potential hazards, determines the feasibility of mitigating the hazards, and makes recommendations regarding areas where public tour access should not be permitted

Review of Laurent Pernot, Epideictic Rhetoric : Questioning the Stakes of Ancient Praise.

NARCIS (Netherlands)

Kuin, Inger Neeltje Irene

2015-01-01

The French scholar Laurent Pernot has been at the forefront of the study of ancient rhetoric for over two decades. His standard work La Rhétorique dans l’Antiquité has been translated into four languages, including an English edition that I found very useful for the (undergraduate) classroom. Pernot

Linear operator pencils on Lie algebras and Laurent biorthogonal polynomials

International Nuclear Information System (INIS)

Gruenbaum, F A; Vinet, Luc; Zhedanov, Alexei

2004-01-01

We study operator pencils on generators of the Lie algebras sl 2 and the oscillator algebra. These pencils are linear in a spectral parameter λ. The corresponding generalized eigenvalue problem gives rise to some sets of orthogonal polynomials and Laurent biorthogonal polynomials (LBP) expressed in terms of the Gauss 2 F 1 and degenerate 1 F 1 hypergeometric functions. For special choices of the parameters of the pencils, we identify the resulting polynomials with the Hendriksen-van Rossum LBP which are widely believed to be the biorthogonal analogues of the classical orthogonal polynomials. This places these examples under the umbrella of the generalized bispectral problem which is considered here. Other (non-bispectral) cases give rise to some 'nonclassical' orthogonal polynomials including Tricomi-Carlitz and random-walk polynomials. An application to solutions of relativistic Toda chain is considered

Two African Saints in Medieval Germany.

Science.gov (United States)

Grimm, Reinhold

1992-01-01

The origin and development of two African saints are discussed: Saint Maurice, patron saint of the eastern empire of Otto I; and Caspar, the youngest of the three Magi. Their representation in German art is described and illustrated. (Author/LB)

Saint rulers as a category of sanctity in Orthodoxy

Directory of Open Access Journals (Sweden)

Jarosław Charkiewicz

2015-11-01

Full Text Available In the wide spectre of Orthodox human sanctity, among others, there is also a category of saint rulers. Despite the fact that it’s represented by a significant number of saints, it remains, utterly undeservedly, in the shadow of the others – more known or more deeply rooted historically. On top of that, the situation may result as well from the fact that saint rulers, as a distinct category of saint, are not separately mentioned neither during the proskomedia, nor during the intercessory prayer of the anaphora. Still, the saint rulers definitely should be considered a separate type of sanctity, deserving a somehow wider presentation. Such is therefore the aim of this article.It is also an attempt of suggesting an interior systematic of this category of sanctity. Preserving, appearing in science, classifications of the saint rulers, the author gives also his own proposition. In the category of saint rulers there are four following groups: (1 rulerswho weren’t neither martyrs nor monks or passion-bearers, (2 rulers who died martyrs, (3 rulers who long before their death became monks and led monastic life, (4 rulers-passion-bearers.

« L’obscurité entre nous ». Menace et fécondité du silence chez Laurent Mauvignier

Directory of Open Access Journals (Sweden)

Julie Crohas Commans

2012-01-01

Full Text Available Dans Loin d’eux et Seuls, Laurent Mauvignier explore un huis clos familial où enfants et parents sont torturés par une transmission à laquelle manquent les mots. Tour à tour, les protagonistes témoignent à bout de souffle de leur malaise. Le silence envahit les discours et mutile le texte et les corps. Menacées par l’obscurité, les voix du récit luttent pour imposer leurs présences et leurs identités. Elles ne trouvent d’issue que dans leur unification, seul moyen de révéler le passage, testament silencieux d’une littérature en quête d’elle-même, au détour des dits et des non-dits de l’écriture de Laurent Mauvignier. In Loin d’eux and Seuls, Laurent Mauvignier explores a familial “huis clos” in which both children and their parents are tortured by wordless communication. In turn, the protagonists breathlessly express their malaise. Silence invades their discourse and mutilates both the text and the bodies. Threatened with falling into obscurity, the voices of the story struggle to establish their presence and their identity. Their only way out is through unification, the sole means of revealing the path, a silent testament of a literature in search of itself through both the spoken and unspoken words of Laurent Mauvignier’s writing.

Saints and Sainthood around the Baltic Sea

DEFF Research Database (Denmark)

This collection of articles covers most of the Baltic Region with a special focus on the cult of saints in Russia, Prussia, Finland, Sweden, Denmark, Estonia and Latvia (more commonly referred to in the Middle Ages as Livonia). The articles cover a wide range of topics, for example the introduction...... of foreign (and ‘old’) saints into new regions, the creation of new local cults of saints in newly Christianized regions, the role of the cult of saints in the creation of political and lay identities, the adaption of the cult of saints in folk poetry and the potential role of saints in times of war...

St. René: the Patron Saint of Anaesthetists and a Patron Saint of Canada.

Science.gov (United States)

Calverley, R K

1980-01-01

René Goupil, the Patron Saint of Anaesthetists, and a Patron Saint of Canada, was born in Angers, France in 1608 and studied surgery. He joined the Jesuits as a donné or volunteer worker in 1640 and served in the then tiny colony of Quebec as one of the first medical workers of Canada. After earning meritorious praise for his skills, he again volunteered to attend the Hurons at Sainte Marie, a mission far beyond the frontiers. René's canoe party was ambushed. He was captured by the Mohawks and endured eight weeks of cruel torture before being killed on September 29, 1642. René was the first of eight North American martyrs whose dedication was recognized by canonization in 1930. St. René was appointed Patron Saint of Anaesthetists in 1951.

Église Saint-Pierre-Saint-Paul, Appoigny (Yonne

Directory of Open Access Journals (Sweden)

Fabrice Henrion

2009-09-01

Full Text Available L’église Saint-Pierre-Saint-Paul d’Appoigny témoigne d’un important chantier du début du XIIIe siècle , mais les sources permettent d’envisager la présence d’un sanctuaire au moins depuis l’extrême fin du VIe siècle. En effet, le règlement liturgique établit par Aunaire, évêque d’Auxerre de 561 à 604, mentionne Epponiacus dans la liste des sanctuaires auxerrois, sans que le vocable de l’église d’Appoigny ne soit précisé. Par ailleurs, depuis au moins le IXe siècle, une tradition, reprise par ...

Inhibition of Corneal Neovascularization with the Combination of Bevacizumab and Plasmid Pigment Epithelium-Derived Factor-Synthetic Amphiphile INTeraction-18 (p-PEDF-SAINT-18 Vector in a Rat Corneal Experimental Angiogenesis Model

Directory of Open Access Journals (Sweden)

Ching-Hsein Chen

2013-04-01

Full Text Available Bevacizumab, a 149-kDa protein, is a recombinant humanized monoclonal antibody to VEGF. PEDF, a 50-kDa glycoprotein, has demonstrated anti-vasopermeability properties. In this study, we demonstrated that the combination of bevacizumab and plasmid pigment epithelium-derived factor-synthetic amphiphile INTeraction-18 (p-PEDF-SAINT-18 has a favorable antiangiogenic effect on corneal NV. Four groups (Group A: 0 μg + 0 μg, B: 0.1 μg + 0.1 μg, C: 1 μg + 1 μg, and D: 10 μg + 10 μg of bevacizumab + p-PEDF-SAINT-18 were prepared and implanted into the rat subconjunctival substantia propria 1.5 mm from the limbus on the temporal side. Then, 1 μg of p-bFGF-SAINT-18 was prepared and implanted into the rat corneal stroma 1.5 mm from the limbus on the same side. The inhibition of NV was observed and quantified from days 1 to 60. Biomicroscopic examination, western blot analysis and immunohistochemistry were used to analyze the 18-kDa bFGF, 50-kDa PEDF and VEGF protein expression. No inhibition activity for normal limbal vessels was noted. Subconjunctival injection with the combination of bevacizumab and p-PEDF-SAINT-18 successfully inhibited corneal NV. The bFGF and PEDF genes were successfully expressed as shown by western blot analysis, and a mild immune response to HLA-DR was shown by immunohistochemistry. We concluded that the combination of bevacizumab and p-PEDF-SAINT-18 may have more potent and prolonged antiangiogenic effects, making it possible to reduce the frequency of subconjunctival.Bevacizumab, a 149-kDa protein, is a recombinant humanized monoclonalantibody to VEGF. PEDF, a 50-kDa glycoprotein, has demonstrated anti-vasopermeabilityproperties. In this study, we demonstrated that the combination of bevacizumaband plasmid pigment epithelium-derived factor-synthetic amphiphile INTeraction-18(p-PEDF-SAINT-18 has a favorable antiangiogenic effect on corneal NV. Four groups(Group A: 0 μg + 0 μg, B: 0.1 μg + 0.1 μg, C: 1 μg + 1 μg, and

75 FR 38718 - Safety Zone; Sault Sainte Marie 4th of July Fireworks, St. Mary's River, Sault Sainte Marie, MI

Science.gov (United States)

2010-07-06

... temporary safety zone on the St. Mary's River, Sault Sainte Marie, Michigan. This zone is intended to..., St. Mary's River, Sault Sainte Marie, MI (a) Location. The following area is a temporary safety zone...-AA00 Safety Zone; Sault Sainte Marie 4th of July Fireworks, St. Mary's River, Sault Sainte Marie, MI...

Making midwives: postmodern conditions and midwifery training in Saint Lucia.

Science.gov (United States)

Hsu, C

2001-01-01

Drawing on material from fieldwork conducted on the island of Saint Lucia, I examine how Saint Lucian nurse-midwives and student midwives negotiate multiple ways of understanding and evaluating their practices and roles in light of contradictory and powerful cultural, historical, and political forces. I argue that, although Saint Lucian nurse-midwives may not qualify as "postmodern" according to the criteria proposed by Davis-Floyd and Davis (1996), they are nonetheless struggling with postmodern conditions as they negotiate between competing healing ideologies. I illustrate the significance of these negotiations through analyzing: (1) the ways nurse-midwives understand and articulate the healing ideologies at play in Saint Lucia, (2) historical and ideological aspects of the Saint Lucian nurse-midwifery training program, and (3) a classroom discussion during which student reported on "bush-midwives."

Dragotsennaja osen / Tatjana Barmakova

Index Scriptorium Estoniae

Barmakova, Tatjana

2004-01-01

Moefirmade Dior, Yves Saint Laurent (jumestuskunstnik Linda Cantello), Guerlain (kunstnik Olivier Echaudemaison), Shiseido (kunstnik Tom Pecheux) meigikollektsioonidest. Diori, Kenzo ja Thierry Mugleri uutest parfüümidest. "Kenzoairi" parfüümipudeli disainis klaasikunstnik Laura de Santillana

Validation study of the reactor physics lattice transport code WIMSD-5B by TRX and BAPL critical experiments of light water reactors

International Nuclear Information System (INIS)

Khan, M.J.H.; Alam, A.B.M.K.; Ahsan, M.H.; Mamun, K.A.A.; Islam, S.M.A.

2015-01-01

Highlights: • To validate the reactor physics lattice code WIMSD-5B by this analysis. • To model TRX and BAPL critical experiments using WIMSD-5B. • To compare the calculated results with experiment and MCNP results. • To rely on WIMSD-5B code for TRIGA calculations. - Abstract: The aim of this analysis is to validate the reactor physics lattice transport code WIMSD-5B by TRX (thermal reactor-one region lattice) and BAPL (Bettis Atomic Power Laboratory-one region lattice) critical experiments of light water reactors for neutronics analysis of 3 MW TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh. This analysis is achieved through the analysis of integral parameters of five light water reactor critical experiments TRX-1, TRX-2, BAPL-UO 2 -1, BAPL-UO 2 -2 and BAPL-UO 2 -3 based on evaluated nuclear data libraries JEFF-3.1 and ENDF/B-VII.1. In integral measurements, these experiments are considered as standard benchmark lattices for validating the reactor physics lattice transport code WIMSD-5B as well as evaluated nuclear data libraries. The integral parameters of the said critical experiments are calculated using the reactor physics lattice transport code WIMSD-5B. The calculated integral parameters are compared to the measured values as well as the earlier published MCNP results based on the Chinese evaluated nuclear data library CENDL-3.0 for assessment of deterministic calculation. It was found that the calculated integral parameters give mostly reasonable and globally consistent results with the experiment and the MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are well consistent with each other. Therefore, this analysis reveals the validation study of the reactor physics lattice transport code WIMSD-5B based on JEFF-3.1 and ENDF/B-VII.1 libraries and can also be essential to

Targeting Rapamycin to Podocytes Using a Vascular Cell Adhesion Molecule-1 (VCAM-1-Harnessed SAINT-Based Lipid Carrier System.

Directory of Open Access Journals (Sweden)

Ganesh Ram R Visweswaran

Full Text Available Together with mesangial cells, glomerular endothelial cells and the basement membrane, podocytes constitute the glomerular filtration barrier (GFB of the kidney. Podocytes play a pivotal role in the progression of various kidney-related diseases such as glomerular sclerosis and glomerulonephritis that finally lead to chronic end-stage renal disease. During podocytopathies, the slit-diaphragm connecting the adjacent podocytes are detached leading to severe loss of proteins in the urine. The pathophysiology of podocytopathies makes podocytes a potential and challenging target for nanomedicine development, though there is a lack of known molecular targets for cell selective drug delivery. To identify VCAM-1 as a cell-surface receptor that is suitable for binding and internalization of nanomedicine carrier systems by podocytes, we investigated its expression in the immortalized podocyte cell lines AB8/13 and MPC-5, and in primary podocytes. Gene and protein expression analyses revealed that VCAM-1 expression is increased by podocytes upon TNFα-activation for up to 24 h. This was paralleled by anti-VCAM-1 antibody binding to the TNFα-activated cells, which can be employed as a ligand to facilitate the uptake of nanocarriers under inflammatory conditions. Hence, we next explored the possibilities of using VCAM-1 as a cell-surface receptor to deliver the potent immunosuppressant rapamycin to TNFα-activated podocytes using the lipid-based nanocarrier system Saint-O-Somes. Anti-VCAM-1-rapamycin-SAINT-O-Somes more effectively inhibited the cell migration of AB8/13 cells than free rapamycin and non-targeted rapamycin-SAINT-O-Somes indicating the potential of VCAM-1 targeted drug delivery to podocytes.

Depleted Reactor Analysis With MCNP-4B

International Nuclear Information System (INIS)

Caner, M.; Silverman, L.; Bettan, M.

2004-01-01

Monte Carlo neutronics calculations are mostly done for fresh reactor cores. There is today an ongoing activity in the development of Monte Carlo plus burnup code systems made possible by the fast gains in computer processor speeds. In this work we investigate the use of MCNP-4B for the calculation of a depleted core of the Soreq reactor (IRR-1). The number densities as function of burnup were taken from the WIMS-D/4 cell code calculations. This particular code coupling has been implemented before. The Monte Carlo code MCNP-4B calculates the coupled transport of neutrons and photons for complicated geometries. We have done neutronics calculations of the IRR-1 core with the WIMS and CITATION codes in the past Also, we have developed an MCNP model of the IRR-1 standard fuel for a criticality safety calculation of a spent fuel storage pool

Saint-Lupicin (Jura, étude de bâti de l’église Notre-Dame

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Aurélia Bully

2007-08-01

Full Text Available Modalités de l’opération et problématiquesL’église de Saint-Lupicin fait l’objet depuis mai 2006 d’un important chantier de restauration sous la conduite de P. Barnoud, Architecte en chef des Monuments historiques. Les travaux portent essentiellement sur le remplacement de la toiture de la nef dont l’état de dégradation menaçait la pérennité de l’ouvrage. Après que la maîtrise d’ouvrage (commune de Saint-Lupicin eut choisi de restituer une charpente à quatre pans dans l’esprit du parti d’ori...

Saint: a lightweight integration environment for model annotation.

Science.gov (United States)

Lister, Allyson L; Pocock, Matthew; Taschuk, Morgan; Wipat, Anil

2009-11-15

Saint is a web application which provides a lightweight annotation integration environment for quantitative biological models. The system enables modellers to rapidly mark up models with biological information derived from a range of data sources. Saint is freely available for use on the web at http://www.cisban.ac.uk/saint. The web application is implemented in Google Web Toolkit and Tomcat, with all major browsers supported. The Java source code is freely available for download at http://saint-annotate.sourceforge.net. The Saint web server requires an installation of libSBML and has been tested on Linux (32-bit Ubuntu 8.10 and 9.04).

The features of Saint Louis

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Pierre-Yves Le Pogam

2017-12-01

Full Text Available The recent ninth centenary of the birth of Saint Louis, in 2014, gave the possibility to renew the study of the man and his reign, so important for French history, not in a nationalistic agenda or for a mere celebration, but in order to shed new light on a figure indeed profoundly studied but deserving a repeated attention, so much Louis IX lends to many-sided, even contradictory explanations. In the past, one has paid an almost maniacal attention to the point of the physical appearance of the king, looking in some images for a reflection of, or indeed a portrait of Saint Louis. Or, on the contrary and more recently, one has denied any validity to this trend of studies. In line with the essay I devoted on this question in the catalogue of the recent exhibition on Saint Louis in Paris, I would like here to go further in the analysis, especially regarding the meaning of details of the dress and bodily features of the saint king.

Theoretical study for ICRF sustained LHD type p-11B reactor

International Nuclear Information System (INIS)

Watanabe, Tsuguhiro

2003-04-01

This is a summary of the workshop on 'Theoretical Study for ICRF Sustained LHD Type p- 11 B Reactor' held in National Institute for Fusion Science (NIFS) on July 25, 2002. In the workshop, study of LHD type D- 3 He reactor is also reported. A review concerning the advanced nuclear fusion fuels is also attached. This review was reported at the workshop of last year. The development of the p- 11 B reactor research which uses the LHD magnetic field configuration has been briefly summarized in section 1. In section 2, an integrated report on advanced nuclear fusion fuels is given. Ignition conditions in a D- 3 He helical reactor are summarized in section 3. 0-dimensional particle and power balance equations are solved numerically assuming the ISS95 confinement law including a confinement factor (γ HH ). It is shown that high average beta plasma confinement, a large confinement factor (γ HH > 3) and the hot ion mode (T i /T e > 1.4) are necessary to achieve the ignition of the D- 3 He helical reactor. Characteristics of ICRF sustained p- 11 B reactor are analyzed in section 4. The nuclear fusion reaction rate is derived assuming a quasilinear plateau distribution function (QPDF) for protons, and an ignition condition of p- 11 B reactor is shown to be possible. The 3 of the presented papers are indexed individually. (J.P.N.)

Karl Lagerfeld obidelsja

Index Scriptorium Estoniae

2006-01-01

Moekunstnik Karl Lagerfeld kaebas kohtusse raamatu "The Beautiful Fall : Fashion, Genius and Glorious Excess in 1970s Paris" autori Alicia Drake'i. Raamat räägib Lagerfeldi noorusajast ja tema konkurentsist moekunstnik Yves Saint Laurent'iga 1970. aastate Pariisis

Earthquake Magnitude Relationships for the Saint Peter and Saint Paul Archipelago, Equatorial Atlantic

Science.gov (United States)

de Melo, Guilherme W. S.; do Nascimento, Aderson F.

2018-03-01

We have investigated several relationships between ML, M(NEIC) and Mw for the earthquakes locally recorded in the Saint Peter and Saint Paul Archipelago (SPSPA), Equatorial Atlantic. Because we only have one station in the area, we could not derive attenuation relations for events recorded at different distances at different stations. Our approach was then to compare our ML estimates with magnitudes reported by NEIC. This approach produced acceptable results particularly for epicentral distance smaller than 100 km. For distances greater that 100 km, there is a systematic increase in the residuals probable due to the lack of station correction and our inability to accurately estimate Q. We also investigate the Mw—M(NEIC) relationship. We find that Mw estimates using S-wave produce smaller residuals when compared with both M(NEIC). Finally, we also investigate the ML—Mw relationship and observe that given the data set we have, the 1:1 holds. We believe that the use of the present methodologies provide consistent magnitude estimates between all the magnitudes investigated that could be used to better assess seismic hazard in the region.

Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D

Energy Technology Data Exchange (ETDEWEB)

Richebois, E

2000-07-01

The objective of this work is to define improved 3-D core calculation methods based on the transport theory. These methods can be particularly useful and lead to more precise computations in areas of the core where anisotropy and steep flux gradients occur, especially near interface and boundary conditions and in regions of high heterogeneity (bundle with absorbent rods). In order to apply the transport theory a new method for calculating reflector constants has been developed, since traditional methods were only suited for 2-group diffusion core calculations and could not be extrapolated to transport calculations. In this thesis work, the new method for obtaining reflector constants is derived regardless of the number of energy groups and of the operator used. The core calculations results using the reflector constants thereof obtained have been validated on the EDF's power reactor Saint Laurent B1 with MOX loading. The advantages of a 3-D core transport calculation scheme have been highlighted as opposed to diffusion methods; there are a considerable number of significant effects and potential advantages to be gained in rod worth calculations for instance. These preliminary results obtained with on particular cycle will have to be confirmed by more systematic analysis. Accidents like MSLB (main steam line break) and LOCA (loss of coolant accident) should also be investigated and constitute challenging situations where anisotropy is high and/or flux gradients are steep. This method is now being validated for others EDF's PWRs' reactors, as well as for experimental reactors and other types of commercial reactors. (author)

Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D

Energy Technology Data Exchange (ETDEWEB)

Richebois, E

2000-07-01

The objective of this work is to define improved 3-D core calculation methods based on the transport theory. These methods can be particularly useful and lead to more precise computations in areas of the core where anisotropy and steep flux gradients occur, especially near interface and boundary conditions and in regions of high heterogeneity (bundle with absorbent rods). In order to apply the transport theory a new method for calculating reflector constants has been developed, since traditional methods were only suited for 2-group diffusion core calculations and could not be extrapolated to transport calculations. In this thesis work, the new method for obtaining reflector constants is derived regardless of the number of energy groups and of the operator used. The core calculations results using the reflector constants thereof obtained have been validated on the EDF's power reactor Saint Laurent B1 with MOX loading. The advantages of a 3-D core transport calculation scheme have been highlighted as opposed to diffusion methods; there are a considerable number of significant effects and potential advantages to be gained in rod worth calculations for instance. These preliminary results obtained with on particular cycle will have to be confirmed by more systematic analysis. Accidents like MSLB (main steam line break) and LOCA (loss of coolant accident) should also be investigated and constitute challenging situations where anisotropy is high and/or flux gradients are steep. This method is now being validated for others EDF's PWRs' reactors, as well as for experimental reactors and other types of commercial reactors. (author)

Three dimensions transport calculations for PWR core

International Nuclear Information System (INIS)

Richebois, E.

2000-01-01

The objective of this work is to define improved 3-D core calculation methods based on the transport theory. These methods can be particularly useful and lead to more precise computations in areas of the core where anisotropy and steep flux gradients occur, especially near interface and boundary conditions and in regions of high heterogeneity (bundle with absorbent rods). In order to apply the transport theory a new method for calculating reflector constants has been developed, since traditional methods were only suited for 2-group diffusion core calculations and could not be extrapolated to transport calculations. In this thesis work, the new method for obtaining reflector constants is derived regardless of the number of energy groups and of the operator used. The core calculations results using the reflector constants thereof obtained have been validated on the EDF's power reactor Saint Laurent B1 with MOX loading. The advantages of a 3-D core transport calculation scheme have been highlighted as opposed to diffusion methods; there are a considerable number of significant effects and potential advantages to be gained in rod worth calculations for instance. These preliminary results obtained with on particular cycle will have to be confirmed by more systematic analysis. Accidents like MSLB (main steam line break) and LOCA (loss of coolant accident) should also be investigated and constitute challenging situations where anisotropy is high and/or flux gradients are steep. This method is now being validated for others EDF's PWRs' reactors, as well as for experimental reactors and other types of commercial reactors. (author)

Matrjoshki ot kutjur

Index Scriptorium Estoniae

2008-01-01

Vene moeajakirja Vogue kümnendaks juubeliks joonistasid tuntud moekunstnikud kogu maailmast matrjoshkade eskiise. Eskiiside järgi maalisid vene meistrid poolemeetrised nukud. Nii sai ajakiri kingituseks Yves Saint Laurent'i, Versace, Prada, Dolce&Gabbana, Oscar de la Renta, Judashkini, Simatshovi ja paljude teiste matrjoshkad

A time series study of drug sales and turbidity of tap water in Le Havre, France.

Science.gov (United States)

Beaudeau, Pascal; Le Tertre, Alain; Zeghnoun, Abdelkrim; Zanobetti, Antonella; Schwartz, Joel

2012-06-01

The 80,000 inhabitants of the lower part of Le Havre obtain their water supply from two karstic springs, Radicatel and Saint-Laurent. Until 2000, the Radicatel water was settled when turbidity exceeded 3 NTU, then filtered and chlorinated, whereas the Saint-Laurent water was simply chlorinated. Our study aimed to characterize the link between water turbidity and the incidence of acute gastroenteritis (AGE). Records on drug sales used for the treatment of AGE were collected from January 1994 to June 1996 (period 1) and from March 1997 to July 2000 (period 2). Daily counts of drug sales were modeled using a Poisson Regression. We used data set 2 as a discovery set, identifying relevant (i.e. both significant and plausible) exposure covariates and lags. We then tested this model on period 1 as a replication dataset. In period 2, the daily drug sales correlated with finished water turbidity at both resources. Settling substantially modified the risk related to turbidity of both raw and finished waters at Radicatel. Correlations were reproducible in period 1 for water from the Radicatel spring. Timeliness of treatment adaptation to turbidity conditions appears to be crucial for reducing the infectious risk due to karstic waters.

Laurent series expansion of sunrise-type diagrams using configuration space techniques

International Nuclear Information System (INIS)

Groote, S.; Koerner, J.G.; Pivovarov, A.A.

2004-01-01

We show that configuration space techniques can be used to efficiently calculate the complete Laurent series ε-expansion of sunrise-type diagrams to any loop order in D-dimensional space-time for any external momentum and for arbitrary mass configurations. For negative powers of ε the results are obtained in analytical form. For positive powers of ε including the finite ε 0 contribution the result is obtained numerically in terms of low-dimensional integrals. We present general features of the calculation and provide exemplary results up to five-loop order which are compared to available results in the literature. (orig.)

Saint rulers as a category of sanctity in Orthodoxy

OpenAIRE

Jarosław Charkiewicz

2015-01-01

In the wide spectre of Orthodox human sanctity, among others, there is also a category of saint rulers. Despite the fact that it’s represented by a significant number of saints, it remains, utterly undeservedly, in the shadow of the others – more known or more deeply rooted historically. On top of that, the situation may result as well from the fact that saint rulers, as a distinct category of saint, are not separately mentioned neither during the proskomedia, nor during the intercessory pray...

A "Sacra Rappresentazione" of Saint Apollonia's Martyrdom.

Science.gov (United States)

Eramo, Stefano; Natali, Alessio; Bravi, Monia; Cella, Diana; Milia, Egle

The literary sources of Saint Apollonia's martyrdom and the evolution of Medieval and Renaissance religious drama are presented along with the compendium of a "Sacra Rappresentazione" from Italian Renaissance regarding Saint Apollonia's Martyrdom. Copyright American Academy of the History of Dentistry.

Putting in operation of Bugey 1

International Nuclear Information System (INIS)

Bertrand, Georges; Denoyer, Michel

1974-01-01

The main items of equipment involved in the running of BUGEY 1, the test procedure adopted and the results obtained are reported. The primary heat-extraction circuit is placed inside a prestressed concrete vessel and consists of: the reactor itself, the supporting structures, the exchanger and 4 turbo-blowers. The stach is made up of prismatic graphite rods forming a regular hexagonal lattice. The annular fuel element, cooled inside and outside consists of a clad natural uranium tube. The secondary circuit corresponds to the conventional part of a thermal centre. Four auxiliary boilers supply steam to the turbo-blowers, turbopumps and degassers providing residual heat evacuation at all-times. The principle of the control system is that of Saint-Laurent-des-Eaux. Trials were carried out on the site itself: blank tests, live tests, general tests. The general testing phase was divided into three periods: aptitude, starting up, trial run. The aptitude period precedes reactor loading and was foreseen to test the state of the circuits and the reliability of each function. The ultimate phase involved the pneumatic trial of the pressure vessel. After loading, two divergences were carried out in December 1971 and the automatic divergence process was adjusted. The start-up period lasted from January 1972 until the end of the same year. The power use tests took place (March 6th-October 23rd 1972) in 7 steps increasing from 100 to 1750Mw(th). A revision period was organized during the summer of 1972. The trial run extended through December 1972 and into 1973. During two years industrial operation the number of ill-timed control rod drops decreased gradually until September 1973 after which the plant ran continuously until June 1974, date of the annual shut-down. A table gives the variation in production and unavailabilities of the unit [fr

Theoretical study for ICRF sustained LHD type p-{sup 11}B reactor

Energy Technology Data Exchange (ETDEWEB)

Watanabe, Tsuguhiro (ed.)

2003-04-01

This is a summary of the workshop on 'Theoretical Study for ICRF Sustained LHD Type p-{sup 11}B Reactor' held in National Institute for Fusion Science (NIFS) on July 25, 2002. In the workshop, study of LHD type D-{sup 3}He reactor is also reported. A review concerning the advanced nuclear fusion fuels is also attached. This review was reported at the workshop of last year. The development of the p-{sup 11}B reactor research which uses the LHD magnetic field configuration has been briefly summarized in section 1. In section 2, an integrated report on advanced nuclear fusion fuels is given. Ignition conditions in a D-{sup 3}He helical reactor are summarized in section 3. 0-dimensional particle and power balance equations are solved numerically assuming the ISS95 confinement law including a confinement factor ({gamma}{sub HH}). It is shown that high average beta plasma confinement, a large confinement factor ({gamma}{sub HH} > 3) and the hot ion mode (T{sub i}/T{sub e} > 1.4) are necessary to achieve the ignition of the D-{sup 3}He helical reactor. Characteristics of ICRF sustained p-{sup 11}B reactor are analyzed in section 4. The nuclear fusion reaction rate < {sigma}{upsilon} > is derived assuming a quasilinear plateau distribution function (QPDF) for protons, and an ignition condition of p-{sup 11}B reactor is shown to be possible. The 3 of the presented papers are indexed individually. (J.P.N.)

REPRESENTATION OF THE SAINTS IN ORTHODOX ICONOGRAPHY

Directory of Open Access Journals (Sweden)

Veronica GHEORGHIȚĂ

2014-06-01

Full Text Available In Romanian iconography, the icon is described as an image of truth, expressing, strengthening and teaching the truth of orthodox faith. Adept and guardian of the byzantine style, the icon depicts the saints in their divine and human nature, but has traits that show the holiness, perfection and simplicity of their life. Given that the saints have been seen as modest, abstinent, fasting people, they have never been portrayed as overweight, but thin, with hollow cheeks and a frail physical appearance. In fact, the iconographic representations are characterized by a high ability to summarize the reality, the physical appearance of the saints being non-anatomical, disproportionate. Lately, it has been noticed in certain iconographic representations a change in painting style: to reproduce reality as faithfully as possible. The orientation toward the icon's external beauty involved the redefinition of the iconic portrait of the saints, who are depicted as human as possible.

René Goupil: patron saint of anesthetists.

Science.gov (United States)

Quintal, J

1995-06-01

René Goupil, the patron saint of anesthetists, is addressed mainly as a 17th century French surgeon who practiced his art in North America. He is also presented as a Jesuit martyr and saint. The article freely borrows from past writings of Jesuits on René Goupil.

Comportamiento de las ecuaciones de Saint-Venant en 1D y aproximaciones para diferentes condiciones en régimen permanente y variable

Directory of Open Access Journals (Sweden)

Gloria Estefany Amarís Castro

2015-07-01

Full Text Available The importance of the behavior of the Saint Venant equations and its implications for flow analysis applied to models of hydraulic transit is the main theme of this research, where the basis of the applications and uses of these mathematical models is determined and the performance is evaluated these equations in 1D and possible approaches for different conditions of a real situation using computational numerical experimentation for a section of a prismatic channel with a hydraulic section, in cases where the channel slope presents three types of conditions: supercritical, subcritical and horizontal slope for a design rate. The main objective of this research is to find a demonstration of the applicability of the Saint Venant equations for different conditions of approaching this problem from the point of view of the solution of the Saint Venant equations in one dimension. Scheme simple solution that produce useful solutions to the needs of engineering and found to be within the sewer network analysis, many factors can affect the solution of the Saint Venant equations is proposed.

Des hommes de Laurent Mauvignier : un roman de filiation ?

Directory of Open Access Journals (Sweden)

Manet van Montfrans

2012-12-01

Full Text Available Des hommes de Laurent Mauvignier est centré sur deux cousins, qui après avoir fait leur service militaire en Algérie, entre 1960 et 1962, sont rentrés dans leur village, marqués à vie par leurs expériences de la guerre. Un incident amène l’un d’eux, narrateur dans la majeure partie du récit, à reconstruire la vie de l’autre, sombré dans la déchéance, et à se remémorer peu à peu leur passé commun. On pourrait considérer ce texte comme « un roman de filiation » même s´il résiste, par le dispositif narratif mis en place par Mauvignier, à cette catégorie générique.

Prevalence of ciguatoxins in lionfish (Pterois spp.) from Guadeloupe, Saint Martin, and Saint Barthélmy Islands (Caribbean).

Science.gov (United States)

Soliño, Lucía; Widgy, Saha; Pautonnier, Anthony; Turquet, Jean; Loeffler, Christopher R; Flores Quintana, Harold A; Diogène, Jorge

2015-08-01

Lionfish (Pterois spp.) are invasive species that have recently spread throughout the Caribbean. Lionfish are available for purchase in local markets for human consumption in several islands of the region. We examined the prevalence of ciguatoxins (CTXs) in lionfish from the French Antilles, a ciguatera-endemic region. The neuroblastoma-2a (N2a) cell assay was used to assess composite cytotoxicity in 120 fish samples collected from the surrounding waters of Guadeloupe (n = 60), Saint Barthélemy Islands (n = 55) and Saint Martin (n = 5). Twenty-seven of these samples exhibited CTX-like activity by the N2a assay. Ciguatoxin (CTX) was confirmed by liquid chromatography-tandem mass spectrometry (LC-MS/MS) in multiple samples that presented highest composite toxicity levels by N2a. Those fish found to contain CTXs were all from Saint Barthélemy. Lionfish from Guadeloupe and Saint Martin did not exhibit toxin activity, although the sample size from Saint Martin was insufficient to draw any conclusions as to the incidence of CTXs. In this study, we provide information about the potential hazard of ciguatera associated with the consumption of lionfish from known endemic areas. We also demonstrate the utility of the cell-based assay combined with LC-MS/MS to assess activity and to provide structural confirmation of CTXs respectively. Copyright © 2015 Elsevier Ltd. All rights reserved.

Erosion-corrosion problems encountered during the operation of conventional plants

International Nuclear Information System (INIS)

Garaud, J.

1984-01-01

Are reported three experiments carried out in order to fight erosion-corrosion by a pH analysis on the heat exchangers of the plant Saint-Laurent-des-Eaux A, on the low pressure reheaters of conventional flame plants and on the reheater-separator vessels of pressurized water reactors (PWR). The utilization of certain amines, other than ammonia (morpholine and cyclohexylamine) may lead only to some limited improvements due to the thermal decomposition of the reagents and due to the subsequent effects they may have on the chemical characteristics of the water and on the condensate treatments. The solutions related to the chemistry modifications of the water in order to fight erosion-corrosion phenomena are in fact a palliative to conceptional errors which can be useful whenever it is impossible to do otherwise [fr

Cleanup Verification Package for the 118-B-1, 105-B Solid Waste Burial Ground

International Nuclear Information System (INIS)

Capron, J.M.

2008-01-01

This cleanup verification package documents completion of remedial action, sampling activities, and compliance criteria for the 118-B-1, 105-B Solid Waste Burial Ground. This waste site was the primary burial ground for general wastes from the operation of the 105-B Reactor and P-10 Tritium Separation Project and also received waste from the 105-N Reactor. The burial ground received reactor hardware, process piping and tubing, fuel spacers, glassware, electrical components, tritium process wastes, soft wastes and other miscellaneous debris

To build an environmental quality building. Evaluation: the HQE secondary school of Pic Saint Loup realized by the region; Construire un batiment respectueux de l'environnement. Retour d'experience: le Lycee HQE du Pic Saint Loup realise par la Region

Energy Technology Data Exchange (ETDEWEB)

Denicourt, Ch.

2004-07-01

This document presents the action realized in Pic Saint Loup secondary school, concerning the program management of an environmental quality building (HQE). The 8 chapters details the realization of the HQE building, the project planing of a HQE building, the Pic Saint Loup project, the operation beginning, the planing implementing, the project feasibility evaluation, the program redaction and the time and cost evaluation. (A.L.B.)

African Journals Online: Saint Kitts and Nevis

African Journals Online (AJOL)

African Journals Online: Saint Kitts and Nevis. Home > African Journals Online: Saint Kitts and Nevis. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register · Browse By Category · Browse Alphabetically · Browse By Country · List All Titles · Free to read Titles This Journal is ...

Saint Lucia revisited.

Science.gov (United States)

Bos, R; Février, M; Knudsen, A B

1988-10-01

The eastern Caribbean island of Saint Lucia is now famous in parasitological history as the setting for a major programme of schistosomiasis control'. Perhaps less well-known are the island's effective control of many intestinal parasites, and elimination of malaria, such that the current patterns of mortality and other demographic indicators now resemble those of industrialized countries. More recently, the island has become the focus for another community-based health programme as the Caribbean region again comes to grips with Aedes aegypti and its recently imported relative, Aedes albopictus, important vectors of yellow fever and dengue viruses (see Box 1).

Saint Benedict of Palermo in Spain

Directory of Open Access Journals (Sweden)

Bernard VINCENT

2016-06-01

Full Text Available Among the devotions to the black Saints, the one of which Benedict of Palermo was the object in Spain in the 17th and 18th centuries was the most remarkable. Born near Palermo to African slaves, this lay brother of a Sicilian franciscan convent, died in the odor of sanctity in 1589. His immediate popularity, encouraged both by the Church and by the Hispanic monarchy, was considerable within the communities of slaves and free blacks. Benedict was beatified in 1743, event which was followed by numerous celebrations and his eventual canonization in 1807. The fervour which surrounded him fade gradually because of the competition represented by the devotion to other black saints and by the very visible decline of slavery. However, thanks to the efforts of the franciscan order, the worship of Saint Benoît of Palermo continued until our days, particularly in Galicia.

ALICE takes root in Saint-Genis-Pouilly

CERN Multimedia

Patrice Loiez

2004-01-01

To celebrate the CERN 50th anniversary and to emphasize the close ties between the community of Saint-Genis-Pouilly, CERN and the ALICE Collaboration, Hubert Bertrand, Mayor of Saint-Genis-Pouilly and Christian Fabjan, Technical Coordinator of the ALICE Experiment, planted a tree on Saturday 16 October 2004 in front of the Jean Monet Culture Center.

ALICE takes root in Saint-Genis-Pouilly

CERN Multimedia

2004-01-01

To celebrate the CERN 50th anniversary and to emphasize the close ties between the community of Saint-Genis-Pouilly, CERN and the ALICE Collaboration, Hubert Bertrand, Mayor of Saint-Genis-Pouilly and Christian Fabjan, Technical Coordinator of the ALICE Experiment, planted a tree on Saturday 16 October 2004 in front of the Jean Monet Culture Center.

Hématome spontané de la surrénale (à propos de 2 cas)

African Journals Online (AJOL)

ra

M. El Baghouli, A. Sahnoun, A. Debbagh, A. Joual, S. Bennati et F. Meziane. Service d'Urologie, CHU Ibn Rochd, Casablanca, Maroc ... Correspondance: Dr. Mohamed EL BAGHOULI, 173 Rue Saint Laurent, App n° 13, 09000 Casablanca, MAROC, elbaghoulim@yahoo.fr. Détails d'acceptation : article reçu: 27/9/2008.

The church Saint-Symphorien in Nuits-Saint-Georges. An architectural and decorative syncretism, ca 1220-1240

Directory of Open Access Journals (Sweden)

Sylvain Demarthe

2011-12-01

Full Text Available Saint Symphorian’s church in Nuits-Saint-Georges (Burgundy, which dates from near 1220-1240, is situated during the transition of two architectural styles and attests a local but rather backward-looking Cistercian legacy that some Gothic urban and more innovative elements modernize. Moreover the church takes part, for the same reasons as those in Agencourt, Gerland and Prissey, in the surprising wave of reconstructions which denotes among others the important economic development of the country of Cîteaux at the beginning of the 13th century.

Who is Jesus Christ for the Ruthenian and Russian Saints? A Theological Exploration of St Dimitry Rostovsky’s The Lives of the Saints

Directory of Open Access Journals (Sweden)

Krzysztof Leśniewski

2014-12-01

Full Text Available Christian hagiography reveals not only the facts of life of individual saints, but first of all, it is a description of theexperience of God loving mankind. From the beginning of Christianity, of great importance in building faith, hope andlove had had stories about those believers who responded with a particular radicalism for the prevenient love of God inthe Trinity of Persons. These stories have been written in various forms of literature.Author in the introductory part of the article introduces into the lives of the saints and their role in the Ruthenian andRussian Orthodoxy. Essentially he focuses on presenting The Menaia edited by St Dimitry Rostovski. This book waspublished in the years 1711 to 1718 in Old Church Slavonic. At the beginning of the twentieth century, it has been rewrittenand translated into Russian. This monumental work appeared in the years 1903-1911 under the title The Lives of theSaints. It has been a rich source of information for researchers from many disciplines.From a theological point of view, the author studied The Lives of the Saints in order to find direct references to theperson and teaching of Jesus Christ. For this purpose, he analyzed quotations from the New Testament, especially fromthe Gospel, referring directly to the Person and teaching of Jesus Christ, as well as the prayers addressed to Him. In hisanalysis, he searched for answers to the questions: Who is Jesus Christ for the Ruthenian and Russian saints, and whatkind of His images predominate in The Lives of the Saints.The first part of the article, on the basis of source texts, indicates personal qualities of Jesus Christ. The Savior hasbeen experienced by the Ruthenian and Russian saints as God who is close to man, the blessed King, the best Lord, theComforter of the crying, the Light, the merciful God, and the Foundation of all good. The image of Christ as sinless,innocent suffering and merciful shines especially in the devotion of Saints Passion

Screening of "Particule Fever" at Saint-Genis

CERN Multimedia

Brice, Maximilien

2015-01-01

La Mission Permanente de la France auprès des Nations Unies organise une projection gratuite du film "Particle Fever" jeudi 19 février 2015 à 19h30 au théâtre du Bordeau de Saint-Genis-Pouilly. Ce partenariat avec le CERN et la Ville de Saint-Genis-Pouilly permet de comprendre, au travers de ce film captivant, l'activité du CERN.

The sacred disease and its patron saint.

Science.gov (United States)

Fatović-Ferencić, S; Dürrigl, M A

2001-08-01

Although the Hippocratic natural theory of epilepsy as a brain disorder originated around 400 bc , it did not begin to take root until the 18th and 19th centuries, leaving the intervening centuries dominated by mostly supernatural concepts. This article provides historical insight into human behavior when afflicted with disease: supplication to a patron saint, Saint Valentine, a cult that spread throughout Europe.

Mark I 1/5-scale boiling water reactor pressure suppression experiment. Quick-look report for test numbers 1.0(a) and 1.0(b) performed on March 4 and 8, 1977

International Nuclear Information System (INIS)

McCauley, E.W.; Pitts, J.H.

1977-01-01

The experimental results obtained from pressure suppression experiment numbers 1.0(a) and 1.0(b) that were performed on the Lawrence Livermore Laboratory's 1 / 5 -scale boiling water reactor (BWR) Mark I pressure suppression experimental facility are summarized

CONTAIN LMR/1B-Mod.1, A computer code for containment analysis of accidents in liquid-metal-cooled nuclear reactors

International Nuclear Information System (INIS)

Murata, K.K.; Carroll, D.E.; Bergeron, K.D.; Valdez, G.D.

1993-01-01

The CONTAIN computer code is a best-estimate, integrated analysis tool for predicting the physical, chemical, and radiological conditions inside a nuclear reactor containment building following the release of core material from the primary system. CONTAIN is supported primarily by the U. S. Nuclear Regulatory Commission (USNRC), and the official code versions produced with this support are intended primarily for the analysis of light water reactors (LWR). The present manual describes CONTAIN LMR/1B-Mod. 1, a code version designed for the analysis of reactors with liquid metal coolant. It is a variant of the official CONTAIN 1.11 LWR code version. Some of the features of CONTAIN-LMR for treating the behavior of liquid metal coolant are in fact present in the LWR code versions but are discussed here rather than in the User's Manual for the LWR versions. These features include models for sodium pool and spray fires. In addition to these models, new or substantially improved models have been installed in CONTAIN-LMR. The latter include models for treating two condensables (sodium and water) simultaneously, sodium atmosphere and pool chemistry, sodium condensation on aerosols, heat transfer from core-debris beds and to sodium pools, and sodium-concrete interactions. A detailed description of each of the above models is given, along with the code input requirements

Benchmark testing of Canadol-2.1 for heavy water reactor

International Nuclear Information System (INIS)

Liu Ping

1999-01-01

The new version evaluated nuclear data library of ENDF-B 6.5 has been released recently. In order to compare the quality of evaluated nuclear data CENDL-2.1 with ENDF-B 6.5, it is necessary to do benchmarks testing for them. In this work, CENDL-2.1 and ENDF-B 6.5 were used to generated the WIMS-69 group library respectively, and benchmarks testing was done for the heavy water reactor, using WIMS5A code. It is obvious that data files of CENDL-2.1 is better than that of old WIMS library for the heavy water reactors calculations, and is in good agreement with those of ENDF-B 6.5

Thermal and fast reactor benchmark testing of ENDF/B-6.4

International Nuclear Information System (INIS)

Liu Guisheng

1999-01-01

The benchmark testing for B-6.4 was done with the same benchmark experiments and calculating method as for B-6.2. The effective multiplication factors k eff , central reaction rate ratios of fast assemblies and lattice cell reaction rate ratios of thermal lattice cell assemblies were calculated and compared with testing results of B-6.2 and CENDL-2. It is obvious that 238 U data files are most important for the calculations of large fast reactors and lattice thermal reactors. However, 238 U data in the new version of ENDF/B-6 have not been renewed. Only data of 235 U, 27 Al, 14 N and 2 D have been renewed in ENDF/B-6.4. Therefor, it will be shown that the thermal reactor benchmark testing results are remarkably improved and the fast reactor benchmark testing results are not improved

UNDER THE PROTECTION OF THE GOD'S SAINT. DYKANKA IMAGE OF SAINT NICHOLAS THE WONDER-WORKER AND ITS ROLE IN NIKOLAI GOGOL'S LIFE

Directory of Open Access Journals (Sweden)

Voropaev V. A.

2008-11-01

Full Text Available The article tells the history of St. Nicholas Church in Dykanka and its holy image of Saint Nicholas, examines some details of the Gogol family life, the legend of Maria Gogol-Yanovskaya's marriage and her oath in front of the Holy Saint icon.

Calculation of the source term for a S1B-sequence at a VVER-1000 type reactor. Part 1

International Nuclear Information System (INIS)

Sdouz, G.

1990-10-01

The behaviour of the source term in a VVER-1000 type reactor is calculated using the 'Source Term Code Package' (STCP). The input data are based on the russian plant Zaporozhye-5. The selected accident sequence is a small break LOCA in the hot leg followed by loss offsite and onsite electric power (S 1 B-sequence). According to the course of the calculation the results are presented and analyzed for each program. Except for the noble gases all release fractions are lower than 10 -4 . 18 refs., 10 tabs. (Author)

PREFACE: 1st International School and Conference "Saint Petersburg OPEN 2014" on Optoelectronics, Photonics, Engineering and Nanostructures

Science.gov (United States)

2014-09-01

Dear Colleagues, 1st International School and Conference "Saint Petersburg OPEN 2014" on Optoelectronics, Photonics, Engineering and Nanostructures was held on March 25 - 27, 2014 at St. Petersburg Academic University - Nanotechnology Research and Education Centre of the Russian Academy of Sciences. The School and Conference included a series of invited talks given by leading professors with the aim to introduce young scientists with actual problems and major advances in physics and technology. The keynote speakers were: Mikhail Glazov (Ioffe Physico-Technical Institute RAS, Russia) Vladimir Dubrovskii (Saint Petersburg Academic University RAS, Russia) Alexey Kavokin (University of Southampton, United Kingdom and St. Petersburg State University, Russia) Vladimir Korenev (Ioffe Physico-Technical Institute RAS, Russia) Sergey Kukushkin (Institute of Problems of Mechanical Engineering RAS, Russia) Nikita Pikhtin (Ioffe Physico-Technical Institute RAS, Russia and "Elfolum" Ltd., Russia) Dmitry Firsov (Saint Petersburg State Polytechnical University, Russia) During the poster session all undergraduate and graduate students attending the conference presented their works. Sufficiently large number of participants with more than 160 student attendees from all over the world allowed the Conference to provide a fertile ground for the fruitful discussions between the young scientists as well as to become a perfect platform for the valuable discussions between student authors and highly experienced scientists. The best student papers, which were selected by the Program Committee and by the invited speakers basing on the theses and their poster presentation, were awarded with diplomas of the conference - see the photos. This year's School and Conference is supported by SPIE (The International Society for Optics and Photonics), OSA (The Optical Society), St. Petersburg State Polytechnical University and by Skolkovo Foundation. It is a continuation of the annual schools and

The history of the missal directions of the All Saints Solemnity

Directory of Open Access Journals (Sweden)

Jan Szczych

2009-09-01

Full Text Available The cult of the saints had its beginning in the Christian ancient times. Since then it was transformed in its own celebrations in honour of All the Saints. The official liturgy of the feast-day of Omnium Sanctorum (All Saints was stabilized in close relation to the development of collective worship of the saints in the West.  The historical liturgical witnesses from the Middle Ages and of the Trident Council time demonstrate a progressive and very natural process of establishment the missal texts of this liturgical celebration. The form of some liturgical directions in the current Missale Romanum (Latin Missal, unchanged for ages, confirms the continuity and constancy of this celebration in the history of Catholic Church. These missal directions explicitly show the same idea of celebration and timeless meaning of the All Saints Solemnity.

Plans for use of ENDF/B in reactor research in Indonesia

International Nuclear Information System (INIS)

Santoso, B.; Syaukat, A.; Subki, I.; Ganesan, S.

1989-07-01

Nuclear data are numerical constants of nature which quantify the nuclear behaviour of all elements and isotopes which make up the reactor medium and its environment, and which are needed as input for performing design calculations for safe and reliable operation of nuclear reactors. The nuclear data are available in the form of recommended values in specially formatted computerized files such as the Evaluated Nuclear Data File-B, known as ENDF/B. The development of base technology in the scheme of original reactor design calculations involves the mastering of the art of ENDF/B data processing. This paper briefly discusses the current status of this activity in Jakarta and gives an account of the future plans, with emphasis on the role of ENDF/B in reactor calculations. (author). 15 refs, 9 figs

THYDE-B1/MOD1: a computer code for analysis of small-break loss-of-coolant accident of boiling water reactors

International Nuclear Information System (INIS)

Muramatsu, Ken; Akimoto, Masayuki

1982-08-01

THYDE-B1/MOD1 is a computer code to analyze thermo-hydraulic transients of the reactor cooling system of a BWR, mainly during a small-break loss-of-coolant accidnet (SB-LOCA) with a special emphasis on the behavior of pressure and mixture level in the pressure vessel. The coolant behavior is simulated with a volume-and-junction method based on assumptions of thermal equilibrium and homogeneous conditions for two-phase flow. A characteristic feature of this code is a three-region representation of the state of the coolant in a control volume, in which three regions, i.e., subcooled liquid, saturated mixture and saturated steam regions are allowed to exist. The regions are separated by moving boundaries, tracked by mass and energy balances for each region. The interior of the pressure vessel is represented by two volumes with three regions: one for inside of the shroud and the other for outside, while other portions of the system are treated with homogeneous model. This method, although it seems to be very simple, has been verified to be adequate for cases of BWR SB-LOCAs in which the hydraulic transient is relatively slow and the cooling of the core strongly depends on the mixture level behavior in the vessel. In order to simulate the system behavior, THYDE-B1 is provided with analytical models for reactor kinetics, heat generation and conduction in fuel rods and structures, heat transfer between coolant and solid surfaces, coolant injection systems, breaks and discharge systems, jet pumps, recirculation pumps, and so on. The verification of the code has been conducted. A good predictability of the code has been indicated through the comparison of calculated results with experimental data provided by ROSA-III small-break tests. This report presents the analytical models, solution method, and input data requirements of the THYDE-B1/MOD1 code. (author)

Impact of bacteriophage Saint3 carriage on the immune evasion capacity and hemolytic potential of Staphylococcus aureus CC398.

Science.gov (United States)

Jung, Philipp; Abdelbary, Mohamed M H; Kraushaar, Britta; Fetsch, Alexandra; Geisel, Jürgen; Herrmann, Mathias; Witte, Wolfgang; Cuny, Christiane; Bischoff, Markus

2017-02-01

Livestock-associated methicillin-resistant Staphylococcus aureus (LA-MRSA) isolates of clonal complex 398 (CC398) are frequently found in Europe, and recent studies highlighted the importance of mobile genetic element (MGE) exchange for host adaptation of this lineage. Of note, one of the MGEs commonly found in human S. aureus isolates, the immune evasion cluster (IEC) harboring bacteriophage Saint3, is very rarely found in LA-MRSA CC398 isolates obtained from farm animals, but more frequently found in LA-MRSA CC398 that were retransmitted to humans. Here, we analyzed with a set of S. aureus CC398 isolates harboring/lacking φSaint3 how this MGE affects (i) phagocytosis of CC398 isolates by polymorphonuclear neutrophils (PMNs), and (ii) hemolysis of human and livestock-derived erythrocytes. Isolates lacking φSaint3 were more efficiently phagocytosed by human PMNs in whole blood phagocytosis assays than isolates harboring this bacteriophage, irrespective of their origin. Notably, a similar effect was observed when equine blood was utilized, but not detected with porcine blood. Integration of φSaint3 into LA-MRSA CC398 strains lacking this MGE confirmed these findings, as φSaint3-harboring recipients were again less efficiently ingested by PMNs in equine and human blood than their parental strains. Integration of φSaint3 strongly reduced the hemolytic potential of the culture supernatants against human-derived erythrocytes, and to a smaller extent also against porcine-derived erythrocytes, while φSaint3 integration only slightly affected the hemolytic capacities against equine-derived red blood cells. The significant protective effect of φSaint3 against phagocytosis by equine PMNs suggests that the host specificity of the IEC components might be broader than currently assumed. Copyright © 2016 Elsevier B.V. All rights reserved.

Comparative analysis between P1 and B1 equations for neutron moderation

International Nuclear Information System (INIS)

Martinez, Aquilino Senra; Silva, Fernando Carvalho da; Cardoso, Carlos Eduardo Santos

2000-01-01

In order to calculate the neutron flux in nuclear reactors, B1 or P1 equations are solved by numerical methods for several groups of energy. The neutron fluxes obtained from the solutions of the B1 and P1 equations are similar when they are applied to large nuclear power reactors. However, an important difference between the two fluxes is that the system of P1 equations uses one more approximation than the B1 system and then, its flux is less precise. The present work shows the relations between both equations and analyzes for what conditions the two equations systems are equivalent. Furthermore, this equations are numerically solved in 54 groups of energy for a quadrangular arrange. (author)

Energy Transition Initiative: Island Energy Snapshot - Saint Martin/Sint Maarten

Energy Technology Data Exchange (ETDEWEB)

2015-09-01

This profile provides a snapshot of the energy landscape of the northeast Caribbean island Saint Martin. The island is divided between two nations, France in the north (Saint-Martin) and the Netherlands in the south (Sint Maarten).

Virological Surveillance of Dengue in Saint Martin and Saint Barthélemy, French West Indies, Using Blood Samples on Filter Paper

Science.gov (United States)

Matheus, Séverine; Chappert, Jean-Loup; Cassadou, Sylvie; Berger, Franck; Labeau, Bhetty; Bremand, Laetitia; Winicki, Alain; Huc-Anais, Patricia; Quenel, Philippe; Dussart, Philippe

2012-01-01

To strengthen active dengue surveillance in Saint Martin and Saint Barthélemy, two French Caribbean islands, we evaluated the epidemiological usefulness of collecting blood samples from NS1-positive dengue patients on filter paper to identify the dengue serotypes circulating in these regions during a 27-month period. This approach allowed dengue serotypes to be identified by reverse transcriptase-polymerase chain reaction in 90.1% of the total set of 666 samples analyzed and, in 95.5% of the samples collected during the acute phase of the disease. This prospective virological surveillance using blood samples absorbed onto filter paper, which were stored at 4°C and shipped at ambient temperature to a specialized laboratory for analysis, allowed us to avoid the logistic and financial costs associated with shipping frozen venous blood samples. This surveillance system offers a low-cost alternative for reinforcing dengue prevention in areas where specialized laboratories do not exist, notably by facilitating the early detection of potentially new dengue serotypes. PMID:22232467

Habitat heterogeneity in the assemblages and shell use by the most abundant hermit crabs (Anomura: Diogenidae and Paguridae: does the occupied shell species differ according to gender and species?

Directory of Open Access Journals (Sweden)

Gilson Stanski

Full Text Available Abstract The goal of this study was to identify patterns of shell occupation by different species of hermit crabs from the southern Brazilian coast. In total, 644 individuals were collected, represented by six hermit species. Isocheles sawayai Forest & Saint Laurent, 1968 showed the highest abundance, with 575 individuals, followed by Loxopagurus loxochelis (Moreira, 1901 (n = 56. The other species were Petrochirus diogenes (Linnaeus, 1758, Dardanus insignis (Saussure, 1858, Pagurus exilis (Benedict, 1892 and Pagurus leptonyx Forest & Saint Laurent, 1968. Loxopagurus loxochelis was found associated with shells of 12 gastropod species, with 75% of males occupying shells of Olivancilaria urceus (Roding, 1798 and 78% of females inhabiting shells of Semicassis granulata (Born, 1778. Shells of Semicassis granulata were the lightest of all gastropod shells, demonstrating differential resource utilization. Additionally, I. sawayai occupied shells of 10 species, highlighting Stramonita haemastoma (Linnaeus, 1767 with the highest occupation percentage in all demographic classes, confirming a pattern of occupation with a strong relationship to the availability of the resource. The comparison of our results with those of other studies corroborated the influence of region and gastropod diversity on gastropod shell occupation.

EDF decommissioning programme a global commitment to safety, environment and cost efficiency of nuclear energy

International Nuclear Information System (INIS)

Grenouillet, J.-J.

2002-01-01

EDF has 9 NPPs permanently shutdown and under decommissioning. EDF considers that if the nuclear option is to remain open, it is necessary to deal with increasing public concerns for environmental and waste management issues. Therefore EDF has decided to achieve total dismantling of all shutdown reactor in the next 25 years. The Decommissioning Program has been developed including 2 stages of activities. The first stage consists of: 1) Final dismantling of Brennilis in 2015; 2) A dismantling demonstration of a PWR reactor building (Chooz A) before starting replacing the population of PWRs currently in operation; 3) Final dismantling of reactor containment of a GCR (Bugey 1) as a first of its kind. The second stage includes: 1)Dismantling of following 5 GCR (Saint Laurent A1 and A2, Chinon A1, A2 and A3); 2) Final dismantling of Chooz A and Bugey 1 in 2025. The successful implementation relies on the simplification of the regulatory process; availability of treatment, conditioning and disposal facilities and effective nuclear industry. The main issue is availability of time and waste solutions such as opening of a Very Low Waste disposal in 2003 (130 000 tons); opening of a new disposal for graphite and radiferous wastes (17 000 tons) in 2010 and opening in 2007-2008 of a centralized interim storage (BANEDA) facility for long-lived Medium Level Wastes (500 tons including filters, control rods etc)Three investigations are to be carried out for high level radioactive waste before 2006

Coupling of tertiary and quaternary changes in human hemoglobin: A 1D and 2D NMR study of hemoglobin Saint Mande (βN102Y)

International Nuclear Information System (INIS)

Craescu, C.T.; Blouquit, Y.; Mispelter, J.

1990-01-01

Hemoglobin Saint Mande (βN102Y) is a low-affinity mutant with the substitution site situated in the quaternary-sensitive α 1 β 2 interface. In adult hemoglobin the Asn102β contributes to the stability of the liganded (R) state, forming a hydrogen bond with Asp94α. The quaternary and tertiary perturbations subsequent to the Tyr for Asn substitution in monocarboxylated hemoglobin Saint Mande have been investigated by one-and two-dimensional nuclear magnetic resonance (NMR) spectroscopy. Analysis of the one-dinensional NMR spectra of the liganded and unliganded samples in 1 H 2 O provides evidence that both R and T quaternary structures of Hb Saint Mande are different from the corresponding ones in HbA. In the monocarboxylated form of the mutant hemoglobin, at acid pH, the authors have observed the disappearance of an R-type hydrogen bond and the appearance of a new one whose proton resonates like a deoxy T marker. Using two-dimensional NMR methods and on the basis of previous results on the monocarboxylated HbA, they have obtained a significant number of resonance assignments in the spectra of monocarboxylated Hb Saint Mande at pH 5.6 in the presence or absence of a strong allosteric effector, inositol hexaphosphate. This enabled us to characterize the tertiary conformational changes triggered by the quaternary-state modification. The observed structural variations are confined within the heme pocket regions but concern both the α and β subunits

Use of the VR-1 ''Vrabec'' training reactor

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Krops, S.; Polach, S.; Sklenka, L.

1994-01-01

An overview is presented of the extent and ways of using the VR-1 training reactor, which is operated by the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. A list and the characteristics of 16 problems developed for teaching purposes is given, and the 14 faculties and 2 research institutes participating in the teaching activities are listed. The reactor is used in the education and training of nuclear scientists and engineers. The instrumentation, experimental, handling and operating tools, as well as documentation and texts relating to the reactor are described. The following examples of the teaching activities are included: a guided visit to the operating reactor site, reactor dynamics study and delayed neutron measurement, training course, and the basic criticality experiment. Nuclear safety aspects (hypothetical accidents, quality control and system qualification demonstration, safety culture) are stressed during the education. The reactor department is involved in international cooperation projects. (J.B.). 3 refs

Béatrice Laurent (ed.), Sleeping Beauties in Victorian Britain, Cultural, Literary and Artistic Explorations of a Myth

OpenAIRE

Lambert-Charbonnier, Martine

2015-01-01

Sleeping Beauties in Victorian Britain is a remarkable collection of articles which uses the interdisciplinary approach to examine a whole network of correspondences between the arts, literature and science, thus conjuring up a new powerful picture of Victorian culture and its tensions over the last three decades of the 19th century. In her article “The Strange Case of the Victorian Sleeping Maid”, Béatrice Laurent, who edited the collection, describes the motif of the Sleeping Beauty as “a c...

the vision of divine light in saint gregory palamas's theology

African Journals Online (AJOL)

in Romania. 2. THE RECEPTION OF SAINT GREGORY PALAMAS'S. THEOLOGY IN THE WEST. In the West, the reception of Saint Gregory Palamas's theology, as it is known, was rather a negative one. His doctrine of divine light was rejected, because it postulated the possibility of seeing God with corporeal eyes. (Lossky ...

La collégiale Saint-Étienne de Neuvy-Saint-Sépulchre (Indre The collegiate church of Saint-Étienne at Neuvy-Saint-Sépulchre (Indre, France. A recent building survey of the rotunda and the nave

Directory of Open Access Journals (Sweden)

Simon Bryant

2006-05-01

Full Text Available La collégiale Saint-Étienne à Neuvy-Saint-Sépulchre (Indre est un des rares édifices subsistants en France qui soit conçu comme une copie de l’église du Saint-Sépulcre de Jérusalem. L’étude archéologique, réalisée pendant des travaux, a permis de préciser les étapes de son évolution depuis sa fondation dans les années 1040. La rotonde, avec ses onze piliers centraux, a été ajoutée à l’extrémité ouest d’une église antérieure. Le mur extérieur a été achevé dans cette première phase mais la cage centrale, qui abritait l’édicule, n’a été terminée qu’au début du XIIe s. Pendant la deuxième moitié du XIIe s., l’église est profondément remaniée et sans doute raccourcie avec la création d’un chevet plat. La voûte primitive est remplacée par trois travées de croisées d’ogives. L’édifice sert de refuge pendant la guerre de Cent Ans, ce qui provoque certains dégâts, partiellement réparés. Malgré les ruptures évidentes dans la construction et un plan irrégulier, l’étude montre que l’édifice est le résultat de la poursuite d’un projet architectural cohérent et original visant à évoquer l’église du Saint-Sépulcre de Jérusalem.The collegiate church of Saint-Étienne at Neuvy-Saint-Sépulchre (Department of the Indre, France is one of the few surviving rotundas built as a copy of the Holy-Sepulcre of Jerusalem during the mid 11th century. Many theories have been advanced concerning the history and the dating of this unusual monument. A recent building survey, carried out during restoration work, has managed to clarify the main phases of its evolution. The rotunda, with eleven central pillars placed around the reliquary monument, was added onto the west end of an existing church during the 1040’s. The two upper stories of the central cage, however, were not finished until the early 12th century. During the second half of the 12th century, the church was extensively

The introduction of Melanoides tuberculata (Mollusca: Thiaridae) to the island of Saint Lucia (West Indies) and its role in the decline of Biomphalaria glabrata, the snail intermediate host of Schistosoma mansoni.

Science.gov (United States)

Pointier, J P

1993-06-01

A malacological survey was carried out in May 1992 in the whole hydrographic system of Saint Lucia 11 years after the end of a biological control programme to eliminate Biomphalaria glabrata, the snail intermediate host of Schistosoma mansoni. A competitor snail, Melanoides tuberculata, was introduced to Saint Lucia in 1978 and field experiments in several habitats were conducted by Prentice between 1978 and 1986. At the present time M. tuberculata is the most common freshwater snail in Saint Lucia. The results of the survey, undertaken in sites where B. glabrata occurred in large populations in the past showed (i) the absence of the snail hosts from seven sites now extensively colonized by the competitor (ii) the presence of B. glabrata in low or very low densities in 17 sites together with the competitor and (iii) the presence of the intermediate hosts in large populations in only two sites where M. tuberculata was absent. These results confirm the positive results observed by Prentice. The presence of another planorbid snail, B. straminea, is reported for the first time in Saint Lucia.

Microseismic noise in the Saint Peter and Saint Paul Archipelago, equatorial Atlantic

Science.gov (United States)

de Queiroz, Daniel É.; do Nascimento, Aderson F.; Schimmel, Martin

2017-12-01

Microseismic noise, also known as ambient seismic noise, are continuous vibrations mostly composed of Rayleigh waves pervasively recorded in the mili Hertz to 1 Hz frequency range. Their precise source mechanisms are under investigations and related to atmospheric perturbations and ocean gravity waves. Our purpose is to show the behavior of the microseismic noise recorded in the Saint Peter and Saint Paul Archipelago (SPSPA) with respect to wind intensity and ocean waves height in this region, between the North and South Atlantic Ocean. We have recorded both primary microseisms (PM) 0.04-0.12 Hz and the secondary microseisms (SM) 0.12-0.4 Hz during almost four years (2012-2015) and we used frequency, temporal, spatial and statistical correlation analysis to do qualitative and quantitative analysis with respect to wind speed intensity and significant wave height for the same periods. The results indicate a good correlation between the PM and the SM noise in the region particularly during the winter in the Northern Hemisphere and a poor correlation during the summer. We have also shown that probably most of the PM are generated in the SPSPA itself. We note that the intensity of SM recorded in SPSPA appears to have a seasonal behavior with the summer and winter in the Northern Hemisphere, and seems to influence the correlation between the PM and the SM, suggesting that the sources of the PM and the SM are not related to the same atmospheric event and from different places. PM generation would occur near the SPSPA whilst the SM would have distant sources towards the North Atlantic.

A New Pilgrimage in Portugal: Following the Steps of Saint Nuno

Directory of Open Access Journals (Sweden)

Carla Braga

2013-12-01

Full Text Available Tourism is an ever-changing reality. Pilgrimages need different stimuli to attract new followers. In this context we propose to create an itinerary following the steps of Saint Nuno of Santa Maria, canonized in 2009. Nuno Álvares Pereira was the real name of Saint Nuno, who was granted the title Constable of Portugal, and became a historic legend in the independence wars of Portugal during the political crisis of 1383-1385. After fighting against the power of Castile (Spain he decided to devote his life to religion as a Carmelite Friar. He represents the perfect hero of the Middle Ages - associating military prowess with a religious character. Our proposal is to create a religious itinerary based on facts of Saint Nuno’s life, so that any visitor may easily discover the country following the steps of this saint who was deeply devoted to the Virgin - in fact, all temples he founded and restored were dedicated to Our Lady. One of his most famous foundations is the Carmelite Convent in Lisbon, which long after his death was an outstanding popular pilgrimage place, and today is still a strong visitor attraction. This exploratory study is based on literature review and text analyses about religious tourism, itinerary design and the life of the saint. The fieldwork includes acknowledging the different sites related to the saint. We believe that it is possible to create an original religious itinerary in Portugal, which will attract not only foreigners but also domestic visitors, increasing the ‘Production and Consumption of the Pilgrimage Tourism Experience’.

Comparative analysis between P1 and B1 equations for neutron moderation; Analise comparativa entre os metodos de obtencao e das solucoes das equacoes P1 e B1 para moderacao de neutrons

Energy Technology Data Exchange (ETDEWEB)

Martinez, Aquilino Senra; Silva, Fernando Carvalho da; Cardoso, Carlos Eduardo Santos [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

2000-07-01

In order to calculate the neutron flux in nuclear reactors, B1 or P1 equations are solved by numerical methods for several groups of energy. The neutron fluxes obtained from the solutions of the B1 and P1 equations are similar when they are applied to large nuclear power reactors. However, an important difference between the two fluxes is that the system of P1 equations uses one more approximation than the B1 system and then, its flux is less precise. The present work shows the relations between both equations and analyzes for what conditions the two equations systems are equivalent. Furthermore, this equations are numerically solved in 54 groups of energy for a quadrangular arrange. (author)

On elevated fluoride and boron concentrations in groundwaters associated with the Lake Saint-Martin impact structure, Manitoba

International Nuclear Information System (INIS)

Desbarats, Alexandre J.

2009-01-01

Hydrogeological investigations conducted by the Geological Survey of Canada in the Lake Saint-Martin region of Manitoba have confirmed earlier reports of naturally elevated F - and B concentrations in local groundwaters. Fluoride and B concentrations are highly correlated (r 2 = 0.905) and reach 15.1 mg/L and 8.5 mg/L, respectively. Virtually all groundwaters with F - concentrations greater than the drinking water limit of 1.5 mg/L are from wells within the Lake Saint-Martin impact structure, a 208 Ma complex crater 23 km in diameter underlying a large part of the study area. The high-F - groundwaters can be classified into two groups according to their anionic and isotopic compositions. Group I samples consist of Na-mixed anion groundwaters, with Cl greater than 100 mg/L and highly depleted 18 O compositions indicative of recharge under much cooler climatic conditions than at present. Samples belonging to this group exhibit a striking relationship to crater morphology, and are found in an arcuate belt within the southern rim of the impact structure. Group II high-F - samples consist of Na-HCO 3 -SO 4 groundwaters, with little Cl, and less depleted 18 O compositions. Samples belonging to this group are associated with groundwaters recharged locally, on a low ridge within the impact structure. This paper traces the probable source of high-F - groundwaters to phosphatic pellets in shales of the Winnipeg Formation, a regional basal clastic unit which sub-crops at shallow depth beneath the crater rim as a result of more than 200 m of structural uplift associated with the impact event. This extensive aquifer is known elsewhere in southern Manitoba for its naturally-softened groundwaters and locally elevated F - concentrations. Group I groundwaters are interpreted as discharge from the Winnipeg Formation where it abuts against crater-fill deposits. Group II high-F - groundwaters are interpreted as modern recharge from within the impact structure, displacing Group I

Calculation of Void in the Fort Saint Vrain Material

Energy Technology Data Exchange (ETDEWEB)

Potter, David Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Taylor, Craig Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Coons, James Elmer [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-05-11

The percent void of the Fort Saint Vrain (FSV) material is estimated to be 21.1% based on the volume of the gap at the top of the drums, the volume of the coolant channels in the FSV fuel element, and the volume of the fuel handling channel in the FSV fuel element.

Poétique de l’invective dans les Poèmes aristophanesques de Laurent Tailhade

Directory of Open Access Journals (Sweden)

Laurent Robert

2012-04-01

Full Text Available Parmi l’abondant corpus traité par Marc Angenot dans La Parole pamphlétaire, les ouvrages de Laurent Tailhade Au Pays du mufle et À travers les Grouins [sic] constituent les seuls recueils poétiques. L’essayiste y voit une illustration du genre de la satire poétique, revivifié dès la fin du xviiie siècle avec les Iambes d’André Chénier, puis au xixe notamment par Auguste Barbier et Victor Hugo. Tailhade pourrait ainsi, superficiellement, être considéré comme le poète satiriste de la Troisième...

Cationic lipid-formulated DNA vaccine against hepatitis B virus: immunogenicity of MIDGE-Th1 vectors encoding small and large surface antigen in comparison to a licensed protein vaccine.

Directory of Open Access Journals (Sweden)

Anne Endmann

Full Text Available Currently marketed vaccines against hepatitis B virus (HBV based on the small (S hepatitis B surface antigen (HBsAg fail to induce a protective immune response in about 10% of vaccinees. DNA vaccination and the inclusion of PreS1 and PreS2 domains of HBsAg have been reported to represent feasible strategies to improve the efficacy of HBV vaccines. Here, we evaluated the immunogenicity of SAINT-18-formulated MIDGE-Th1 vectors encoding the S or the large (L protein of HBsAg in mice and pigs. In both animal models, vectors encoding the secretion-competent S protein induced stronger humoral responses than vectors encoding the L protein, which was shown to be retained mainly intracellularly despite the presence of a heterologous secretion signal. In pigs, SAINT-18-formulated MIDGE-Th1 vectors encoding the S protein elicited an immune response of the same magnitude as the licensed protein vaccine Engerix-B, with S protein-specific antibody levels significantly higher than those considered protective in humans, and lasting for at least six months after the third immunization. Thus, our results provide not only the proof of concept for the SAINT-18-formulated MIDGE-Th1 vector approach but also confirm that with a cationic-lipid formulation, a DNA vaccine at a relatively low dose can elicit an immune response similar to a human dose of an aluminum hydroxide-adjuvanted protein vaccine in large animals.

Locality and Distance in Cults of Saints in Medieval Norway

DEFF Research Database (Denmark)

Petersen, Nils Holger

2017-01-01

A discussion of the Norwegian medieval cult of the purported Irish St Sunniva, a cult in which holiness is seen as foreign and distant in the cultural memory of the saint.......A discussion of the Norwegian medieval cult of the purported Irish St Sunniva, a cult in which holiness is seen as foreign and distant in the cultural memory of the saint....

Nuclear graphite waste's behaviour under disposal conditions: Study of the release and repartition of organic and inorganic forms of carbon 14 and tritium in alkaline media

International Nuclear Information System (INIS)

Vende, L.

2012-01-01

23000 tons of graphite wastes will be generated during dismantling of the first generation of French reactors (9 gas cooled reactors). These wastes are classified as Long Lived Low Level wastes (LLW-LL). As requested by the law, the French National Radioactive Waste Management Agency (Andra) is studying concepts of low-depth disposals.In this work we focus on carbon 14, the main long-lived radionuclide in graphite waste (5730 y), but also on tritium, which is the main contributor to the radioactivity in the short term. Carbon 14 and tritium may be released from graphite waste in many forms in gaseous phase ( 14 CO 2 , HT...) or in solution ( 14 CO 3 2- , HTO...). Their speciation will strongly affect their migration from the disposal site to the environment. Leaching experiments, in alkaline solution (0.1 M NaOH simulating repository conditions) have been performed on irradiated graphite, from Saint-Laurent A2 and G2 reactors, in order to quantify their release and characterize their speciation. The studies show that carbon 14 exists in both gaseous and aqueous phases. In the gaseous phase, release is weak (≤0.1%) and corresponds to oxidizable species. Carbon 14 is mainly released into liquid phase, as both inorganic and organic species. 65% of released fraction is inorganic and 35% organic carbon. Two tritiated species have been identified in gaseous phase: HTO and HT/Organically Bond Tritium. More than 90% of tritium in that phase corresponds to HT/OBT. But release is weak (≤0.1%). HTO is mainly in the liquid phase. (author)

Attempt of application of prefabrication techniques to nuclear engineering

International Nuclear Information System (INIS)

Frangi, Roger

1981-01-01

Prefabrication can apply to nuclear civil engineering for the execution of complicated or tall shuttering or casing work, requiring shoring that one would wish to simplify or suppress. This technique saves on work hours and improves quality and safety. A few examples carried out on the Saint-Laurent-des-Eaux and Chinon power stations are given as well as that which will be undertaken on the Belleville power station [fr

Nuclear Safeguards Considerations For The Pebble Bed Modular Reactor (PBMR)

Energy Technology Data Exchange (ETDEWEB)

Phillip Casey Durst; David Beddingfield; Brian Boyer; Robert Bean; Michael Collins; Michael Ehinger; David Hanks; David L. Moses; Lee Refalo

2009-10-01

High temperature reactors (HTRs) have been considered since the 1940s, and have been constructed and demonstrated in the United Kingdom (Dragon), United States (Peach Bottom and Fort Saint Vrain), Japan (HTTR), Germany (AVR and THTR-300), and have been the subject of conceptual studies in Russia (VGM). The attraction to these reactors is that they can use a variety of reactor fuels, including abundant thorium, which upon reprocessing of the spent fuel can produce fissile U-233. Hence, they could extend the stocks of available uranium, provided the fuel is reprocessed. Another attractive attribute is that HTRs typically operate at a much higher temperature than conventional light water reactors (LWRs), because of the use of pyrolytic carbon and silicon carbide coated (TRISO) fuel particles embedded in ceramic graphite. Rather than simply discharge most of the unused heat from the working fluid in the power plant to the environment, engineers have been designing reactors for 40 years to recover this heat and make it available for district heating or chemical conversion plants. Demonstrating high-temperature nuclear energy conversion was the purpose behind Fort Saint Vrain in the United States, THTR-300 in Germany, HTTR in Japan, and HTR-10 and HTR-PM, being built in China. This resulted in nuclear reactors at least 30% or more thermodynamically efficient than conventional LWRs, especially if the waste heat can be effectively utilized in chemical processing plants. A modern variant of high temperature reactors is the Pebble Bed Modular Reactor (PBMR). Originally developed in the United States and Germany, it is now being redesigned and marketed by the Republic of South Africa and China. The team examined historical high temperature and high temperature gas reactors (HTR and HTGR) and reviewed safeguards considerations for this reactor. The following is a preliminary report on this topic prepared under the ASA-100 Advanced Safeguards Project in support of the NNSA Next

A restoration and conservation project of the “Saint Dominic” Monastery in Soriano Calabro, Italy

Directory of Open Access Journals (Sweden)

Nazzareno Davolos

2008-04-01

Full Text Available The article is extracted from the Master Thesis about Restoration of the Monuments at “La Sapienza”, University of the Studies of Rome. The Monastery was one of the most important of the Dominican Order in Europe. The building dates back to year 1510, it broke down almost completely in the earthquake of year 1659. It was rebuilt following the architect B. Presti’s project. At the present time the “Saint Domenic” Monastery largely seems a ruin, mainly as a consequence of the cat- N. Davolos - A restoration and conservation project of the ÒSaint DominicÓ Monastery... 185 astrophic earthquake in 1783. However, with the new look that has acquired, it still preserves an extraordinary charm that continues to astonish. The project followed the trend of the critical and conservative restoration with the safeguard of the artistic and figurative data of the “Saint Domenic” Monastery which has been analysed through an accurate historical-critical work. The idea is to preserve and transmit to the future generations the “Saint Domenic” monument in his authenticity, in its formal and material consistence, with the marks of the passing of time. The abstracts reports only the most important aspects which are representative of the project. Besides the historical analysis, laboratory examination have been executed on the material used in the construction of the ancient facade through the observation of thin sections by optic microscope and with the realization of spectrum of X-ray diffraction, in order to know the nature and composition, the state of preservation and the kinds of deterioration to support an appropriate intervention of restoration.

The harmonious relationship between faith and science from the perspective of some great saints: A brief comment.

Science.gov (United States)

Cortés, Manuel E; Del Río, Juan Pablo; Vigil, Pilar

2015-02-01

The objective of this editorial is to show that a harmonious relationship between science and faith is possible, as exemplified by great saints of the Catholic Church. It begins with the definitions of science and faith, followed by an explanation of the apparent conflict between them. A few saints that constitute an example that a fruitful relationship between these two seemingly opposed realities has been possible are Saint Albert the Great, Saint John of the Cross, Saint Giuseppe Moscati, and Saint Edith Stein, among others, and this editorial highlights their deep contributions to the dialogue between faith and reason. This editorial ends with a brief discussion on whether it is possible to be both a scientist and a man of faith.

Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

IRPHE/B and W-SS-LATTICE, Spectral Shift Reactor Lattice Experiments

International Nuclear Information System (INIS)

2003-01-01

Description: B and W has performed and analysed a series of physics experiments basically concerned with the technology of heterogeneous reactors moderated and cooled by a variable mixture of heavy and light water. A reactor so moderated is termed Spectral Shift Control Reactor (S SCR). In the practical application of this concept, the moderator mixture is rich in heavy water at the beginning of core life, so a relatively large fraction of the neutrons are epithermal and are absorbed in the fertile material. As fuel is consumed, the moderator is diluted with light water. In this way the neutron spectrum is shifted, thereby increasing the proportion of thermal neutrons and the reactivity of the system. The general objective of the S SCR Basic Physics Program was to study the nuclear properties of rod lattices moderated by D 2 O-H 2 O mixtures. The volume ratio of moderator to non-moderator in all lattices was approximately 1.0, and the fuel was either 4%-enriched UO 2 clad in stainless steel or 93%-enriched UO 2 -ThO 2 (Nth/N 15) pellets clad in aluminum. The D 2 O concentration in the moderator ranged from zero to about 90 mole %. The experimental program includes critical experiments with both types of fuel, exponential experiments at room temperature with both types of fuel, exponential experiments at elevated temperatures with the 4%-enriched UO 2 fuel, and neutron age measurements in ThO 2 lattices. The theoretical program included the development of calculation methods applicable to these systems, and the analysis and correlation of the experimental data. A first report provides the results of critical experiments performed under the Spectral Shift Control Reactor Basic Physics Program. A second report documents experimental results and theoretical interpretation of a series of twenty uniform lattice critical experiments in which the neutron spectrum is varied over a fairly broad range. A third report addresses issues that bear on the problems associated with

Particular intervention plan of the Saint Alban-Saint Maurice l'Exil Nuclear Power Plant

International Nuclear Information System (INIS)

2010-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Saint Alban-Saint Maurice NPP (Isere, France)

Testing ENDF/B-V data for thermal reactors

International Nuclear Information System (INIS)

Craig, D.S.

1982-10-01

Lattice parameters have been calculated for some thermal reactor benchmark lattices using ENDF/B-V data. These lattices were TRX-1, -2; BAPL-UO 2 -1,-2,-3; BNL-ThO 2 - 233 UO 2 -H 2 0-1,-2,-3; MIT-4,-5,-6; and PNL-31,-33,-35 (infinite lattices). In addition, parameters were calculated for 3 ZEEP lattices, 3 High-Conversion U0 2 -H 2 0 lattices, and 7 BNL-Th0 2 - 233 U0 2 -D 2 0 lattices. These calculations were made using the integral transport cell code RAHAB with the resonance reaction rates obtained using the OZMA code operating in the discrete ordinate mode. This code calculates the resonance rates allowing for the interaction of all resonances. Four group reaction rates for use in method comparisons are given for several lattices. The author discusses the use of the OZMA code for these calculations, including the choice of options and the orders of the angular quadratures, and compares results obtained using the CRNL thermal scattering data with those obtained using ENDF/B data

Application of a new cross section library based on ENDF/B-IV to reactor core analysis

International Nuclear Information System (INIS)

Lima Bezerra, J. de.

1991-04-01

The use of the ENDF/B-IV library in the LEOPARD code for the Angra-1 reactor simulation is presented. The results are compared to those obtained using the ENDF/B-II library and show better values for the power distribution but an underestimated global reactivity as compared to experimental results. (F.E.). 1 ref, 55 figs, 1 tab

Fast-reactor-data testing of ENDF/B-V at ORNL

International Nuclear Information System (INIS)

Wright, R.Q.; Ford, W.E. III; Lucius, J.L.; Webster, C.C.; Marable, J.H.

1982-01-01

The Cross Section Evaluation Working Group (CSEWG) is coordinating a program to assess the adequacy of ENDF/B-V cross sections for both fast- and thermal-reactor design applications. A secondary goal is to evaluate cross-section processing codes, cross-section libraries, and radiation-transport codes. Fast reactor data testing (FRDT) goals are accomplished, in part, by comparison of calculated results with documented performance parameters of CSEWG fast reactor benchmarks and with results obtained by other data testers. The purpose of this paper is to describe the results of FRDT at Oak Ridge National Laboratory

Self-consistent-field method and τ-functional method on group manifold in soliton theory. II. Laurent coefficients of soliton solutions for sln and for sun

International Nuclear Information System (INIS)

Nishiyama, Seiya; Providencia, Joao da; Komatsu, Takao

2007-01-01

To go beyond perturbative method in terms of variables of collective motion, using infinite-dimensional fermions, we have aimed to construct the self-consistent-field (SCF) theory, i.e., time dependent Hartree-Fock theory on associative affine Kac-Moody algebras along the soliton theory. In this paper, toward such an ultimate goal we will reconstruct a theoretical frame for a υ (external parameter)-dependent SCF method to describe more precisely the dynamics on the infinite-dimensional fermion Fock space. An infinite-dimensional fermion operator is introduced through Laurent expansion of finite-dimensional fermion operators with respect to degrees of freedom of the fermions related to a υ-dependent and a Υ-periodic potential. As an illustration, we derive explicit expressions for the Laurent coefficients of soliton solutions for sl n and for su n on infinite-dimensional Grassmannian. The associative affine Kac-Moody algebras play a crucial role to determine the dynamics on the infinite-dimensional fermion Fock space

Stationary low power reactor No. 1 (SL-1) accident site decontamination ampersand dismantlement project

International Nuclear Information System (INIS)

Perry, E.F.

1995-01-01

The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the building contained the reactor pressure vessel surrounded by gravel shielding. Above the pressure vessel, in the center portion of the building, was a turbine generator and plant support equipment. The upper section of the building contained an air cooled condenser and its circulation fan. The major support facilities included a 2,500 ft 2 two story, cinder block administrative building; two 4,000 ft 2 single story, steel frame office buildings; a 850 ft 2 steel framed, metal sided PL condenser building, and a 550 ft 2 steel framed decontamination and laydown building

Of volcanoes, saints, trash, and frogs

DEFF Research Database (Denmark)

Andersen, Astrid Oberborbeck

, at the same time as political elections and economic hardship. During one year of ethnographic fieldwork volcanoes, saints, trash and frogs were among the nonhuman entities referred to in conversations and engaged with when responding to the changes that trouble the world and everyday life of Arequipans...

Changes in the Population Distribution and Transport Network of Saint Petersburg

Directory of Open Access Journals (Sweden)

Xiaoling Li

2016-12-01

Full Text Available The authors explores the interdependence between demographic changes and transport network centrality, using Saint Petersburg as an example. The article describes the demographic data for the period 2002—2015 and the transportation network data of 2006. The authors employ several methods of demographic research; they identified the centre of gravity of the population, produce the standard deviational ellipsis and use the kernel density estimation. The street network centrality of Saint Petersburg was analyzed using the Multiple Centrality Assessment Model (MCA and the Urban Network Analysis Tool for ArcGIS. The analysis of the population distribution in Saint Petersburg shows that each area of the city has seen their population grow over the last thirteen years. However, it is the population of suburban areas that increased the most. The core area of the city has the tendency of outward diffusion, and the population gravity centre has been moving northwards. Spatial characteristics of the population growth, changes in the population gravity centre, the standard deviational ellipse and characteristics of the street network centrality show that Saint Petersburg is at the final stage of urbanization and its development pattern is similar to that of other major cities.

Gravimetric structure for the abyssal mantle massif of Saint Peter and Saint Paul peridotite ridge, Equatorial Atlantic Ocean, and its relation to active uplift

Directory of Open Access Journals (Sweden)

KENJI F. MOTOKI

2014-06-01

Full Text Available This paper presents gravimetric and morphologic analyses based on the satellite-derived data set of EGM2008 and TOPEX for the area of the oceanic mantle massif of the Saint Peter and Saint Paul peridotite ridge, Equatorial Atlantic Ocean. The free-air anomaly indicates that the present plate boundary is not situated along the longitudinal graben which cuts peridotite ridge, but about 20 km to the north of it. The high Bouguer anomaly of the peridotite ridge suggests that it is constituted mainly by unserpentinised ultramafic rocks. The absence of isostatic compensation and low-degree serpentinisation of the ultramafic rocks indicate that the peridotite ridge is sustained mainly by active tectonic uplift. The unparallel relation between the transform fault and the relative plate motion generates near north-south compression and the consequent tectonic uplift. In this sense, the peridotite massif is a pressure ridge due to the strike-slip displacement of the Saint Paul Transform Fault.

Please exercise extreme caution at the Saint-Genis roundabout

CERN Multimedia

2015-01-01

In the interests of enhanced safety, a new pathway for pedestrians and cyclists has been constructed around the outside of the Saint-Genis roundabout. However, the markings of the previous cycle path, which is now closed to traffic, are still visible and can cause confusion. We therefore call on everyone to exercise extreme caution and to use the new pathway.   New two-way markings have been laid out, inviting pedestrians and cyclists coming from the direction of Saint-Genis-Pouilly to go towards the Swiss border or CERN Entrance E using the left-hand side of the roundabout (i.e. the Prévessin side). So, from now on, cyclists must no longer go around the roundabout on the right-hand side and pedestrians will no longer have to cross the D884 dual carriageway. Similarly, people staying at the Saint-Genis hostel are invited to follow these new markings to get to CERN or to return to the hostel, which means they will avoid having to cross the D35 highway at a spot where traffic is...

Sanctified madness: the God-intoxicated saints of Bengal.

Science.gov (United States)

Morinis, A

1985-01-01

The saintly madman is a familiar character in South Asia. To outer appearances he is no different from a lunatic, but the mad saint comes to be revered because his idiocy is popularly believed to arise from a different cause than ordinary madness. The common psychopath neglects social conventions because his consciousness is dimmed by incapacity; the saintly madman also breaches convention, but does so because his heightened consciousness has liberated him from the bonds of convention that entrap ordinary people. In the terms of Hinduism, he has tasted the divine nectar of God-realization and has returned to the human realm intoxicated by the experience. In this paper two popular God intoxicated saints of Bengal are discussed. The question is posed whether 'God intoxication' can be considered a culture-bound syndrome of Bengal. The concept of 'culture bound syndrome' is found to be too narrow to encompass the most significant issues to arise from reflection on the characteristics of the God intoxicated. These larger issues have to do with the relationship between cultural practices and models and mental states (whether deviant, as implied by the term 'syndrome' although deviance does not always carry the negative connotation implicit in 'syndrome', or normal). It is suggested that all cultures culture a limited range of mental states and thus the questions posed by the notion of culture bound syndromes are subsumed by larger questions about the relationship of all mind-states to the socio-cultural environment which conditions them. The conclusion is that God intoxication is indeed a uniquely Bengali mental condition, with variants throughout South Asia and kinship to other mystical states, but that the concept of 'syndrome' is not useful.

President Ilves kõneles Saint Gallenis

Index Scriptorium Estoniae

2009-01-01

President Toomas Hendrik Ilves esines 9. mail 2009 Šveitsis, Saint Galleni 39. majandus- ja poliitikasümpoosionil kõnega teemal "20 aastat pärast Berliini müüri langemist - Euroopa uued väljakutsed". Vabariigi President töövisiidil Šveitsis 08.-09.05.2009

SUFI SAINTS IN KARNATAKA

Directory of Open Access Journals (Sweden)

Maruti KAMBLE

2011-01-01

Full Text Available Karnataka is one of the most important southern states of India. It has gainedprominence politically, socio-economically, philosophically and in many otherways. It is a meeting place of many religious philosophies and a melting pointhelping to achieve the synthesis of the teaching ofmany religious reforms. Sufismis a mystic religion. It is an offshoot of Islam. Sufi saints are the followers ofALLAH and the practice of peace, benevolence and tolerance. They promulgateda religion based on the concept of love, the love with the fellow being and thelove with the ultimate or the creator. Sufi saintsand Sufism are an existing realityin Indian socio-religious fold and it has contributed for a healthy and amicablesocial order. It has lead to a new social set-up full of values, and discipline.Sufism as a religion of the teaming millions becamethe practicing system amongthe people of India as well as Karnataka. This study of Sufi Saints in Karnataka isthus an inspired attempt to portray this religion of the soul and heart. Muchemphasis is laid on the concepts and special aspects of Sufism, along with variouspractices found in it. I was always attracted by its spiritual significance andpractical essence and also its profound influence on the general public. Hence, mylittle attempt to explain the same through the lifestories of some of the great Sufisaints in Karnataka.

Chooz-B1, the new Electricite de France PWR: calculation scheme of neutron leakages from the reactor cavity

International Nuclear Information System (INIS)

Champion, G.; Thiriet, A.; Vergnaud, T.; Bourdet, L.; Nimal, J.C.; Brandicourt, G.

1987-04-01

A new calculation scheme has been set up to assess the neutron field characteristics inside French PWR. In order to take into account multiple neutron scattering and the complexity of the reactor geometry, the use of Monte-Carlo methods have been heavily increased. They are coupled with classical SN.-methods. The main goal aimed at was to find out the neutron field characteristics at the level of the reactor pit openings. These radiation reference sources will be used to check the neutron shielding efficiencies. The new calculation scheme has been applied to CHOOZ-B1, the first unit of the new N4 program. The former results have been compared with the measurement results related to PALUEL-I and II PWR, two units of the previous P4 program. Although the core and the geometry are not entirely similar, it is possible to check with confidence the calculation results along the vessel and at the core midplane level with the measurement results at the same locations. It appears that they are in good agreement. Consequently, the new calculation scheme appears reliable

Reactor protection system. Revision 1

International Nuclear Information System (INIS)

Fairbrother, D.B.; Vincent, D.R.; Lesniak, L.M.

1975-04-01

The reactor protection system-II (RPS-II) designed for use on Babcock and Wilcox 145- and 205-fuel assembly pressurized water reactors is described. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W. (U.S.)

Geothermic and thermal drilling in Saint-Paul-les-Dax - SPDX 1

Energy Technology Data Exchange (ETDEWEB)

Godard, J.M.; Tronel, F.; Penicault, J.P.; Pouchan, P.

1994-12-31

In 1990, the municipality of Saint Paul les Dax (Landes), located in a thermal area, has decided to promote a geothermal-balneotherapy continued project. Geological studies and seismic exploration from oil and gas allowed to decide to drill a deep well on the northern flank of Dax diapir. The drilling operation (October - December 1993) has given the following result : final depth 1665 m, thermal reservoir dated Danian-Paleocene producing water at 66 degree celsius. The potential flowrate estimated at 150 m{sup 3}/h is going to be used to met the heating requirements of public buildings, greenhouses, collective equipment and new thermal centers. The geothermal use of the water will give annual energy saving of 5 900 MWh. (Authors). 2 figs.

Consistent initial conditions for the Saint-Venant equations in river network modeling

Directory of Open Access Journals (Sweden)

C.-W. Yu

2017-09-01

Full Text Available Initial conditions for flows and depths (cross-sectional areas throughout a river network are required for any time-marching (unsteady solution of the one-dimensional (1-D hydrodynamic Saint-Venant equations. For a river network modeled with several Strahler orders of tributaries, comprehensive and consistent synoptic data are typically lacking and synthetic starting conditions are needed. Because of underlying nonlinearity, poorly defined or inconsistent initial conditions can lead to convergence problems and long spin-up times in an unsteady solver. Two new approaches are defined and demonstrated herein for computing flows and cross-sectional areas (or depths. These methods can produce an initial condition data set that is consistent with modeled landscape runoff and river geometry boundary conditions at the initial time. These new methods are (1 the pseudo time-marching method (PTM that iterates toward a steady-state initial condition using an unsteady Saint-Venant solver and (2 the steady-solution method (SSM that makes use of graph theory for initial flow rates and solution of a steady-state 1-D momentum equation for the channel cross-sectional areas. The PTM is shown to be adequate for short river reaches but is significantly slower and has occasional non-convergent behavior for large river networks. The SSM approach is shown to provide a rapid solution of consistent initial conditions for both small and large networks, albeit with the requirement that additional code must be written rather than applying an existing unsteady Saint-Venant solver.

Saint Louis Center for Sustainment of Trauma and Readiness Skills: A Collaborative Air Force-Civilian Trauma Skills Training Program

Science.gov (United States)

2016-05-19

NUMBER 6. AUTHOR(S) Jason W. Grimm , Karen Johnson 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 7. PERFORMING ORGANIZATION...ABSTRACT SAR 18. NUMBER OF PAGES 5 19a. NAME OF RESPONSIBLE PERSON Jason Grimm a. REPORT U b. ABSTRACT U c. THIS PAGE U 19b... Grimm Karen Johns For correspo Vista at Gra J Emerg Nu 0099-1767 Published b http://dx.do ■ ■ • ■SAINT LOUIS CENTER FOR SUSTAINMENT OF TRAUMA AND

Des saints pour la fiction, des saints face à l’Histoire

Directory of Open Access Journals (Sweden)

Aude Bonord

2008-12-01

Full Text Available Pourquoi des écrivains non confessionnels (Joseph Delteil, Blaise Cendrars, Christian Bobin, Sylvie Germain, Claude Louis-Combet ont-ils choisi de réécrire des vies de saints au XXe siècle ? Le parti pris est surprenant à plusieurs titres. L’hagiographie est un genre historique et religieux, terrain a priori réservé aux historiens, aux ecclésiastiques ou aux écrivains catholiques. De plus, à la fin du siècle, l’hagiographie est sortie du champ littéraire avec la disparition du groupe des écrivains catholiques. Curieusement, nos auteurs vont s’inscrire dans ces décalages non seulement pour définir leur place par rapport à l’hagiographe traditionnel mais aussi pour s’approprier le genre. Amorces fictionnelles et objets de rêveries poétiques, les vies de saints sont soumises à la fantaisie littéraire de ces auteurs au statut improbable. Dans un dialogue avec les sources allant du jeu à la contestation, les écrivains utilisent l’intertexte hagiographique, et notamment son système narratif, pour s’évader dans le merveilleux mais encore pour penser leur époque. En effet, si éloignée de la réalité contemporaine soit-elle en apparence, l’hagiographie joue à la fois un rôle de contrepoint et de reflet du présent. La confrontation avec ces récits surgis du passé permet alors aux auteurs de repenser la marche de l’Histoire et l’inscription de l’Homme dans le temps.

THYDE-B1/MOD2: a computer code for analysis of small-break loss-of-coolant accidents of boiling water reactors

International Nuclear Information System (INIS)

Nakamura, Hideo; Muramatsu, Ken; Kukita, Yutaka; Tasaka, Kanji

1988-04-01

THYDE-B1/MOD2 is a fast-running best estimate (BE) computer code to analyze thermal-hydraulic behaviors of the reactor cooling system of a boiling water reactor (BWR), mainly, during a small-break loss-of-coolant accident (SBLOCA) with a special emphasis on the behavior of pressure and mixture level in the pressure vessel. The coolant behavior is simulated with a volume-and-junction method based on assumptions of thermal equilibrium and homogeneous conditions for two-phase flow. A characteristic feature of this code is a three-region representation of the state of the coolant in a control volume, in which three regions consist of subcooled liquid, saturated mixture and saturated steam regions from the volume bottom. The regions are separated by two horizontal moving boundaries which are tracked by mass and energy balances for each region. With this three region node model, the interior of the pressure vessel can be represented by only two volumes: one for inside of the shroud and the other for outside, while other portions of the system are treated with homogeneous node model. This method, although it seems to be very simple, has been verified to be adequate for cases of BWR SBLOCAs in which the thermal-hydraulic behavior is relatively slow and gravity controlled. The code has been improved and modified from the last version of the code, THYDE-B1/MOD1, especially in the phase separation model which is used in the mixture level calculation in the three region node model. Then, a good predictability of the code has been indicated through the comparison of calculated results with various SBLOCA test data including ROSA-III of JAERI and FIST of the General Electric Co. This report presents the code modifications and input data requirements of the THYDE-B1/MOD2 code. (author)

Colourful sparkles of imaginary vistas: Saintly beauty in the eyes of the beholder

Directory of Open Access Journals (Sweden)

Dimitrova Elizabeta

2013-01-01

Full Text Available The article deals with the issue of physical appearance of the saintly images in Byzantine painting and the manners of its conception. In that regard, the paper offers categorization of the portraiture in which different saints receive distinctive aesthetic code appropriate to their type of “attractiveness”.

Preliminary Hazard Classification for the 105-B Reactor

International Nuclear Information System (INIS)

Kerr, N.R.

1997-08-01

This document summarizes the inventories of radioactive and hazardous materials present within the 105-B Reactor and uses the inventory information to determine the preliminary hazard classification for the surveillance and maintenance activities of the facility. The result of this effort was the preliminary hazard classification for the 105-B Building surveillance and maintenance activities. The preliminary hazard classification was determined to be Nuclear Category 3. Additional hazard and accident analysis will be documented in a separate report to define the hazard controls and final hazard classification

Rare copy of "Life of Saint Volo-dymyr" (Kyiv, 1670 from the manuscript Corpus of Lives of the Saints as a source for the 17th century Kyiv hagiography study

Directory of Open Access Journals (Sweden)

Bondar N. P.

2017-01-01

Full Text Available In the article a rare copy of an old-printed edition of “Life of Saint Volodymyr”, published circa 1670 in the Kyiv-Pechersk Lavra printing-house is characterized. The copy was included to Corpus of Lives of the Saints of the17th-18th centuries from the collection of Church and Archeological museum of Kyiv Ecclesiastical Academy (Fond 301, Unit 416L. According to the modern advances of codicology, archeology, filigranology it became possible to critically review the data of descriptions, which brought new results. The approximate dating of the old-printed edition, which has no title and imprint, is confirmed. The publishing history of “Life of Saint Volodymyr” is analyzed. The research of the copy is accompanied by the complex description of overall manuscript hagiography codex, the analysis of its content, specifics, ownership notes and paper filigrees. Archeographic analysis of Corpus of Lives of the Saints was combined with study of formation of Ukrainian hagiography complex of the second half of the 17th - the early 18th centuries.

Plutonium disposition study phase 1b final report

International Nuclear Information System (INIS)

1993-01-01

This report provides the results of the Westinghouse activities performed as part of the Plutonium Disposition Study Phase 1b. These activities, which took place from May 16, 1993 to September 15, 1993, build upon the work completed in Phase 1a, which concluded on May 15, 1993. In Phase 1a, three Plutonium Disposal Reactor (PDR) options were developed for the disposal of excess weapons grade plutonium from returned and dismantled nuclear weapons. This report documents the results of several tasks that were performed to further knowledge in specific areas leading up to Phase 2 of the PDR Study. The Westinghouse activities for Phase 1b are summarized as follows: (1) resolved technical issues concerning reactor physics including equilibrium cycle calculations, use of gadolinium, moderator temperature coefficient, and others as documented in Section 2.0; (2) analyzed large Westinghouse commercial plants for plutonium disposal; (3) reactor safety issues including the steam line break were resolved, and are included in Section 2.0; (4) several tasks related to the PDR Fuel Cycle were examined; (5) cost and deployment options were examined to determine optimal configuration for both plutonium disposal and tritium production; (6) response to questions from DOE and National Academy of Scientists (NAS) reviewers concerning the PDR Phase 1a report are included in Appendix A

Evaluation of OPPS model for plant operator's task simulation with Micro-SAINT

International Nuclear Information System (INIS)

Yoshida, Kazuo

1991-03-01

The development of a computer simulation method for cognitive behavior of operators under emergency conditions in nuclear power plant are being conducted at Japan Atomic Energy Research Institute (JAERI). As one of activities in this project, the task network modeling and simulation method has been evaluated with reproduced OPPS model using Micro-SAINT which is a PC software for task network analysis. OPPS is an operator's task simulation model developed by Oak Ridge National Laboratory. Operator's tasks under the condition of failure open of a safety relief valve in a BWR power plant has been analyzed as a sample problem with Micro-SAINT version of OPPS for the evaluation of task network analysis method. Furthermore, the fundamental capabilities of Micro-SAINT has been evaluated, and the task network in OPPS model has been also examined. As the results of this study, it has been clarified that random seed numbers in Micro-SAINT affect the probabilistic branching ratio and the distribution of task execution time calculated by Monte Carlo simulations, and the expression of network for a repeated task in the OPPS model leads to incorrect standard deviation in the case that a task execution time has some distribution. (author)

Calculation and Analysis of B/T (Burning and/or Transmutation Rate of Minor Actinides and Plutonium Performed by Fast B/T Reactor

Directory of Open Access Journals (Sweden)

Marsodi

2006-01-01

Full Text Available Calculation and analysis of B/T (Burning and/or Transmutation rate of MA (minor actinides and Pu (Plutonium has been performed in fast B/T reactor. The study was based on the assumption that the spectrum shift of neutron flux to higher side of neutron energy had a potential significance for designing the fast B/T reactor and a remarkable effect for increasing the B/T rate of MA and/or Pu. The spectrum shifts of neutron have been performed by change MOX to metallic fuel. Blending fraction of MA and or Pu in B/T fuel and the volume ratio of fuel to coolant in the reactor core were also considered. Here, the performance of fast B/T reactor was evaluated theoretically based on the calculation results of the neutronics and burn-up analysis. In this study, the B/T rate of MA and/or Pu increased by increasing the blending fraction of MA and or Pu and by changing the F/C ratio. According to the results, the total B/T rate, i.e. [B/T rate]MA + [B/T rate]Pu, could be kept nearly constant under the critical condition, if the sum of the MA and Pu inventory in the core is nearly constant. The effect of loading structure was examined for inner or outer loading of concentric geometry and for homogeneous loading. Homogeneous loading of B/T fuel was the good structure for obtaining the higher B/T rate, rather than inner or outer loading

Rahmaninov ja Saint-Saens Estonia kontserdisaalis / Tiina Õun

Index Scriptorium Estoniae

Õun, Tiina, 1954-

2005-01-01

18. novembril Estonia kontserdisaalis toimuvast Sergei Rahmaninovi Klaverikontsert nr 2 ja "Kellad" ettekandest ja 29. novembril Toimuvast Camille Saint-Saensi ooperi "Simson ja Delila" kontsertettekandest

Status of data testing of ENDF/B-V reactor dosimetry file

International Nuclear Information System (INIS)

Magurno, B.A.

1979-01-01

The ENDF/B-V Reactor Dosimetry File was released August 1979, and Phase II data testing started. The results presented here are from Brookhaven National Laboratory only, and are considered preliminary. The tests include calculated spectrum-averaged cross sections using 235 U fission spectrum (Watt), 252 Cf spontaneous fission spectrum (Watt and Maxwellian), and the Coupled Fast Reactor Measurement Facility (CFRMF) spectrum. 6 tables

Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

International Nuclear Information System (INIS)

Liu Guisheng

1995-01-01

How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testings of CENDL-2 and ENDF/B-6. (4 tabs., 2 figs.)

Measurement of thermal neutron flux spatial distribution in the IEA-R1 reactor core

International Nuclear Information System (INIS)

D'Utra Bitelli, U.

1993-01-01

This work presents the spatial thermal neutron flux in IEA-R1 reactor obtained by activation foils methods. These measurements were made in 27 fuel elements of the reactor core (165 B configuration). The results are important to compare with theoretical values, power calibration and safety analysis. (author)

Saint-Augustin, Proudhon, antithèses

OpenAIRE

Pasteur , Sébastien

2005-01-01

Proudhon cite peu Saint-Augustin, mais le parallèle d'un contexte historique à son tournant offre matière à réfléchir. D'autant que Proudhon, anticlérical concède au Père de l'Eglise, un rang de philosophe, occasion d'aborder la fondation du discours philosophique au travers de la confession.

Les couleurs de Moscou et de Saint-Pétersbourg The colours of Moscow and Saint Petersburg

Directory of Open Access Journals (Sweden)

Andréi Éfimov

2008-05-01

Full Text Available Moscou et Saint-Pétersbourg ont connu une évolution chromatique similaire mais les différences en matière de plan, d’urbanisme et d’influences culturelles, et leurs rôles alternés de capitale ont déterminé leurs particularités chromatiques propres. Le Moscou en bois du xiiie siècle s’est enrichi d’un ensemble de cathédrales blanches aux coupoles dorées entourées par la muraille en brique rouge du Kremlin. Le style baroque a introduit dans l’architecture de Moscou et de Saint-Pétersbourg les couleurs bleu foncé, orange et verte. À l’époque du classicisme, on utilisait la palette officielle de teintes pastel à dominante ocre. L’achromatisme devient ensuite un trait distinctif de l’éclectisme en Russie. Au début du XXe siècle, l’Art nouveau ranime les villes grâce aux couleurs verte, orange et violette. Dans les années 1920 et 1930, les constructivistes utilisent les tons gris mais tentent d’élaborer un code chromatique homogène. L’architecture soviétique, quant à elle, reprend l’esthétique du classicisme « ocre ». La construction de masse des années 1960 aux années 1980 méconnaît la couleur, mais à la charnière des XXe et XXIe siècles apparaissent des approches professionnelles qui visent à créer un milieu chromatique similaire pour les deux villes.Moscow and Saint Petersburg experienced similar evolutions in colour, but the differences in their plans, urbanity and cultural influences, and their alternating roles as capitals, determined the particularities of their palettes. The wooden Moscow of the thirteenth century was enriched by a group of white cathedrals with golden domes, surrounded by the red brick wall of the Kremlin. Baroque, as an architectural style, introduced Moscow and Saint Petersburg to the colours dark blue, orange, and green. The official palette of classicism was pastel, predominantly ochre, while the period of eclecticism in Russia was achromatic. At the

Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

International Nuclear Information System (INIS)

Liu Guisheng

1995-11-01

How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testing of CENDL-2 and ENDF/B-6. (author). 8 refs, 2 figs, 4 tabs

Reactor noise analysis of experimental fast reactor 'JOYO'

International Nuclear Information System (INIS)

Ohtani, Hideji; Yamamoto, Hisashi

1980-01-01

As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

New species and new records of deepwater munidid squat lobsters from north-western Australia: Onconida, Bathymunida, Crosnierita, Plesionida and Torbenella.

Science.gov (United States)

Ahyong, Shane T; Taylor, Joanne; Mccallum, Anna W

2013-11-04

Seven species of Munididae are reported from the continental margin of north-western Australia. Three species are new to science: Crosnierita adela sp. nov., Onconida ariel sp. nov. and Plesionida aurelia sp. nov., each presently known only from Western Australia. Four species are reported for the first time from Australian waters, Bathymunida balssi Van Dam, 1838, Bathymunida dissimilis Baba & de Saint Laurent, 1996, Crosnierita yante (Macpherson, 1994) and Torbenella orbis (Baba, 2005). Keys to the world species of the genera represented are provided.

Historical trajectories of fashion: from ancient luxury to its democratization

Directory of Open Access Journals (Sweden)

António Machuco Rosa

2014-08-01

concept of luxury as opposed to the social significance that luxury possessed in premodern societies. The evolution of luxury is seen within the context of the evolution of fashion, highlighting how it participates in the emergence of modern forms of display of individual desire. This evolution is analyzed through four historical examples: the dandy “Beau” Brummell, the haute couture initiated by Frederik Worth, the creations of Yves Saint Laurent and the collections that Karl Lagerfeld developed for H&M.

Bathymetry of Lake Erie and Lake Saint Clair

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Bathymetry of Lake Erie and Lake Saint Clair has been compiled as a component of a NOAA project to rescue Great Lakes lake floor geological and geophysical data and...

Safety and radiation protection within the French electronuclear fleet in 2014. The IRSN's opinion

International Nuclear Information System (INIS)

2015-11-01

This annual report concerns the 58 pressurized water reactors of the French electronuclear fleet which are currently being operated. After a presentation of this fleet, and a discussion of the global assessment of safety and radiation protection within this fleet (discussion of the noticed trends), this document first reports the analysis performed by the IRSN of some important events and anomalies which occurred in 2014: the presence of migrating elements in the primary circuit which resulted in the damage fuel assembly sheaths (in Saint-Laurent des Eaux), the spraying of electric equipment due to a water flow from leaky hoppers, and the risk of unavailability of important equipment due to a high temperature in the room of the emergency back-up turbo generator set. The next chapter comments significant evolutions: renewal of the command-control system for the 1300 MWe reactors, risks induced on the Gravelines nuclear plant site by the exploitation of the Dunkirk methane terminal, and internal EDF arbitrages related to declarations regarding events which occurred in Val de Loire nuclear plants. These evolutions illustrate how expertises performed by the IRSN on request by the ASN complement EDF expertises and are a contribution to the improvement of installation safety

Verification OFENDF/B-VII.0, ENDF/B-VII.1 and JENDL-4.0 nuclear data libraries for criticality calculations using NEA/NSC benchmarks

International Nuclear Information System (INIS)

Bouhaddane, A.; Farkas, G.; Hascik, J.; Slugen, V.

2015-01-01

The paper presents verification of selected nuclear data libraries with the aim to apply them to fast reactor calculations. More precise results were achieved for thermal neutrons calculations. This corresponds with the demand for more precise nuclear data for fast reactors. However, fast neutron calculations show some consistency, in particular between ENDF-B/VII.1 and JENDL-4.0 nuclear data libraries. The results support the idea to prefer using newer ENDF-B/VII.1 instead of the previous version ENDF-B/VII.0. Certainly, there are still some issues to be addressed and there is potential to gain more conclusive results. Although, application of ENDF-B/VII.1 and JENDL-4.0 is expected for further calculations. (authors)

Repression and black holes in Laurent Mauvignier novel about Algerian War

Directory of Open Access Journals (Sweden)

Giacomo Raccis

2015-12-01

Full Text Available XXth century history obliged narrators to clash with events that was literally inexpressible, measuring the potential and the lack of literary means. Laurent Mauvignier made this confrontarion the centre of his poetics: from minimal, private tragedies to great, historical dramas, passing through the media mystification of absurd fait divers, his novels face the Evil problem and its representation in words. With Des hommes (2009, Mauvignier addresses his question to one of the most problematic repression object in historical French memory: Algerian War. Building a polyphonic novel, he deals with an event deeply characterized by silence (the veteran silence studied by Benjamin Stora and Andrea Brazzoduro and that has been manipulated by the institutional and mediatic vulgata. Infact, the narration shows how the amnesty of collective faults is based on the "order to say nothing" (overturning Foucault, first of all caused by the social load of an history that nobody wants. This paper aims at showing how Mauvignier's work, inspired by modernist novel and "nouveau roman" (Duras, Simon, resorts to literary experimentalism to "défamiliariser" this historical event using the tools of a fiction claiming the value of a "secondary experience" to redeem a piece of history refused by the public discourse.

THE IMPACT OF SAINT PARASCHEVA PILGRIMAGE ON TOURISM IN IASI COUNTY

Directory of Open Access Journals (Sweden)

Alexandra Georgiana PARASCA

2015-07-01

Full Text Available Nowadays, pilgrimage is a part of international tourism, being considered religious tourism, because it contributes to the development of economy, like any other type of tourism. This research paper takes into consideration the pilgrimage to Saint Paracheva, and how it helps the development of religious tourism in Iasi county, the economical implications. We try to capture the importance of Saint Parascheva pilgrimage, because year after year it bring many more pilgrims to Iasi city. In time, it could become an important place of pilgrimage at European level.

European Geophysical Society (23rd) General Assembly, Annales Geophysicae, Part 1, Society Symposia, Solid Earth Geophysics & Geodesy, Supplement 1 to Volume 16 Held in Nice, France on 20-24 April 1998

Science.gov (United States)

1998-01-01

means of recognising partial melting were tested there. 1) Macroscopic texture: because melt is mobile it collects in structural sites, e.g. boudin ...Janicot (3), A. Viltard (1), P. de Felice (1), H. Laurent (2) (1) Laboratoire de Meteorologie Dynamique, CNRS Ecole Polytechnique, France (2...the main aircraft emissions injection area. AUTOMATIC TRACKING OF WEST AFRICAN CLOUD CLUSTERS V. Mathon and H. Laurent (ORSTOM, BP 5045, F-34Q32

ENEL overall PWR plant models and neutronic integrated computing systems

International Nuclear Information System (INIS)

Pedroni, G.; Pollachini, L.; Vimercati, G.; Cori, R.; Pretolani, F.; Spelta, S.

1987-01-01

To support the design activity of the Italian nuclear energy program for the construction of pressurized water reactors, the Italian Electricity Board (ENEL) needs to verify the design as a whole (that is, the nuclear steam supply system and balance of plant) both in steady-state operation and in transient. The ENEL has therefore developed two computer models to analyze both operational and incidental transients. The models, named STRIP and SFINCS, perform the analysis of the nuclear as well as the conventional part of the plant (the control system being properly taken into account). The STRIP model has been developed by means of the French (Electricite de France) modular code SICLE, while SFINCS is based on the Italian (ENEL) modular code LEGO. STRIP validation was performed with respect to Fessenheim French power plant experimental data. Two significant transients were chosen: load step and total load rejection. SFINCS validation was performed with respect to Saint-Laurent French power plant experimental data and also by comparing the SFINCS-STRIP responses

Methods and instrumentation for investigating Hall sensors during their irradiation in nuclear research reactors

International Nuclear Information System (INIS)

Bolshakova, I.; Holyaka, R.; Makido, E.; Marusenkov, A.; Shurygin, F.; Yerashok, V.; Moreau, P. J.; Vayakis, G.; Duran, I.; Stockel, J.; Chekanov, V.; Konopleva, R.; Nazarkin, I.; Kulikov, S.; Leroy, C.

2009-01-01

Present work discusses the issues of creating the instrumentation for testing the semiconductor magnetic field sensors during their irradiation with neutrons in nuclear reactors up to fluences similar to neutron fluences in steady-state sensor locations in ITER. The novelty of the work consists in Hall sensor parameters being investigated: first, directly during the irradiation (in real time), and, second, at high irradiation levels (fast neutron fluence > 10 18 n/cm 2 ). Developed instrumentation has been successfully tested and applied in the research experiments on radiation stability of magnetic sensors in IBR-2 (JINR, Dubna) and VVR-M (PNPI, Saint-Petersburg) reactors. The 'Remote-Rad' bench consists of 2 heads (head 1 and head 2) bearing investigated sensors put in a ceramic setting, of electronic unit, of personal computer and of signal lines. Each head contains 6 Hall sensors and a coil for generating test magnetic field. Moreover head 1 contains thermocouples for temperature measurement while the temperature of head 2 is measured by thermo-resistive method. The heads are placed in the reactor channel

Radiolytic reactions in the coolant of helium cooled reactors

International Nuclear Information System (INIS)

Tingey, G.L.; Morgan, W.C.

1975-01-01

The success of helium cooled reactors is dependent upon the ability to prevent significant reaction between the coolant and the other components in the reactor primary circuit. Since the thermal reaction of graphite with oxidizing gases is rapid at temperatures of interest, the thermal reactions are limited primarily by the concentration of impurity gases in the helium coolant. On the other hand, the rates of radiolytic reactions in helium are shown to be independent of reactive gas concentration until that concentration reaches a very low level. Calculated steady-state concentrations of reactive species in the reactor coolant and core burnoff rates are presented for current U. S. designed, helium cooled reactors. Since precise base data are not currently available for radiolytic rates of some reactions and thermal reaction rate data are often variable, the accuracy of the predicted gas composition is being compared with the actual gas compositions measured during startup tests of the Fort Saint Vrain high temperature gas-cooled reactor. The current status of these confirmatory tests is discussed. 12 references

Training courses at VR-1 reactor

International Nuclear Information System (INIS)

Sklenka, L.; Kropik, M.

2006-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilization - i.e. extensive educational program. The educational program is intended for the training of university students and selected nuclear power plant personnel. The training courses provide them experience in reactor and neutron physics, dosimetry, nuclear safety and operation of nuclear facilities. At present, the training course participants can go through more than 20 standard experimental exercises; particular exercises for special training can be prepared. Approximately 200 university students become familiar with the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. The VR-1 reactor takes also part in Eugene Wigner Course on Reactor Physics Experiments in the framework of European Nuclear Educational Network (ENEN) association. Recently, training courses for Bulgarian research reactor specialists supported by IAEA were carried out. An attractive program including demonstration of reactor operation is prepared also for high school students. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. (author)

Current status of the Thai Research Reactor (TRR-1/M1)

International Nuclear Information System (INIS)

Chueinta, Siripone; Julanan, Mongkol; Charncanchee, Decharchai

2006-01-01

The first Thai Research Reactor, TRR-1 went critical on 27 October 1962 at the maximum power of 1 MW. It was located at Office of Atoms for Peace (OAP) in Bangkok. Since then, TRR-1 was continuously operated and eventually shut down in 1975. Plate type, high-enriched uranium (HEU) and U 3 O 8 A1 cladding were used as the reactor fuel. Light water was used as moderator and coolant as well. In 1975, because of the problem from fuel supplier and also to supporting the Treaty of Non Proliferation of Nuclear Weapon or NPT, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. A new core was a hexagonal core shape designed by General Atomics (GA). Afterwards, TRR-1 was officially renamed to the Thai Research Reactor-1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose swimming pool type reactor with nominal power of 2 MW. The TRR-1/M1 uses uranium enriched at 20% in U-235 (LEU) and ZrH alloy as fuel. Light water is also used as coolant and moderator. At present, the reactor is operating with core No.14. The reactor has been serving for various kinds of utilization namely, radioisotope production, neutron activation analysis, beam experiments and reactor physics experiments. (author)

J-R Fracture Resistance of SA533 Gr.B-Cl.1 Steel for Reactor Pressure Vessel

Energy Technology Data Exchange (ETDEWEB)

Yoon, Ji-Hyun; Hong, Seokmin; Lee, Bong-Sang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

A rolled plate might show different mechanical behaviors from a forging, even though they contain same chemical compositions. Furthermore, it is known that the fracture behavior of a rolled plate is very sensitive to material orientation comparing to a forging. In this study, the J-R fracture resistances of SA533 Gr.B-Cl.1 plate were measured at reactor operating temperature and the material orientation sensitivity was discussed. The decrease of fracture resistance of this kind of low alloy steel at an elevated temperature is known as the effect of dynamic strain aging (DSA). It was attributed to that the carbides and grains elongated to primary rolling direction, so that the aspect ratio of carbides and grains in the specimen with T-L orientation is larger. Generally, the hard second phase could take a roll of trigger point of unstable fracture. It is needed that the fracture surfaces of the tested specimens to be examined profoundly.

The performance of ENDF/B-V.2 nuclear data for fast reactor calculations

International Nuclear Information System (INIS)

Atkinson, C.A.; Collins, P.J.

1987-01-01

Calculations with ENDF/B-V.2 data have been made for twenty-five fast-spectrum integral assemblies covering a wide range of sizes and compositions. Analysis was done by transport codes with refined cross section processing methods and detailed reactor modelling. The predictions of fission rate distributions and control rod worths were emphasized for the more prototypic benchmark cores. The results show considerable improvements in agreement with experiment compared with analysis using ENDF/B-IV data, but it is apparent that significant errors remain for fast reactor design calculations

Annual report on JEN-1 reactor; Informe periodico del Reactor JEN-1 correspondiente al ano 1971

Energy Technology Data Exchange (ETDEWEB)

Montes, J

1972-07-01

In the annual report on the JEN-1 reactor the main features of the reactor operations and maintenance are described. The reactor has been critical for 1831 hours, what means 65,8% of the total working time. Maintenance and pool water contamination have occupied the rest of the time. The maintenance schedule is shown in detail according to three subjects. The main failures and reactor scrams are also described. The daily maximum values of the water activity are given so as the activity of the air in the reactor hall. (Author)

Welding of the A1 reactor pressure vessel

International Nuclear Information System (INIS)

Becka, J.

1975-01-01

As concerns welding, the A-1 reactor pressure vessel represents a geometrically complex unit containing 1492 welded joints. The length of welded sections varies between 10 and 620 mm. At an operating temperature of 120 degC and a pressure of 650 N/cm 2 the welded joints in the reactor core are exposed to an integral dose of 3x10 18 n/cm 2 . The chemical composition is shown for pressure vessel steel as specified by CSN 413090.9 modified by Ni, Ti and Al additions, and for the welding electrodes used. The requirements are also shown for the mechanical properties of the base and the weld metals. The technique and conditions of welding are described. No defects were found in ultrasonic testing of welded joints. (J.B.)

On the Hierarchy of Saints on Altars. Visitation Records of Otto Friedrich Buchheim, the Bishop of Ljubljana (1641–1664

Directory of Open Access Journals (Sweden)

Lavrič, Ana

2011-09-01

Full Text Available The visitation records of Otto Friedrich Buchheim, the Bishop of Ljubljana from 1641–1664, offer an insight into the rules governing the disposition of saintly figures in altar retables. The central place was accorded to the titular saint, while companion saints are positioned in pairs (separately for each level of the retable in such a way that those of higher rank are placed on the more distinguished gospel side, whereas those of lower rank stand on the subordinate epistle side. The priority of one saint over another was not a matter of a random choice, but of a fixed hierarchical order which was created over the course of centuries in the Litany of All Saints and also in the hymns of the officium for All Saints Day; this hierarchy, as Buchheim remarks, is "in agreement with the general feeling of the Catholic Church". Ecclesiastical art in Slovenia shows that in the Gothic period the hierarchical principle governing the disposition of saintly figures was not yet firmly fixed, but it was fully established in the late Renaissance and Baroque periods, which coincides with the period of unification of the Litany of All Saints for the entire Catholic Church. Later it started to loosen again, yet it remained in force up to the 20th century.

Response of infaunal macrobenthos to the sediment granulometry in a tropical continental margine southwest coast of India

Digital Repository Service at National Institute of Oceanography (India)

Jayaraj, K.A.; Sheeba, P.; Jacob, J.; Revichandran, C.; Arun, P.K.; Praseeda, K.S.; Nisha, P.A.; Rasheed, K.A.

. Marine Ecology Progress Series 232, 15e27. El-Wakeel, S.K., Riley, J.P., 1957. Determination of organic carbon in the ma- rine muds. Journal of Du Counseil International Exploration 22, 180e183. Fauchald, K., Jones, G.F., 1979a. A survey of five... Press, Chicago, 111 pp. Massad, R., Brunel, P., 1979. Associations par stations, densites et diversite des polychates du benthos circalittoral et bathyal de estuaire maritime du Saint Laurent. Naturaliste Canadien 106, 229e253 (in French). McLaren, P...

Project management plan for the 105-C Reactor interim safe storage project. Revision 1

International Nuclear Information System (INIS)

Miller, R.L.

1997-01-01

In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

State of development of high temperature gas-cooled reactors in foreign countries

International Nuclear Information System (INIS)

Sudo, Yukio

1990-01-01

Emphasis has been placed in the development of high temperature gas-cooled reactors on high thermal efficiency as power reactors and the reactor from which nuclear heat can be utilized. In U.K., as the international project 'Dragon Project', the experimental Dragon reactor for research use with 20 MWt output and exit coolant temperature 750 deg C was constructed, and operated till 1976. Coated fuel particles were developed. In West Germany, the experimental power reactor AVR with 46 MWt and 15 MWe output was operated till 1988. The prototype power reactor THTR-300 with 300 MWe output and 750 deg C exit temperature is in commercial operation. In USA, the experimental power reactor Peach Bottom reactor with 40 MWe output and 728 deg C exit temperature was operated till 1974. The prototype Fort Saint Vrain power reactor with 330 MWe output and 782 deg C exit temperature was operated till 1989. In USSR, the modular VGM with 200 MWh output is at the planning stage. Also in China, high temperature gas-cooled reactors are at the design stage. Switzerland has taken part in various international projects. (K.I.)

Saint Petersburg magnetic observatory: from Voeikovo subdivision to INTERMAGNET certification

Science.gov (United States)

Sidorov, Roman; Soloviev, Anatoly; Krasnoperov, Roman; Kudin, Dmitry; Grudnev, Andrei; Kopytenko, Yury; Kotikov, Andrei; Sergushin, Pavel

2017-11-01

Since June 2012 the Saint Petersburg magnetic observatory is being developed and maintained by two institutions of the Russian Academy of Sciences (RAS) - the Geophysical Center of RAS (GC RAS) and the Saint Petersburg branch of the Pushkov Institute of Terrestrial Magnetism, Ionosphere and Radio Wave Propagation of RAS (IZMIRAN SPb). On 29 April 2016 the application of the Saint Petersburg observatory (IAGA code SPG) for introduction into the INTERMAGNET network was accepted after approval by the experts of the first definitive dataset over 2015, produced by the GC RAS, and on 9 June 2016 the SPG observatory was officially certified. One of the oldest series of magnetic observations, originating in 1834, was resumed in the 21st century, meeting the highest quality standards and all modern technical requirements. In this paper a brief historical and scientific background of the SPG observatory foundation and development is given, the stages of its renovation and upgrade in the 21st century are described, and information on its current state is provided. The first results of the observatory functioning are discussed and geomagnetic variations registered at the SPG observatory are assessed and compared with geomagnetic data from the INTERMAGNET observatories located in the same region.

Saint Petersburg magnetic observatory: from Voeikovo subdivision to INTERMAGNET certification

Directory of Open Access Journals (Sweden)

R. Sidorov

2017-11-01

Full Text Available Since June 2012 the Saint Petersburg magnetic observatory is being developed and maintained by two institutions of the Russian Academy of Sciences (RAS – the Geophysical Center of RAS (GC RAS and the Saint Petersburg branch of the Pushkov Institute of Terrestrial Magnetism, Ionosphere and Radio Wave Propagation of RAS (IZMIRAN SPb. On 29 April 2016 the application of the Saint Petersburg observatory (IAGA code SPG for introduction into the INTERMAGNET network was accepted after approval by the experts of the first definitive dataset over 2015, produced by the GC RAS, and on 9 June 2016 the SPG observatory was officially certified. One of the oldest series of magnetic observations, originating in 1834, was resumed in the 21st century, meeting the highest quality standards and all modern technical requirements. In this paper a brief historical and scientific background of the SPG observatory foundation and development is given, the stages of its renovation and upgrade in the 21st century are described, and information on its current state is provided. The first results of the observatory functioning are discussed and geomagnetic variations registered at the SPG observatory are assessed and compared with geomagnetic data from the INTERMAGNET observatories located in the same region.

Reactor benchmarks and integral data testing and feedback into ENDF/B-VI

International Nuclear Information System (INIS)

McKnight, R.D.; Williams, M.L.

1992-01-01

The role of integral data testing and its feedback into the ENDF/B evaluated nuclear data files are reviewed. The use of the CSEWG reactor benchmarks in the data testing process is discussed and selected results based on ENDF/B Version VI data are presented. Finally, recommendations are given to improve the implementation in future integral data testing of ENDF/B

Developing Semi-Analytical solutions for Saint-Venant Equations in the Uniform Flow Region

Directory of Open Access Journals (Sweden)

M.M. Heidari

2016-09-01

error increases with increasing ΔQ/Q. To assess the importance of Froud Number and KF2, also several simulations were carried out, the results showed that the maximum error in the development equation for various Froud Number and KF2>1, is less than 3.8 percent. Conclusion: Using Laplace transform to the saint venant equations and with respect to upstream and downstream boundary a formula for routing discharge presented. Investigation of the applicability range of presenting formula and cognitive effective factors on accuracy is necessary. So, the finite volume method using the time splitting scheme was employed to develop a computer code for solving the one dimensional unsteady flow equation. Then some tests of unsteady flow were simulated and verified the equations. The results showed that the maximum error increases with decreasing KF2 and increasing the rate of sudden changes of discharge. The maximum error in the presented formula for all tests with KF2>1, less than 3.8 percent.

Thinking with the saint: the miracle of Saint Januarius of Naples and science in early modern Europe.

Science.gov (United States)

de Ceglia, Francesco Paolo

2014-01-01

The aim of this paper is to reconstruct the way in which early modem science questioned and indirectly influenced (while being in its turn influenced by) the conceptualization of the liquefaction of the blood of Saint Januarius, a phenomenon that has been taking place at regular intervals in Naples since the late Middle Ages. In the seventeenth century, a debate arose that divided Europe between supporters of a theory of divine intervention and believers in the occult properties of the blood. These two theoretical options reflected two different perspectives on the relationship between the natural and the supernatural. While in the seventeenth century, the emphasis was placed on the predictable periodicity of the miraculous event of liquefaction as a manifestation of God in his role as a divine regulator, in the eighteenth century the event came to be described as capricious and unpredictable, in an attempt to differentiate miracles from the workings of nature, which were deemed to be normative. The miracle of the blood of Saint Januarius thus provides a window through which we can catch a glimpse of how the natural order was perceived in early modern Europe at a time when the Continent was culturally fragmented into north and south, Protestantism and Catholicism, learned and ignorant.

Recuperation of the energy released in the G-1, an air-cooled graphite reactor core

International Nuclear Information System (INIS)

Chambadal, P.; Pascal, M.

1955-01-01

The CEA (in his five-year setting plan) has objective among others, the realization of the two first french reactors moderated with graphite. The construction of the G-1 reactor in Marcoule, first french plutonic core, is achieved so that it will diverge in the beginning of 1956 and reach its full power in the beginning of the second semester of the same year. In this report we will detail the specificities of the reactor and in particular its cooling and energy recuperation system. The G-1 reactor being essentially intended to allow the french technicians to study the behavior of an energy installation supply taking its heat in a nuclear source as early as possible. (M.B.) [fr

Iconologie des infantes (Tumbo A et Tumbo B de la cathédrale de Saint-Jacques de Compostelle et Tumbo de Touxos Outos

Directory of Open Access Journals (Sweden)

Ghislaine Fournès

2008-07-01

Full Text Available Les miniatures des Tumbos A et B de la cathédrale de Saint-Jacques de Compostelle et du Tumbo de Touxos Outos établissent à travers la représentation des rois, reines et infantes, d’Alphonse II à Alphonse X, une généalogie royale. L’analyse des miniatures consacrées aux figures féminines confirme que, dans le royaume de León et en Castille, les infantes ont eu, aux XIe et XIIe siècles, un rôle majeur, spirituel et politique, notamment à travers l’institution de l’infantat.Las miniaturas de los Tumbos A y B de la catedral de Santiago de Compostela, y del Tumbo de Touxos Outos establecen a través de la representación de los reyes, reinas e infantas, desde Alfonso II hasta Alfonso X, una genealogía real. El análisis de las miniaturas dedicadas a las figuras femeninas confirma que, en el reino de León y en Castilla, las infantas detuvieron, durante los siglos XI y XII, un papel importante, a la vez espiritual y político, sobre todo gracias a la institución del infantado.

MARKETING STRATEGY FOR THE FINNISH TOURIST COMPANY BASED ON SAINT PETERSBURG MARKET RESEARCH

OpenAIRE

Miroshnichenko, Julia

2014-01-01

The goal of this thesis is to get a marketing strategy for proposed tourist business through the field-work marketing research. The purpose of this marketing research was to investigate the attitudes of Russian tourists in Saint Pe-tersburg towards Finland as a destination. The research examines the respondents’ own evaluation of the Finnish tourism possibilities, as well as the expert evaluation (made by the professionals of tourist agencies in Saint Petersburg) of the Finnish tourist ma...

A Latter-day Saint Approach to Addiction: Aetiology, Consequences and Treatment in a Theological Context

Directory of Open Access Journals (Sweden)

James D. Holt

2014-12-01

Full Text Available This article explores the theological underpinning of the nature, aetiology and treatment of addictions within The Church of Jesus Christ of Latter-day Saints. The first section outlines the “plan of salvation” and how this provides the theological framework for the source and solution to addictions. The final section explores addiction against this background in terms of its aetiology, types, consequences and treatment in a Latter-day Saint context. In so doing it builds on the recognition by the Church in recent years that addiction is a problem in the lives of some of its members and that treatment programs coherent with its teachings and beliefs are necessary. The article concludes by suggesting that while addiction may be more openly discussed within a Latter-day Saint context there is a need to keep this dialogue moving forward. This article does not examine Latter-day Saint teaching within the wider context of psychotherapy and other definitions of addiction; rather it explores the place of addiction as understood within the theological and ecclesiological context of Mormonism.

The Forging of a White Gay Aesthetic at the Saint, 1980–84

Directory of Open Access Journals (Sweden)

Tim Lawrence

2011-06-01

Full Text Available Based on original interviews with key protagonists and documentary research, the article examines the way in which the DJs who worked at the Saint forged a white gay aesthetic across the first half of the 1980s. A private party located in the East Village, New York, the Saint attracted a privileged white male crowd, and this group's position within the emerging culture of neoliberalism, along with the deepening impact of the AIDS epidemic, encouraged its spinners to sever their ties with sounds that were associated with blackness. However, if Saint DJs rejected a high proportion of records that were being released by New York's independents, and also snubbed Chicago house when it broke in 1985, their forging of an aesthetic that emphasised seamless transitions, often between records that contained similar sonic qualities, preempted the style of mixing that would be popularised in house music culture.

Annual report on JEN-1 reactor

International Nuclear Information System (INIS)

Montes, J.

1972-01-01

In the annual report on the JEN-1 reactor the main features of the reactor operations and maintenance are described. The reactor has been critical for 1831 hours, what means 65,8% of the total working time. Maintenance and pool water contamination have occupied the rest of the time. The maintenance schedule is shown in detail according to three subjects. The main failures and reactor scrams are also described. The daily maximum values of the water activity are given so as the activity of the air in the reactor hall. (Author)

105-B Reactor museum feasibility assessment (Phase 2) project

International Nuclear Information System (INIS)

Heckel, R. P.

2000-01-01

This 105-B Reactor Museum feasibility assessment project report documents project activities that have been performed, including a review and assessment of previously existing information, a walk-through of the facility, an assessment of potential hazards, and selection of mitigative measures deemed to be appropriate to allow unescorted access by members of the public to a specified primary tour route

Contextualising and Visualising Saints in the 14-15th century

Czech Academy of Sciences Publication Activity Database

Horníčková, Kateřina

-, č. 62 (2011), s. 21-39 ISSN 1029-0737 Institutional research plan: CEZ:AV0Z90090514 Keywords : medieval art * saints' representation * representation of place Subject RIV: AA - Philosophy ; Religion

New observations on the miniature of the vision of Saint Gregory of Nazianzus in Paris. GR. 510

Directory of Open Access Journals (Sweden)

Gavrilović Zaga

2007-01-01

Full Text Available The article deals with the iconography of the illustration of the Second Paschal Homily of St. Gregory of Nazianzus on fol. 285r of the Paris manuscript. It questions the identity of the woman saint represented on the right of St. Paraskeve in the lower register of the scene. Unlike that above St. Paraskeve, the inscription identifying this second woman saint is fragmentary and difficult to read, but it has been widely accepted that she is Saint Helena, mother of the Emperor Constantine the Great. On the basis of two other representations of Helena in the same manuscript and of the style of the inscription accompanying them, as well as taking into account the importance of the theological meaning expounded by St. Gregory in his oration, it is suggested that the second woman saint may be St. Kyriake.

Safety operation of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

2001-01-01

There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MW t , owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kW t , owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kW t , owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

Potentialities of high temperature reactors (HTR)

International Nuclear Information System (INIS)

Hittner, D.

2001-01-01

This articles reviews the assets of high temperature reactors concerning the amount of radioactive wastes produced. 2 factors favors HTR-type reactors: high thermal efficiency and high burn-ups. The high thermal efficiency is due to the high temperature of the coolant, in the case of the GT-MHR project (a cooperation between General Atomic, Minatom, Framatome, and Fuji Electric) designed to burn Russian military plutonium, the expected yield will be 47% with an outlet helium temperature of 850 Celsius degrees. The high temperature of the coolant favors a lot of uses of the heat generated by the reactor: urban heating, chemical processes, or desalination of sea water.The use of a HTR-type reactor in a co-generating way can value up to 90% of the energy produced. The high burn-up is due to the technology of HTR-type fuel that is based on encapsulation of fuel balls with heat-resisting materials. The nuclear fuel of Fort-Saint-Vrain unit (Usa) has reached values of burn-ups from 100.000 to 120.000 MWj/t. It is shown that the quantity of unloaded spent fuel can be divided by 4 for the same amount of electricity produced, in the case of the GT-MHR project in comparison with a light water reactor. (A.C.)

Geologic map of Saint Lawrence Island, Alaska

Science.gov (United States)

Patton, William W.; Wilson, Frederic H.; Taylor, Theresa A.

2011-01-01

Saint Lawrence Island is located in the northern Bering Sea, 190 km southwest of the tip of the Seward Peninsula, Alaska, and 75 km southeast of the Chukotsk Peninsula, Russia (see index map, map sheet). It lies on a broad, shallow-water continental shelf that extends from western Alaska to northeastern Russia. The island is situated on a northwest-trending structural uplift exposing rocks as old as Paleozoic above sea level. The submerged shelf between the Seward Peninsula and Saint Lawrence Island is covered mainly with Cenozoic deposits (Dundo and Egiazarov, 1982). Northeast of the island, the shelf is underlain by a large structural depression, the Norton Basin, which contains as much as 6.5 km of Cenozoic strata (Grim and McManus, 1970; Fisher and others, 1982). Sparse test-well data indicate that the Cenozoic strata are underlain by Paleozoic and Proterozoic rocks, similar to those exposed on the Seward Peninsula (Turner and others, 1983). Saint Lawrence Island is 160 km long in an east-west direction and from 15 km to 55 km wide in a north-south direction. The east end of the island consists largely of a wave-cut platform, which has been elevated as much as 30 m above sea level. Isolated upland areas composed largely of granitic plutons rise as much as 550 m above the wave-cut platform. The central part of the island is dominated by the Kookooligit Mountains, a large Quaternary shield volcano that extends over an area of 850 km2 and rises to an elevation of 630 m. The west end of the island is composed of the Poovoot Range, a group of barren, rubble-covered hills as high as 450 m that extend from Boxer Bay on the southwest coast to Taphook Mountain on the north coast. The Poovoot Range is flanked on the southeast by the Putgut Plateau, a nearly flat, lake-dotted plain that stands 30?60 m above sea level. The west end of the island is marked by uplands underlain by the Sevuokuk pluton (unit Kg), a long narrow granite body that extends from Gambell on the

The implantation of a PV electric energy generation system at the Saint Peter and Saint Paul islands

Energy Technology Data Exchange (ETDEWEB)

Galdino, Marco Antonio; Silva, Patricia de Castro da [Centro de Pesquisas de Energia Eletrica (CEPEL), Rio de Janeiro, RJ (Brazil)], E-mail: marcoag@cepel.br; Souza, Marco Antonio Carvalho [Secretaria da Comissao Interministerial para os Recursos do Mar (SECIRM), Brasilia, DF (Brazil)

2009-07-01

The Saint Peter and Saint Paul Islands are located at 0 degree 55.00' N and 29 degree 20.76'' W, at a distance of circa 550 M (nautical miles) NE from the City of Natal, RN (Northeast Region of Brazil), and comprises of many small islands and rocks of igneous plutonic origin. In 1998, a first Scientific Station was built in order to receive researchers involved in several projects. The CEPEL, as responsible by the electrical energy supply to the Scientific Station; designed and installed a PV electric energy generation system which had a power of 3.6 kWp. This system operated successfully for the last 10 years, suffering frequent maintenance. In 2006, a new design for the Scientific Station has been started aiming to improve its resources and safety. The new PV system has a maximum power of 7.8 kWp, and employs an updated technology (SMA, Germany). The equipment was integrated and submitted to intensive testing at facilities of CEPEL, and was installed and commissioned at the Islands in June 2008. Since the installation, the equipment has been operating as required, meeting the energy and water demand of the Station. The present paper describes the many steps involved in the implantation of the PV system at the Scientific Station. (author)

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, Karel; Sklenka, Lubomir

2003-01-01

Full text: The training reactor VR-1 Vrabec ('Sparrow'), operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly, it is designed and operated for training of students from Czech universities, preparing of experts for the Czech nuclear programme, as well as for certain research and development work, and for information programmes in the sphere of non-military nuclear energy use (public relation). The VR-1 training reactor is a pool-type light-water reactor based on enriched uranium with maximum thermal power 1kWth and short time period up to 5kW th . The moderator of neutrons is light demineralized water (H 2 O) that is also used as a reflector, a biological shielding, and a coolant. Heat is removed from the core with natural convection. The reactor core contains 14 to 18 fuel assemblies IRT-3M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The core is accommodated in a cylindrical stainless steel vessel - pool, which is filled with water. UR-70 control rods serve the reactor control and safe shutdown. Training of the VR-1 reactor provides students with experience in reactor and neutron physics, dosimetry, nuclear safety, and nuclear installation operation. Students from technical universities and from natural sciences universities come to the reactor for training. Approximately 200 university students are introduced to the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. Practical Course on Reactor Physics in Framework of European Nuclear Engineering Network has been newly introduced. Currently, students can try out more than 20 experimental exercises. Further training courses have been included

New burnup calculation of TRIGA IPR-R1 reactor

International Nuclear Information System (INIS)

Meireles, Sincler P. de; Campolina, Daniel de A.M.; Santos, Andre A. Campagnole dos; Menezes, Maria A.B.C.; Mesquita, Amir Z.

2015-01-01

The IPR-R1 TRIGA Mark I research reactor, located at the Nuclear Technology Development Center - CDTN, Belo Horizonte, Brazil, operates since 1960.The reactor is operating for more than fifty years and has a long history of operation. Determining the current composition of the fuel is very important to calculate various parameters. The reactor burnup calculation has been performed before, however, new techniques, methods, software and increase of the processing capacity of the new computers motivates new investigations to be performed. This work presents the evolution of effective multiplication constant and the results of burnup. This new model has a more detailed geometry with the introduction of the new devices, like the control rods and the samarium discs. This increase of materials in the simulation in burnup calculation was very important for results. For these series of simulations a more recently cross section library, ENDF/B-VII, was used. To perform the calculations two Monte Carlo particle transport code were used: Serpent and MCNPX. The results obtained from two codes are presented and compared with previous studies in the literature. (author)

German Phase B [risk study] highlights the role of [reactor] accident management

International Nuclear Information System (INIS)

Anon.

1989-01-01

Phase B of the German probabilistic risk assessment study, now scheduled for publication this month, suggests that reactor accident management measures can prevent or mitigate about 90 per cent of event sequences. (author)

Prayer to the Saints or the Virgin and Health among Older Mexican Americans

Science.gov (United States)

Krause, Neal; Bastida, Elena

2011-01-01

The purpose of this study was to evaluate a conceptual model that assesses whether praying to the saints or the Virgin is associated with the health of older Mexican Americans. A survey was conducted of 1,005 older Mexican Americans (Mean age = 73.9 years; SD = 6.6 years). Data from 795 of the Catholic respondents are presented in this study. The…

Development of flood-inundation maps for the Mississippi River in Saint Paul, Minnesota

Science.gov (United States)

Czuba, Christiana R.; Fallon, James D.; Lewis, Corby R.; Cooper, Diane F.

2014-01-01

Digital flood-inundation maps for a 6.3-mile reach of the Mississippi River in Saint Paul, Minnesota, were developed through a multi-agency effort by the U.S. Geological Survey in cooperation with the U.S. Army Corps of Engineers and in collaboration with the National Weather Service. The inundation maps, which can be accessed through the U.S. Geological Survey Flood Inundation Mapping Science Web site at http://water.usgs.gov/osw/flood_inundation/ and the National Weather Service Advanced Hydrologic Prediction Service site at http://water.weather.gov/ahps/inundation.php, depict estimates of the areal extent and depth of flooding corresponding to selected water levels (stages) at the U.S. Geological Survey streamgage at the Mississippi River at Saint Paul (05331000). The National Weather Service forecasted peak-stage information at the streamgage may be used in conjunction with the maps developed in this study to show predicted areas of flood inundation. In this study, flood profiles were computed for the Mississippi River by means of a one-dimensional step-backwater model. The hydraulic model was calibrated using the most recent stage-discharge relation at the Robert Street location (rating curve number 38.0) of the Mississippi River at Saint Paul (streamgage 05331000), as well as an approximate water-surface elevation-discharge relation at the Mississippi River at South Saint Paul (U.S. Army Corps of Engineers streamgage SSPM5). The model also was verified against observed high-water marks from the recent 2011 flood event and the water-surface profile from existing flood insurance studies. The hydraulic model was then used to determine 25 water-surface profiles for flood stages at 1-foot intervals ranging from approximately bankfull stage to greater than the highest recorded stage at streamgage 05331000. The simulated water-surface profiles were then combined with a geographic information system digital elevation model, derived from high-resolution topography

Optimization of a heterogeneous catalytic hydrodynamic cavitation reactor performance in decolorization of Rhodamine B: application of scrap iron sheets.

Science.gov (United States)

Basiri Parsa, Jalal; Ebrahimzadeh Zonouzian, Seyyed Alireza

2013-11-01

A low pressure pilot scale hydrodynamic cavitation (HC) reactor with 30 L volume, using fixed scrap iron sheets, as the heterogeneous catalyst, with no external source of H2O2 was devised to investigate the effects of operating parameters of the HC reactor performance. In situ generation of Fenton reagents suggested an induced advanced Fenton process (IAFP) to explain the enhancing effect of the used catalyst in the HC process. The reactor optimization was done based upon the extent of decolorization (ED) of aqueous solution of Rhodamine B (RhB). To have a perfect study on the pertinent parameters of the heterogeneous catalyzed HC reactor, the following cases as, the effects of scrap iron sheets, inlet pressure (2.4-5.8 bar), the distance between orifice plates and catalyst sheets (submerged and inline located orifice plates), back-pressure (2-6 bar), orifice plates type (4 various orifice plates), pH (2-10) and initial RhB concentration (2-14 mg L(-1)) have been investigated. The results showed that the highest cavitational yield can be obtained at pH 3 and initial dye concentration of 10 mg L(-1). Also, an increase in the inlet pressure would lead to an increase in the ED. In addition, it was found that using the deeper holes (thicker orifice plates) would lead to lower ED, and holes with larger diameter would lead to the higher ED in the same cross-sectional area, but in the same holes' diameters, higher cross-sectional area leads to the lower ED. The submerged operation mode showed a greater cavitational effects rather than the inline mode. Also, for the inline mode, the optimum value of 3 bar was obtained for the back-pressure condition in the system. Moreover, according to the analysis of changes in the UV-Vis spectra of RhB, both degradation of RhB chromophore structure and N-deethylation were occurred during the catalyzed HC process. Copyright © 2013 Elsevier B.V. All rights reserved.

Inspecting Sizewell B Class 1 and IoF components

International Nuclear Information System (INIS)

McNulty, T.

1990-01-01

Class 1 and ''incredibility of failure'' (IoF) pre-service inspections for Sizewell B cover steam generator and pressurizer welds and nozzles, welds on the emergency boration system, accumulators and reactor coolant loop, and the whole of the Class 1 piping. The contractor for this work has recently been selected. The scope of the work and the techniques and equipment to be used are outlined. (author)

Moving ring reactor 'Karin-1'

International Nuclear Information System (INIS)

1983-12-01

The conceptual design of a moving ring reactor ''Karin-1'' has been carried out to advance fusion system design, to clarify the research and development problems, and to decide their priority. In order to attain these objectives, a D-T reactor with tritium breeding blanket is designed, a commercial reactor with net power output of 500 MWe is designed, the compatibility of plasma physics with fusion engineering is demonstrated, and some other guideline is indicated. A moving ring reactor is composed mainly of three parts. In the first formation section, a plasma ring is formed and heated up to ignition temperature. The plasma ring of compact torus is transported from the formation section through the next burning section to generate fusion power. Then the plasma ring moves into the last recovery section, and the energy and particles of the plasma ring are recovered. The outline of a moving ring reactor ''Karin-1'' is described. As a candidate material for the first wall, SiC was adopted to reduce the MHD effect and to minimize the interaction with neutrons and charged particles. The thin metal lining was applied to the SiC surface to solve the problem of the compatibility with lithium blanket. Plasma physics, the engineering aspect and the items of research and development are described. (Kako, I.)

SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations

International Nuclear Information System (INIS)

Gauld, I.C.

2000-01-01

Five commercial reactor criticals (CRCs) for the LaSalle Unit 1 boiling-water reactor have been analyzed using KENO V.a, the Monte Carlo criticality code of the SCALE 4 code system. The irradiated fuel assembly isotopics for the criticality analyses were provided by the Waste Package Design team at the Yucca Mountain Project in the US, who performed the depletion calculations using the SAS2H sequence of SCALE 4. The reactor critical measurements involved two beginning-of-cycle and three middle-of-cycle configurations. The CRCs involved relatively low-cycle burnups, and therefore contained a relatively high gadolinium poison content in the reactor assemblies. This report summarizes the data and methods used in analyzing the critical configurations and assesses the sensitivity of the results to some of the modeling approximations used to represent the gadolinium poison distribution within the assemblies. The KENO V.a calculations, performed using the SCALE 44GROUPNDF5 ENDF/B-V cross-section library, yield predicted k eff values within about 1% Δk/k relative to reactor measurements for the five CRCs using general 8-pin and 9-pin heterogeneous gadolinium poison pin assembly models

The Segmented Aperture Interferometric Nulling Testbed (SAINT) I: overview and air-side system description

Science.gov (United States)

Hicks, Brian A.; Lyon, Richard G.; Petrone, Peter; Ballard, Marlin; Bolcar, Matthew R.; Bolognese, Jeff; Clampin, Mark; Dogoda, Peter; Dworzanski, Daniel; Helmbrecht, Michael A.; Koca, Corina; Shiri, Ron

2016-07-01

This work presents an overview of the Segmented Aperture Interferometric Nulling Testbed (SAINT), a project that will pair an actively-controlled macro-scale segmented mirror with the Visible Nulling Coronagraph (VNC). SAINT will incorporate the VNC's demonstrated wavefront sensing and control system to refine and quantify end-to-end high-contrast starlight suppression performance. This pathfinder testbed will be used as a tool to study and refine approaches to mitigating instabilities and complex diffraction expected from future large segmented aperture telescopes.

iB1350 no.1. A generation III.7 reactor after the Fukushima Daiichi accident

International Nuclear Information System (INIS)

Sato, Takashi; Matsumoto, Keiji; Hosomi, Kenji; Kojima, Yoshihiro; Taguchi, Keisuke

2017-01-01

iB1350 stands for an innovative, intelligent and inexpensive BWR 1350. It is the first generation III.7 reactor after the Fukushima Daiichi accident. It has incorporated lessons learned from the Fukushima Daiichi accident and WENRA safety objectives. It has innovative safety to cope with devastating natural disasters including a giant earthquake, a large tsunami and a monster hurricane. The iB1350 can survive passively such devastation and a very prolonged SBO without any support from the outside of a site up to 7 days even preventing core melt. It, however, is based on the well-established proven ABWR design. The NSSS is exactly the same as that of the current ABWR. As for safety design, it has a double cylinder RCCV (Mark W containment) and in-depth hybrid safety systems (IDHS). The Mark W containment has double FP confinement barriers and the in-containment filtered venting system (IFVS) that enable passively no emergency evacuation outside the immediate vicinity of the plant for a SA. It has a large volume to hold hydrogen, an innovative core catcher (iCC), a passive flooding system and an innovative passive containment cooling system (iPCCS) establishing passively practical elimination of containment failure even in a long term. The IDHS consists of 4 division active safety systems for a DBA, 2 division active safety systems for a SA and built-in passive safety systems (BiPSS) consisting of an isolation condenser (IC) and the iPCCS for a SA. While the conventional PCCS can never cool the S/P, the iPCCS can automatically cool the S/P directly even in a DBA LOCA. That makes it possible for the iB1350 to optimize the active safety systems for a DBA. Sato came up with several optimized configurations of the IDHS that are expected to achieve further cost reduction and enhance its reliability resulting from passive feature of the iPCCS. The IC/iPCCS pool has enough capacity for 7 day grace period. The IC/iPCCS heat exchangers, the core and the spent fuel pool are

Public meeting of September 13, 2005 at Saint-Dizier; Reunion publique du 13 septembre 2005 a Saint-Dizier

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the debates of the second public hearing at Saint-Dizier. This meeting gathers representatives of the different actors of the nuclear industry, ministers, public authorities, non governmental organizations who argue the questions asked by peoples from the audience. The topics concern the safety aspects of waste facilities, in particular according to the studies carried out at the Bure site, the different categories of wastes and the future wastes that will be generated by the dismantling of nuclear facilities etc. (J.S.)

The determination of neutron energy spectrum in reactor core C1 of reactor VR-1 Sparrow

Energy Technology Data Exchange (ETDEWEB)

Vins, M. [Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University, V Holesovickach 2, 180 00 Prague 8 (Czech Republic)], E-mail: vinsmiro@seznam.cz

2008-07-15

This contribution overviews neutron spectrum measurement, which was done on training reactor VR-1 Sparrow with a new nuclear fuel. Former nuclear fuel IRT-3M was changed for current nuclear fuel IRT-4M with lower enrichment of 235U (enrichment was reduced from former 36% to 20%) in terms of Reduced Enrichment for Research and Test Reactors (RERTR) Program. Neutron spectrum measurement was obtained by irradiation of activation foils at the end of pipe of rabit system and consecutive deconvolution of obtained saturated activities. Deconvolution was performed by computer iterative code SAND-II with 620 groups' structure. All gamma measurements were performed on Canberra HPGe. Activation foils were chosen according physical and nuclear parameters from the set of certificated foils. The Resulting differential flux at the end of pipe of rabit system agreed well with typical spectrum of light water reactor. Measurement of neutron spectrum has brought better knowledge about new reactor core C1 and improved methodology of activation measurement. (author)

Life and death at precolumbian Lavoutte, Saint Lucia, Lesser Antilles

NARCIS (Netherlands)

Hofman, C.L.; Hoogland, M.L.P.; Mickleburgh, H.L.; Laffoon, J.E.; Weston, D.A.; Field, M.H.

2012-01-01

The Caribbean archaeological record requires immediate attention and protection. Development and natural forces have impacted archaeological sites, destroying or severely damaging them. The precolumbian site of Lavoutte, located in northern Saint Lucia, has been known as a major Late Ceramic Age

Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

Tombes et cimetières éthiopiens : des rois, des saints, des anonymes1

OpenAIRE

Derat, Marie-Laure

2009-01-01

L’histoire des tombes et cimetières éthiopiens, dans la longue durée, en est encore à ses balbutiements. Si les tombes des saints et des rois nous sont un peu mieux connus grâce à des textes témoignant à la fois des enjeux entourant les sépultures de ces personnages hors du commun et des soins apportés à leur inhumation, en revanche, les cimetières ordinaires échappent encore largement à l’enquête, en grande partie parce que le commun des mortels est inhumé dans l’anonymat et dans un grand dé...

What Are Robespierre and Telemachus Doing in Saint-Domingue?

DEFF Research Database (Denmark)

Kjærgård, Jonas Ross

2018-01-01

Charles Pigault-Lebrun's play Le blanc et le noir (1795) is one of only a handful of French revolutionary plays to stage the Saint-Domingue slave rebellion, a rebellion today better known as the Haitian Revolution (1791–1804). I argue that Pigault-Lebrun uses early melodramatic generic traits to ...

The Way of Saint James and the Xacobeo 2010 in the tourism websites of the Spanish autonomous communities

Directory of Open Access Journals (Sweden)

María-Dolores Fernández-Poyatos, Ph.D.

2012-01-01

Full Text Available This article analyses the tourism websites of Spanish autonomous communities crossed by the Way of Saint James. Considering that the Way of Saint James and the Xacobeo 2010 are important touristic opportunities for these autonomous regions, the main objective of this investigation is to evaluate the information about these touristic places in their tourism websites. The analysis focused on two aspects: firstly, establishing whether the autonomous communities have used the Way of Saint James and the Xacobeo 2010 to promote themselves, and secondly, evaluating the quality of the websites. The study included a literature review, definition of concepts and criteria to measure the quality of websites, and the analysis of the content and design of the selected tourism websites. The results show that the Galician website is the most complete in terms of information about the Way of Saint James and the Xacobeo 2010. The information about the Way of Saint James and the Xacobeo 2010 in the websites of the other communities is vague and differs from one website to another. Due to the touristic significance of the Xacobeo 2010 and the importance of Internet as a medium of communication, the research group plans to conduct a new analysis of the communities’ institutional websites in 2011.

Occupational analysis for the Angra-1 reactor

International Nuclear Information System (INIS)

Moraes, A.

1991-01-01

Due to several modifications which were imposed to its time schedule during construction, the Angra-1 reactor did not enter to the grid in 1982 as it was initially foreseen. These modifications occurred due to an unforeseen scenario that was verified in steam generators (serie D-3, Westinghouse) of power stations with similar configurations which had been installed in other countries such as Ringhals-3 (Sweden), Almaraz-1 (Spain) and McGuine-1 (USA). So, among the main events that occurred in the Angra-1 reactor, which were of interest from the point of view of radiation protection, it could be pointed out the personnel monitoring, and the occupational exposure measurements at different reactor power, during the reactor fueling and during modification and tests performed at the steam generators and at ducts of the primary coolant circuit. (author)

The Slavonic Translation of the Life of Saint Euthymius the Great: Observations on Language and Authorship

Directory of Open Access Journals (Sweden)

Dmitriy Evgenyevich Afinogenov

2015-10-01

Full Text Available The Slavonic translation of the Life of Saint Euthymius the Great (BHG 647 by Cyril of Scythopolis, attested at the earliest manuscript of the late 14th c., was probably made by a person originating from South-East Rus in the 11th c., as it displays some grammatical, lexical, and phonetic features peculiar for this area and time, and visible, in particular, in Ipatiev Chronicle and the Tale of Igor’s Campaign. It may have formed a part of the collection comprising several writings by Cyril, including the Life of Saint Sabas and the Praise of Euthymius and Sabas (lost in the Greek original. This collection was later incorporated into the Great Lectionary Menologion of Metropolitan Makarij. The details added by the translator to the description of certain realia pertaining to the Monastery of Saint Euthymius in Palestine suggest a personal knowledge of that monastic complex (the Laura and the coenobium. The proposed author of the translation is Saint Anthony of the Cave Monastery in Kiev († 1073, who could perfectly well have visited the Holy Land during his stay on Mount Athos prior to 1051.

Sainte-Bernardette du Banlay, Nevers

Directory of Open Access Journals (Sweden)

Christophe Joly

2009-11-01

Full Text Available Construite par Claude Parent et Paul Virilio en 1964-1965, l’église Sainte-Bernadette du Banlay témoigne de leurs travaux sur la fonction oblique. L’édifice fut édifié à l’issue d’un concours d’architecture lancé en 1963 par Mgr Vial et l’Abbé Bourgoin, curé de la paroisse. L’église est inspirée de l’architecture des bunkers. Deux coques de béton s’imbriquent l’une dans l’autre en se décalant par rapport à l’axe longitudinal. L’apparence générale est un édifice monolithique, qui évoque un rocher. Á l’intérieur, deux grands plans obliques paraissent exhumés pour constituer la nef et le chœur. En relation étroite avec la grotte des apparitions de Lourdes, l’église est construite comme une crypte suspendue dont la coupe adopte la forme d’un cœur. Par le choix de matériaux bruts et d’un éclairage zénithal, les architectes confèrent à l’ensemble une étonnante intimité. C’est par l’opposition entre le volume extérieur austère et fermé et l’espace intérieur accueillant et protecteur que les concepteurs expriment la nouvelle fonction d’une église conçue dans une période d’incertitude et de tensions.The Sainte-Bernadette du Banlay church at Nevers was built from 1964 to 1965 to the designs of the architects Claude Parent and Paul Virilio, working on their theme of the oblique function. It was the fruit of an architectural competition organised in 1963 by Monseigneur Vial and the Abbé Bourgoin, the parish priest. The church’s architecture is inspired by that of defensive bunkers. Two reinforced concrete shells are joined the one into the other but out of true on a longitudinal axis. The overall appearance of the church is that of a monolithic block, something like a rock. Inside, two large oblique planes seem to emerge to create the nave and the chancel. Closely related to the Lourdes grotto of the Virgin’s appearances, the church is designed as a suspended crypt

ETOA, ABBN Multigroup Constants from ENDF/B for Fast Reactors

International Nuclear Information System (INIS)

Nishimura, Hideo

1977-01-01

1 - Nature of physical problem solved: Production of ABBN type group constants up to 70 groups for fast reactor calculations, reading ENDF/B library as input. 2 - Method of solution: The multigroup method of Bondarenko et al. is used for processing basic nuclear data. Calculational algorithms for an unresolved resonance region are the same as those in the MC 2 code. For a resolved resonance region, an ultrafine energy structure dependent on a level scheme is adopted. 3 - Restrictions on the complexity of the problem: Maximum number of: energy groups: 70; sigma 0 values: 6; temperatures: 5. Self-shielding factors for an unrealistically low value of sigma 0 are not guaranteed because of the approximations used in the unresolved resonance region

L’église Saint-Michel de Lille : chronologie d’un chantier

Directory of Open Access Journals (Sweden)

Catherine Guillot

2012-04-01

Full Text Available Après le démantèlement des fortifications de Lille en 1858, un nouveau quartier est aménagé au sud de la ville, dont un des équipements importants est l’église Saint-Michel, construite entre 1868 et 1874 par l’architecte Alfred Coisel. Très bien documenté, son chantier dévoile un mobilier et un décor exemplaire par son homogénéité et par la place accordée à la peinture murale. Cette étude met en évidence, outre le rôle du peintre Alphonse Colas, des artistes méconnus comme Albéric Duyver et Marie Carin. L’iconographie, qui révèle un des plus importants cycles consacrés à l’archange saint Michel, est également extrêmement caractéristique de son temps.After the demolition of the fortifications at Lille, in 1858, a new quarter developed to the south of the city. One of the important features of this new neighbourhood was the Saint-Michel church, built between 1868 and 1874 to the designs of the architect Alfred Coisel. The building of this church is exceptionally well documented and reveals church furnishings and decoration of an exemplary nature in terms of homogeneity and the special place given over to mural paintings. This study underlines the role of the painter Alphonse Colas, but also the contribution of other, less well known artists such as Albéric Duyver and Marie Carin. The iconographical theme is one of the most important cycles of its time devoted to the archangel Saint Michel, and is highly characteristic of the period.

The classification of wood chips parameters by crushing of waste cane from different varieties of grapevine

Directory of Open Access Journals (Sweden)

Patrik Burg

2008-01-01

Full Text Available This work deales with exploitatives parameters monitoring of wood shreder PEZZOLATO 110 Mb by crushing of waste cane of six varieties. The results shows that the wood shreders efficiency, fuel consumption and the wood chips elements size can be influenced by varieties characters of cane. The va­lued machines efficiency was 230–470 kg . h−1 by average volume 40.70 % water in wood. The hig­hest values by cane crushing had the variety Saint Laurent (0.47 t . h−1 and the lowest variety ­Blauer Portugieser (0.23 t . h−1. The specific consumption of petrol Natural 95 was 4.52.10−3–8.12.10−3 l . kg−1. The average middle elements lenght was 6.64 mm by crushed varieties.

Egg deposition by lithophilic-spawning fishes in the Detroit and Saint Clair Rivers, 2005–14

Science.gov (United States)

Prichard, Carson G.; Craig, Jaquelyn M.; Roseman, Edward F.; Fischer, Jason L.; Manny, Bruce A.; Kennedy, Gregory W.

2017-03-14

A long-term, multiseason, fish egg sampling program conducted annually on the Detroit (2005–14) and Saint Clair (2010–14) Rivers was summarized to identify where productive fish spawning habitat currently exists. Egg mats were placed on the river bottom during the spring and fall at historic spawning areas and candidate fish spawning habitat restoration sites throughout both rivers. Widespread evidence was found of lithophilic spawning by numerous native fish species, including walleye (Sander vitreus), lake whitefish (Coregonus clupeaformis), lake sturgeon (Acipenser fulvescens), suckers (Catostomidae spp.), and trout-perch (Percopsis omiscomaycus). Walleye, lake whitefish, and suckers spp. spawned in nearly every region of each river in all years on both reef and nonreef substrates. Lake sturgeon eggs were collected almost exclusively over constructed reefs. Catch-per-unit effort of walleye, lake whitefish, and sucker eggs was much greater in the Detroit River than in the Saint Clair River, while Saint Clair River sites supported the greatest collections of lake sturgeon eggs. Collections during this study of lake sturgeon eggs on man-made spawning reefs suggest that artificial reefs may be an effective tool for restoring fish populations in the Detroit and Saint Clair Rivers; however, the quick response of lake sturgeon to spawn on newly constructed reefs and the fact that walleye, lake whitefish, and sucker eggs were often collected over substrate with little interstitial space to protect eggs from siltation and predators suggests that lack of suitable spawning habitat may continue to limit reproduction of lithophilic-spawning fish species in the Saint Clair-Detroit River System.

Reactor operations at SAFARI-1

International Nuclear Information System (INIS)

Vlok, J.W.H.

2003-01-01

A vigorous commercial programme of isotope production and other radiation services has been followed by the SAFARI-1 research reactor over the past ten years - superimposed on the original purpose of the reactor to provide a basic tool for nuclear research, development and education to the country at an institutional level. A combination of the binding nature of the resulting contractual obligations and tighter regulatory control has demanded an equally vigorous programme of upgrading, replacement and renovation of many systems in order to improve the safety and reliability of the reactor. Not least among these changes is the more effective training and deployment of operations personnel that has been necessitated as the operational demands on the reactor evolved from five days per week to twenty four hours per day, seven days per week, with more than 300 days per year at full power. This paper briefly sketches the operational history of SAFARI-1 and then focuses on the training and structuring currently in place to meet the operational needs. There is a detailed step-by-step look at the operator?s career plan and pre-defined milestones. Shift work, especially the shift cycle, has a negative influence on the operator's career path development, especially due to his unavailability for training. Methods utilised to minimise this influence are presented. The increase of responsibilities regarding the operation of the reactor, ancillaries and experimental facilities as the operator progresses with his career are discussed. (author)

IAEA Operational Safety Team Reviews Saint-Alban Nuclear Power Plant, France

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed safety practices at France's Saint-Alban Nuclear Power Plant (NPP) and has highlighted a set of strong practices as well as a series of recommendations to reinforce them. The IAEA assembled the team at the request of the Government of France to conduct an Operational Safety Review (OSART) of the Saint-Alban NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review from 20 September to 6 October 2010. The team was made up of experts from Belgium, Canada, the Czech Republic, Germany, Lithuania, the Netherlands, Slovakia, Sweden and the USA. An OSART mission is designed to review programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Saint-Alban conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely are under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: A safety guideline for outages; The use of remote video surveillance of fuel inspection and handling activities; A motivational tool for plant staff regarding the benefits of operating experience and associated corrective actions; and Use of a sophisticated key control system

Saint John lateral pipeline project: comprehensive study report

International Nuclear Information System (INIS)

1999-02-01

A descripion is given of the results of an environmental impact assessment of the construction of a natural gas pipeline that will bring gas from Maritimes and Northeast Pipeline Management Ltd.'s (M and NP) main transmission pipeline to clients in Lake Utopia and Saint John, NB. It will be 110 km long, and the Saint John lateral will join the mainline approximately 2 km south of Big Kedron Lake, NB. Various institutional, industrial, commercial and residential clients will be able to access the pipeline in the future, and it is intended to be capable of future expansion for markets along its route and for markets that become economically feasible in the future. A matrix was developed that relates environmental resources to Environmental Components of Concern (ECCs), and to the rationale for exclusion/inclusion of the ECC as a Valued Environmental Component (VECs). The positive benefits of the pipeline to clients in the Saint John area include: reduced dependence on foreign oil, fuel switching and price competition, lower air emission pollution, increased energy efficiency, and a source of energy that is secure and reliable. VECs were selected based on: concerns of various stakeholders including the public, community groups, scientific parties, Aboriginal groups, government officials and agencies, relevant regulations; relevant literature; and past evaluation experiences, including future developments of the proposed study area. Further selection of the VECs required an examination of the issues picked out via scoping to determine the ways in which the overall project could affect the ECCs, and included construction, operation, decommissioning/abandonment, malfunctions and accidents of the pipeline. The phases of the project as they impacted residually and cumulatively on the VECs were evaluated, and impacts on Valued Socio-Economic Components (VSCs) were assessed also. The mitigation efforts taken will minimize the potential effects of the project on VECs and VSCs

The research reactor as a tool in the master in nuclear reactors in Argentina

International Nuclear Information System (INIS)

Notari, Carla

2003-01-01

complete the Master with a seminar: Nuclear Power Plants, and a Thesis. In the frame of the academic plan, multiple activities are organized related to research reactors and also to nuclear power plants. Since the very beginning the performance of selected experiments in a nuclear reactor was recognized as an extraordinary tool to give the students an insight in the principal phenomena associated with the chain reaction and the related engineering problems. This experiments have an intrinsic elevated cost, associated with the relevance of the installation and with the specialized personnel involved. CNEA provides the career with this educational instrument through the Ra-1 and RA-3 reactors located at Constituyentes and Ezeiza Atomic Centers respectively. Various activities are under way but the most established, in the Reactor Physics Course, is the estimation of kinetic parameters in RA-1 reactor. The practice includes three different experiments: Approach to critical and calibration of control rods by the compensation method: Starting in a subcritical state with source the calibration of control rod B1 vs B2 is done by introduction of the first and withdrawal of the second. The methods used are based on the Point Kinetic Model; Measurement of control rods effectivity by the rod-drop method: Separate Rod Drop of rods B1 B2 B3 of the overall ensemble B1 B2 B3 B4 and total scram starting with three withdrawn and one partially inserted, is the procedure followed to estimate the reactivity worth of B1 B2 B3 and scram. The Point Kinetic Model and the Modal Kinetic Model are used; Reactor noise technique for the estimation of reactor parameters: α and Λ. The kinetic parameters are estimated assuring that the Point Kinetic Model is valid (detection chambers near to the core), that the fluctuation of the fission density is the dominant source of the correlated part of neutron noise (measurement at low power, <10kw), the dominance of the fundamental armonic (simultaneous use of

Importance of self-shielding for improving sensitivity coefficients in light water nuclear reactors

International Nuclear Information System (INIS)

Foad, Basma; Takeda, Toshikazu

2014-01-01

Highlights: • A new method has been developed for calculating sensitivity coefficients. • This method is based on the use of infinite dilution cross-sections instead of effective cross-sections. • The change of self-shielding factor due to cross-section perturbation has been considered. • SRAC and SAINT codes are used for calculating improved sensitivities, while MCNP code has been used for verification. - Abstract: In order to perform sensitivity analyzes in light water reactors where self-shielding effect becomes important, a new method has been developed for calculating sensitivity coefficient of core characteristics relative to the infinite dilution cross-sections instead of the effective cross-sections. This method considers the change of the self-shielding factor due to cross-section perturbation for different nuclides and reactions. SRAC and SAINT codes are used to calculate the improved sensitivity; while the accuracy of the present method has been verified by MCNP code and good agreement has been found

Interrater reliability of the Saint-Anne Dargassies Scale in assessing the neurological patterns of healthy preterm newborns

Directory of Open Access Journals (Sweden)

Carla Ismirna Santos Alves

Full Text Available Abstract Objectives: to assess the interrater reliability of the Saint-Anne Dargassies Scale in assessing neurological patterns of healthy preterm newborns. Methods: twenty preterm newborns met the inclusion criteria for participation in this prospective study. The neurologic examination was performed using the Saint-Anne Dargassies Scale, showing normal serial cranial ultrasound examination. In order to test the reliability, the study was structured as follows: group I (rater 1/physiotherapist; rater 2/neonatologist; group II (rater 3/physiotherapist; rater 4/child neurologist and the gold standard (expert and professor in pediatric neurology. Results: high interrater agreement was observed between groups I - II compared with the gold standard in assessing postural pattern (p<0.01. Regarding the assessment ofprimitive reflexes, greater agreement was observed in the evaluation of palmar grasp reflex and Moro reflex (p< 0.01 for group I compared with the gold standard. An analysis of tone demonstrated heterogeneous agreement, without compromising the reliability of the scale. The probability of equality between measurements of head circumference in the two groups, compared with the gold standard, was observed. Conclusions: the Saint-Anne Dargassies Scale demonstrated high reliability and homogeneity with significant power of reproducibility and may be capable to identify preterm newborns suspected of having neurological deficits.

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Karel, Matejka; Lubomir, Sklenka

2005-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilisation - i.e. extensive educational programme. The educational programme is intended for the training of university students (all technical universities in Czech Republic) and selected nuclear power plant personnel. At the present, students can go through more than 20 different experimental exercises. An attractive programme including demonstration of reactor operation is prepared also for high school students. Moreover, research and development works and information programmes proceed at the VR-1 reactor as well

Comparison calculation of a large sodium-cooled fast breeder reactor using the cell code MICROX-2 in connection with ENDF/B-VI and JEF-1.1 neutron data

International Nuclear Information System (INIS)

Pelloni, S.

1992-02-01

We have obtained results for a large sodium-cooled fast breeder reactor benchmark using data from the ENDF/B-VI and from Revision 1 of the JEF-1 (JEF-1.1) evaluation. The required cross sections were processed with the NJOY code system (Version 89.62) and homogenized with the spectrum cell code MICROX-2. Multigroup transport-theory calculations in 33 neutron groups (forward and adjoint) were performed using the two-dimensional code TWODANT and kinetic parameters were determined using the first-order perturbation-theory code PERT-V. We calculated eigenvalues, neutron balance data, global and regional breeding and conversion ratios, central rate ratios and reactivity worths with and without sodium, effective delayed neutron fraction and inhour reactivity, regional sodium void reactivity, and isothermal core fuel Doppler-reactivities. In particular, it is shown that good agreement (generally within one standard deviation) is achieved between these results and the average values over sixteen benchmark solutions obtained in the past. The eigenvalues predicted with ENDF/B-VI are up to 0.7% larger than those calculated with JEF-1.1 cross sections. This discrepancy is mainly due to different inelastic scattering cross sections for 23 Na and 238 U, and to different fast fission and nubar data for 239 Pu. (author) 5 figs., 30 tabs., 24 refs

A School-Based Enterprise: The Saint Pauls, North Carolina Experience.

Science.gov (United States)

Paquin, Thomas F.

1991-01-01

The superintendent of Saint Pauls Schools describes how educators, community leaders, businesspersons, and high school students worked together to develop the Way Off Broadway Deli, a successful school-based enterprise providing experiential education in entrepreneurship and small business management, as well as student employment and local…

Ecole d’été de probabilités de Saint-Flour XXVIII

CERN Document Server

2000-01-01

This volume contains lectures given at the Saint-Flour Summer School of Probability Theory during 17th Aug. - 3rd Sept. 1998. The contents of the three courses are the following: - Continuous martingales on differential manifolds. - Topics in non-parametric statistics. - Free probability theory. The reader is expected to have a graduate level in probability theory and statistics. This book is of interest to PhD students in probability and statistics or operators theory as well as for researchers in all these fields. The series of lecture notes from the Saint-Flour Probability Summer School can be considered as an encyclopedia of probability theory and related fields.

BETHSY 9.1b Test Calculation with TRACE Using 3D Vessel Component

International Nuclear Information System (INIS)

Berar, O.; Prosek, A.

2012-01-01

Recently, several advanced multidimensional computational tools for simulating reactor system behaviour during real and hypothetical transient scenarios were developed. One of such advanced, best-estimate reactor systems codes is TRAC/RELAP Advanced Computational Engine (TRACE), developed by the U.S. Nuclear Regulatory Commission. The advanced TRACE comes with a graphical user interface called SNAP (Symbolic Nuclear Analysis Package). It is intended for pre- and post-processing, running codes, RELAP5 to TRACE input deck conversion, input deck database generation etc. The TRACE code is still not fully development and it will have all the capabilities of RELAP5. The purpose of the present study was therefore to assess the 3D capability of the TRACE on BETHSY 9.1b test. The TRACE input deck was semi-converted (using SNAP and manual corrections) from the RELAP5 input deck. The 3D fluid dynamics within reactor vessel was modelled and compared to 1D fluid dynamics. The 3D calculation was compared both to TRACE 1D calculation and RELAP5 calculation. Namely, the geometry used in TRACE is basically the same, what gives very good basis for the comparison of the codes. The only exception is 3D reactor vessel model in case of TRACE 3D calculation. The TRACE V5.0 Patch 1 and RELAP5/MOD3.3 Patch 4 were used for calculations. The BETHSY 9.1b test (International Standard Problem no. 27 or ISP-27) was 5.08 cm equivalent diameter cold leg break without high pressure safety injection and with delayed ultimate procedure. BETHSY facility was a 3-loop replica of a 900 MWe FRAMATOME pressurized water reactor. For better presentation of the calculated physical phenomena and processes, an animation model using SNAP was developed. In general, the TRACE 3D code calculation is in good agreement with the BETHSY 9.1b test. The TRACE 3D calculation results are as good as or better than the RELAP5 calculated results. Also, the TRACE 3D calculation is not significantly different from TRACE 1D

The “Enemy” of the Saint in the Vita Fulgentii

Directory of Open Access Journals (Sweden)

Isabella D'Auria

2015-06-01

Full Text Available This paper aims to analyze the traits that characterize the “enemy” of the saint in the Vita Fulgentii. The work tells in twenty-nine chapters the life of the bishop of Ruspe Fulgentius, troubled by exile and persecutions both in the monastic phase and in the episcopal one, in the context of the vandalic invasion in Africa between 5th and 6th century. The “enemy”, that identifies, in the most cases, with the invader of arian faith, presents a stereotyped nature, summarizing the tipical characteristics of barbarian and the ones specific to the heterodox. In order to achieve the goal of the reader’s moral edification, the text presents antithetical models, the saint ant his opposer, and all the account revolves around this dialectic; so it is worthy of interest to pick out the elements that define, throught a relationship of opposition, the collective identities, that in this text are represented by Catholics invaded and by barbarian and heretic invaders.

Stability analysis of the Ghana Research Reactor-1 (GHARR-1)

International Nuclear Information System (INIS)

Della, R.; Alhassan, E.; Adoo, N.A.; Bansah, C.Y.; Nyarko, B.J.B.; Akaho, E.H.K.

2013-01-01

Highlights: • We developed a theoretical model to study the stability of the Ghana Research Reactor-1. • The neutronics transfer function was described by the point kinetics model for a single group of delayed neutrons. • The thermal hydraulics transfer function was based on the modified lumped parameter concept. • A computer code, RESA (REactor Stability Analysis) was developed. • Results show that the closed-loop transfer function was stable and well damped for variable operating power levels. - Abstract: A theoretical model has been developed to study the stability of the Ghana Research Reactor one (GHARR-1). The closed-loop transfer function of GHARR-1 was established based on the model, which involved the neutronics and the thermal hydraulics transfer functions. The reactor kinetics was described by the point kinetics model for a single group of delayed neutrons, whilst the thermal hydraulics transfer function was based on the modified lumped parameter concept. The inherent internal feedback effect due to the fuel and the coolant was represented by the fuel temperature coefficient and the moderator temperature coefficient respectively. A computer code, RESA (REactor Stability Analysis), entirely in Java was developed based on the model for systems analysis. Stability analysis of the open-loop transfer function of GHARR-1 based on the Nyquist criterion and Bode diagrams using RESA, has shown that the closed-loop transfer function was marginally stable for variable operating power levels. The relative stability margins of GHARR-1 were also identified

RAPID-L Highly Automated Fast Reactor Concept Without Any Control Rods (1) Reactor concept and plant dynamics analyses

International Nuclear Information System (INIS)

Kambe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Iwamura, Takamichi

2002-01-01

The 200 kWe uranium-nitride fueled lithium cooled fast reactor concept 'RAPID-L' to achieve highly automated reactor operation has been demonstrated. RAPID-L is designed for Lunar base power system. It is one of the variants of RAPID (Refueling by All Pins Integrated Design), fast reactor concept, which enable quick and simplified refueling. The essential feature of RAPID concept is that the reactor core consists of an integrated fuel assembly instead of conventional fuel subassemblies. In this small size reactor core, 2700 fuel pins are integrated altogether and encased in a fuel cartridge. Refueling is conducted by replacing a fuel cartridge. The reactor can be operated without refueling for up to 10 years. Unique challenges in reactivity control systems design have been attempted in RAPID-L concept. The reactor has no control rod, but involves the following innovative reactivity control systems: Lithium Expansion Modules (LEM) for inherent reactivity feedback, Lithium Injection Modules (LIM) for inherent ultimate shutdown, and Lithium Release Modules (LRM) for automated reactor startup. All these systems adopt lithium-6 as a liquid poison instead of B 4 C rods. In combination with LEMs, LIMs and LRMs, RAPID-L can be operated without operator. This is the first reactor concept ever established in the world. This reactor concept is also applicable to the terrestrial fast reactors. In this paper, RAPID-L reactor concept and its transient characteristics are presented. (authors)

Neutron radiography in the IEA-R1 reactor

International Nuclear Information System (INIS)

Pugliesi, R.; Moraes, A.P.V. de; Yamazaki, I.M.; Freitas Acosta, C. de.

1988-08-01

Neutronradiography of several materials have been obtained at the IEA-R1 Nuclear Research Reactor (IPEN-CNEN/SP), by means of two conversion techniques: a) (n, α) at the beam-hole n 0 3 where a collimated thermal neutron beam, exposure area 4 cm x 8cm and flux at the sample 10 5 n/s cm 2 is obtained. The film used was the CN-85 cellulose nitrate coated with lithium tetraborate (conversor). The time irradiation of the film was 15 minutes and in following was eteched during 30 minutes in a NaOH(10%) aqueous solution at a constant temperature of 60 0 C.; b) (n,γ) by using an experimental arrangement installed in the botton of the pool of the reactor. The flux of the collimated neutron beam is 10 5 n/s/cm 2 at the sample and the conversion is made by means of a dysprozium sheet. The film used was Kodak T-5. The irradiation and the transfering time was 2 hours and 20 hours respectively. (author) [pt

Determination of the neutron spectrum at different locations in the Argentine RA-1 Reactor; Determinacion del espectro neutronico en distintas posiciones del reactor RA-1

Energy Technology Data Exchange (ETDEWEB)

Lerner, A M; Madariaga, M R [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

1999-12-31

Full text: It is well known that the RA-1 reactor is used to irradiate different types of materials with neutrons. The Radio dosimetry Group (which belongs to the Nuclear Regulatory Authority) uses its fast column for the design, calibration and set up of criticality dosimeters as well as for a quick assessment of the dose to workers in case of an accident. With such purpose, Au(1), Au under Cd and In(2) foils were irradiated to estimate absolute thermal, epithermal and fast neutron fluxes at the irradiation location. The accuracy of this estimation is higher when the response to the present neutron spectrum of the different materials constituting the detectors is better known. This, in turn, requires the previous knowledge of such spectrum (a detailed energy dependence of neutron flux) at the analysed location. In this work a neutronic calculation is presented at the fast irradiation location. The whole calculation was carried out following two different methodologies, and considering a power of 40 kW. The reactor and its surroundings were represented by a simplified one-dimensional model, as a concentric cylindrical set of regions. Figures are drawn representing fast and thermal fluxes (with the cut at 0.4 eV) as a function of the distance to the core centre. The neutron flux (in n/cm{sup 2}sec.eV) as a function of energy is also shown at the fast irradiation location. Values of flux (in n/cm{sup 2}.sec.eV) are also provided as a function of energy in other typical locations, as well as the equivalent integrated flux values (in n/cm{sup 2}.sec). ((1) According to the reaction Au{sup 197}(n,{gamma})Au{sup 198}, having a cross section of {sigma}{sub 0}=98.8b for thermal neutrons. (2) According to the reaction In{sup 115}(n,n`)In{sup 115m}, with a cross section of some 70 mb for neutrons with energies above 1.2MeV). (author) [Espanol] Texto completo: Como se sabe, el reactor RA1 se utiliza para irradiar con neutrones distintos tipos de materiales. El grupo de

Bunker culturel : la régénération du patrimoine militaire urbain à Saint-Nazaire

Directory of Open Access Journals (Sweden)

Renzo Lecardane

2011-06-01

Full Text Available Au cours des deux dernières décennies Saint-Nazaire a relancé son développement sans se référer nécessairement aux modèles des métropoles européennes. Concentrées autour de la zone portuaire, près de la base sous-marine allemande, les nouvelles opérations urbaines ont contribué à définir un important projet touristique et culturel. La spécificité symbolique et la valorisation du patrimoine militaire ont permis à Saint-Nazaire de montrer que l’identité d’une ville pouvait activer sa croissance.Over the last two decades, the port city of Saint-Nazaire has encouraged urban redevelopment without necessarily following the models suggested by other European cities. An important cultural and tourist centre has been developed around the port zone, close to the German submarine base dating from the Second World War. The symbolic specificity and the interpretation of this military heritage have shown, at Saint-Nazaire, how a town's special identity can foster growth.

Revision of by-laws about effluents of EdF's nuclear power plants

International Nuclear Information System (INIS)

2002-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

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

Chooz B1 start-up marked by total computer control

International Nuclear Information System (INIS)

Anon.

1995-01-01

The start-up of Chooz B1, the first of EdF's latest generation 1450 MWe N4 reactors, marks the first use in a nuclear power plant of a fully computerised control room. Working in partnership with EdF, Sema Group designed and supplied the advanced command and control system for this plant. (Author)

The eleventh CRL-Salmonella workshop, 9 May 2006, Saint Malo, France

NARCIS (Netherlands)

Mooijman KA; MGB

2006-01-01

De elfde workshop georganiseerd door het Communautair Referentie Laboratorium voor Salmonella (CRL-Salmonella) werd gehouden op 9 mei 2006 in Saint Malo, Frankrijk. Deelnemers waren vertegenwoordigers van de nationale Referentie Laboratoria voor Salmonella (NRLs-Salmonella) van de lidstaten van de

Estimation of radioactivity in structural materials of ETRR-1 reactor

Energy Technology Data Exchange (ETDEWEB)

Imam, M [National Center for Nuclear Safety and Radiation Control Atomic Energy Authority, Cairo (Egypt)

1997-12-31

Precise knowledge of the thermal neutron flux in the different structural materials of a reactor is necessary to estimate the radioactive inventory in these materials that are needed in any decommissioning study of the reactor. ETRR-1 is a research reactor that went critical on 2/1691. In spite of this long age of the reactor, the effective operation time of this reactor is very short since the reactor was shutdown for long periods. Because of this long age one may think of reactor decommissioning. For this purpose, the radioactivity of the reactor structural materials was estimated. Apart from the reactor core, the important structural materials in the ETRR-1 are the reactor tank, shielding concrete, and the graphite thermal column. The thermal neutron flux was determined by the monte Carlo method in these materials and the isotope inventory and the radioactivity were calculated by the international code ORIGEN-JR. 1 fig.

Code-B-1 for stress/strain calculation for TRISO fuel particle (Contract research)

International Nuclear Information System (INIS)

Aihara, Jun; Ueta, Shohei; Shibata, Taiju; Sawa, Kazuhiro

2011-12-01

We have developed Code-B-1 for the prediction of the failure probabilities of the coated fuel particles for the high temperature gas-cooled reactors (HTGRs) under operation by modification of an existing code. A finite element method (FEM) is employed for the stress calculation part and Code-B-1 can treat the plastic deformation of the coating layer of the coated fuel particles which the existing code cannot treat. (author)

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

African Journals Online (AJOL)

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

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

African Journals Online (AJOL)

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

Diet of the oilfish Ruvettus pretiosus (Perciformes: Gempylidae in the Saint Peter and Saint Paul archipelago, Brazil

Directory of Open Access Journals (Sweden)

Danielle de Lima Viana

2012-06-01

Full Text Available Feeding aspects of the oilfish, Ruvettus pretiosus, were studied based on 360 stomachs of both male and female specimens caught off the Saint Peter and Saint Paul Archipelago. The total length of the specimens ranged from 52.4 cm to 189.0 cm. Of the 360 stomachs examined, 135 presented some food and 225 were empty. Thirty-four taxa were identified, represented by 16 fish, 17 cephalopods and 1 crustacean. The stabilization of the food items richness was attained at 35 food items and 104 stomachs, approximately. A remarkable predation upon the flying fish Cheilopogon cyanopterus was observed around SPSPA, directly related to the main reproductive period of this species in the area. The oilfish's food spectrum shows that the species feeds on a wide vertical range in the water column, catching prey items at the surface or in shallow waters, as well as epi-mesopelagic fish, in addition to mesopelagic cephalopods.Aspectos alimentares do peixe-prego, Ruvettus pretiosus, foram estudados com base nos estômagos de 360 espécimes, de ambos os sexos, capturados nos arredores do Arquipélago de São Pedro e São Paulo. Todos os exemplares foram capturados com linha de mão. O comprimento total dos exemplares variou de 52,4 cm a 189,0 cm. Dos 360 estômagos examinados, 135 apresentaram algum alimento e 225 estavam vazios. Trinta e quatro táxons foram identificados, representados por 16 peixes, 17 cefalópodes e um crustáceo. A estabilização da riqueza dos itens alimentares foi obtida com 35 itens e 104 estômagos. Uma predação notável sobre o peixe-voador Cheilopogon cyanopterus foi observada nas adjacências do ASPSP, diretamente relacionada com o principal período reprodutivo dessa espécie na área. O espectro alimentar do peixe-prego mostra que a espécie se alimenta em uma ampla faixa vertical na coluna d'agua, capturando desde presas de superfície ou águas rasas, a peixes epi-mesopelágicos, além de cefalópodes mesopelágicos.

Teinturerie Riboud, Sainte-Marie-aux-Mines. Carrefour de Ribeauvillé (lieu dit " Sur le Pré ").

OpenAIRE

Fluck , Pierre

2007-01-01

L'usine est un héritage d'un bâtiment très ancien, acheté par Martin Riboud en 1837 et modifié pour les besoins de la production industrielle. Riboud et Ziegler avaient créé à l'origine une teinturerie au 6, rue Saint-Louis en 1829. Dès les années 1830, l'entreprise s'installa au carrefour de Ribeauvillé sur le site de l'ancienne maison du juge des mines. En 1850, l'entreprise porte la raison Riboud Frères. Depuis 1947, Société des teintureries de l'Est. Fermeture en janvier 2011. Les fabrica...

Emergency response guide-B ECCS guideline evaluation analyses for N reactor

International Nuclear Information System (INIS)

Chapman, J.C.; Callow, R.A.

1989-07-01

INEL conducted two ECCS analyses for Westinghouse Hanford. Both analyses will assist in the evaluation of proposed changes to the N Reactor Emergency Response Guide-B (ERG-B) Emergency Core System (ECCS) guideline. The analyses were a sensitivity study for reduced-ECCS flow rates and a mechanistically determined confinement steam source for a delayed-ECCS LOCA sequence. The reduced-ECCS sensitivity study established the maximum allowable reduction in ECCS flow as a function of time after core refill for a large break loss-of-coolant accident (LOCA) sequence in the N Reactor. The maximum allowable ECCS flow reduction is defined as the maximum flow reduction for which ECCS continues to provide adequate core cooling. The delayed-ECCS analysis established the liquid and steam break flows and enthalpies during the reflood of a hot core following a delayed ECCS injection LOCA sequence. A simulation of a large, hot leg manifold break with a seven-minute ECCS injection delay was used as a representative LOCA sequence. Both analyses were perform using the RELAP5/MOD2.5 transient computer code. 13 refs., 17 figs., 3 tabs

A Pebble-Bed Breed-and-Burn Reactor

International Nuclear Information System (INIS)

Greenspan, Ehud

2016-01-01

The primary objective of this project is to use three-dimensional fuel shuffling in order to reduce the minimum peak radiation damage of ~550 dpa present Breed-and-Burn (B&B) fast nuclear reactor cores designs (they feature 2-D fuel shuffling) call for to as close as possible to the presently accepted value of 200 dpa thereby enabling earlier commercialization of B&B reactors which could make substantial contribution to energy sustainability and economic stability without need for fuel recycling. Another objective is increasing the average discharge burnup for the same peak discharge burnup thereby (1) increasing the fuel utilization of 2-D shuffled B&B reactors and (2) reducing the reprocessing capacity required to support a given capacity of FRs that are to recycle fuel.

A Pebble-Bed Breed-and-Burn Reactor

Energy Technology Data Exchange (ETDEWEB)

Greenspan, Ehud [Univ. of California, Berkeley, CA (United States)

2016-03-31

The primary objective of this project is to use three-dimensional fuel shuffling in order to reduce the minimum peak radiation damage of ~550 dpa present Breed-and-Burn (B&B) fast nuclear reactor cores designs (they feature 2-D fuel shuffling) call for to as close as possible to the presently accepted value of 200 dpa thereby enabling earlier commercialization of B&B reactors which could make substantial contribution to energy sustainability and economic stability without need for fuel recycling. Another objective is increasing the average discharge burnup for the same peak discharge burnup thereby (1) increasing the fuel utilization of 2-D shuffled B&B reactors and (2) reducing the reprocessing capacity required to support a given capacity of FRs that are to recycle fuel.

La fouille du fort Saint-Georges à Chinon (Indre-et-Loire. Premiers résultats The excavation of fort Saint-Georges at Chinon (Indre-et-Loire. First results

Directory of Open Access Journals (Sweden)

Bruno Dufaÿ

2006-05-01

Full Text Available Cette note présente les premiers résultats des fouilles menées en 2003 et 2004 sur la quasi-totalité du fort Saint-Georges à Chinon (Indre-et-Loire. Celui-ci est l’un des trois éléments de la forteresse médiévale qui domine la ville. La fouille a permis de préciser la fonction du fort, construit dans la deuxième moitié du XIIe s., à l’époque où Chinon est le centre administratif des possessions continentales des Plantagenêt, rois d’Angleterre. Du point de vue militaire, il formait une fortification avancée, protégeant le château principal, selon une structure que Richard Cœur de Lion appliquera au Château Gaillard. À l’intérieur, de vastes bâtiments constituaient des logis, conçus peut-être au départ pour héberger la chancellerie royale.This article presents the first results of the excavations undertaken in 2003 and 2004 over almost all of the Fort Saint-Georges at Chinon (Indre-et-Loire, one of three elements of the medieval fortress which dominates the town. The excavation enabled us to clarify the function of the fort, built in the 2nd half of the 12th century at a time when Chinon was the administrative centre of the continental possesions of the Plantagenet King of England. From a military point of view, it formed an advanced fortification protecting the main castle, within a structure that Richard the Lionheart would apply to the Chayeau Gaillard. Inside, some vast buildings made up the dwellings, designed perhaps initially to house the royal chanceller.

Reactor pressure vessel steels ASTM A533B and A508 Cl.2

International Nuclear Information System (INIS)

Pelli, R.; Kemppainen, M.; Toerroenen, K.

1979-11-01

This report presents the tensile test results of steels ASTM A533B and A508 Cl.2 obtained in connection with a programme initiated to gather and create information needed for the assessment of the structural integrity of the reactor pressure vessels. The tensile properties were studied between -196 and 300 degC varying austenitizing and tempering temperatures and having two different carbon contents for the heats of A533B. (author)

Saint Venant's equation and theory of characteristics

International Nuclear Information System (INIS)

Daubert, Andre

1978-01-01

This theory, in its general scope, will be dealt with through the concrete example of Saint Venant's equations which govern the waves in channels. 1. Finding the characteristic directions. The aim is to interpret the hyperbolic sort of equations to show that there is a way of combining them in order to shape them so that they express a linear relation between the variations of the unknowns when moving along particular differential paths. In certain cases, this differential relation can integrate to lead to Rieman's invariants. 2. Relation between the theory of characteristics and the wave equation. In the linear systems case, it is worthwhile showing simply, how the method of characteristics is linked to the conventional treatment of the wave equation. 3. Relation between the theory of characteristics and the Cauchy problem. The theory of characteristics is frequently introduced as from the Cauchy problem, the characteristics forming the conditions of indetermination of the Cauchy problem [fr

Multiple Irradiation Capsule Experiment (MICE)-3B Irradiation Test of Space Fuel Specimens in the Advanced Test Reactor (ATR) - Close Out Documentation for Naval Reactors (NR) Information

Energy Technology Data Exchange (ETDEWEB)

M. Chen; CM Regan; D. Noe

2006-01-09

Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (low fission rate, high temperature, long duration). As such, basic testing is required to validate predictions (and in some cases determine) performance aspects of these fuels. Therefore, the MICE-3B test of UO{sub 2} pellets was designed to provide data on gas release, unrestrained swelling, and restrained swelling at the upper range of fission rates expected for a space reactor. These data would be compared with model predictions and used to determine adequacy of a space reactor design basis relative to fission gas release and swelling of UO{sub 2} fuel and to assess potential pellet-clad interactions. A primary goal of an irradiation test for UN fuel was to assess performance issues currently associated with this fuel type such as gas release, swelling and transient performance. Information learned from this effort may have enabled use of UN fuel for future applications.

Operation characteristics and conditions of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Polach, S.; Sklenka, L.

1994-01-01

The first 3 years of operation of the VR-1 training reactor are reviewed. This period includes its physical start-up (preparation, implementation, results) and operation development as far as the current operating configuration of the reactor core. The physical start-up was commenced using a reactor core referred to as AZ A1, whose physical parameters had been verified by calculation and whose configuration was based on data tested experimentally on the SR-0 reactor at Vochov. The next operating core, labelled AZ A2, was already prepared during the test operation of the VR-1 reactor. Its configuration was such that both of the main horizontal channels, radial and tangential, could be employed. The configuration that followed, AZ A3, was an intermediate step before testing the graphite side reflector. The current reactor core, labelled AZ A3 G, was obtained by supplementing the previous core with a one-sided graphite side reflector. (Z.S.). 2 tabs., 11 figs., 2 refs

REX1-87, Multigroup Neutron Cross-Sections from ENDF/B

International Nuclear Information System (INIS)

Gopalakrishnan, V.; Ganesan, S.

1988-01-01

1 - Description of program or function: The program calculates self- shielding factors for reactor applications from a pre-processed (linearized) evaluated nuclear data file in the ENDF/B format. 2 - Method of solution: Bondarenko definition of multigroup self- shielding factors invoking narrow resonance treatment is used. 3 - Restrictions on the complexity of the problem: a) Maximum no. of energy group is 620. b) Only the built-in forms of the weighting functions can be chosen. c) The program is strictly limited to resolved resonance region from physical considerations

Burnup measurements at the RECH-1 research reactor

International Nuclear Information System (INIS)

Henriquez, C.; Navarro, G.; Pereda, C.; Torres, H.; Pena, L.; Klein, J.; Calderon, D.; Kestelman, A.J.

2002-01-01

The Chilean Nuclear Energy Commission has decided to produce LEU fuel elements for the RECH-1 research reactor. During December 1998, the Fuel Fabrication Plant delivered the first four fuel elements, called leaders, to the RECH-1 reactor. The set was introduced into the reactor's core, following the normal routine, but performing a special follow-up on their behavior inside and outside the core. In order to measure the burn-up of the leader fuel elements, it was decided to develop a burn-up measurements system to be installed into the RECH-1 reactor pool, and to decline the use of a similar system, which operates in a hot cell. The main reason to build this facility was to have the capability to measure the burn-up of fuel elements without waiting for long decay period. This paper gives a brief description of the facility to measure the burn-up of spent fuel elements installed into the reactor pool, showing the preliminary obtained spectra and briefly discussing them. (author)

AN ORTHODOX THINKER AND A ROMANIAN HEART: THE SAINT HIERARCH ANTHIM

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Henrieta Anişoara ŞERBAN

2016-10-01

Full Text Available 2016 is an anniversary year, dedicated to the Saint Hierarch Anthim, a multi-faced personality of Georgian origin, but with a Romanian accomplished life. He was a true Orthodox believer, a Hierarch of our Orthodox Church in Wallachia and a deep thinker, who lived through the teachings of the faith. At the same time, he was a good manager and a philanthropist, a scholar, a polyglot, a calligrapher, a typographer, a Church architect, an orator turned writer, a painter and a sculptor. His great homiletic work entitled Didahiile sends to Didache, the oldest post-Bible Christian text, famous at Constantinople, known also as The Teachings of the Twelve Apostles (The Teachings of the Lord to the Gentiles (or Nations by the Twelve Apostles. The study approaches and develops these dimensions of the personality and of the thought of the Saint Hierarch Anthim, in order to emphasize both his life and his work as an esteemed symbol of the Orthodox faith.

Concept on coupled spectrum B/T (burning and/or transmutation) reactor for treatment of minor actinides by thermal and fast neutrons

International Nuclear Information System (INIS)

Aziz, Ferhat; Kitamoto, Asashi

1996-01-01

A conceptual design of B/T (burning and/or transmutation) reactor based on a modified conventional 1150 MWe-PWR system, with core consisted of two concentric regions for thermal and fast neutrons, was proposed herein for B/T treatment of MA (minor actinides). The B/T fuel considered was supposed such that MA discharged from 1 GWe-LWR was blended homogeneously with the composition of LWR fuel. In the outer region 23- Np, 241 Am and 243 Am were loaded and burned by thermal neutron, while in the inner region 244 Cm was loaded and burned mainly by fast neutron. The geometry of B/T fuel and the fuel assembly in the outer region was left in the same condition to those of standard PWR while in the inner region the B/T fuel was arranged in the hexagonal geometry, allowed high fuel to coolant volume ratio (V m /V f ), to keep the harder neutron spectrum. Two cases of the Coupled Spectrum B/T Reactor (CSR) with different (V m 1 f ) ratio in the inner region were studied, and the results for the tight lattice with (V m /V f ) = 0.5 showed that those isotopes approached the equilibrium composition after about 5 recycle period, when the CSR was operated under the reactivity swing of 2.8 % dk/k. The evaluations on the void coefficient of reactivity, the Doppler effect and the reactivity swing showed that the CSR concept has the inherent safety and can burn and/or transmute all kind of MA in a single reactor. This CSR can burn about 808 kg of MA in one recycle period of 3 years, which is equivalent to the discharged fuel from about 12 units of LWR in a year. (author)

"Das Konkrete ist das Abstrakte, an das man sich schließlich gewöhnt hat." (Laurent Schwartz) Über den Ablauf des mathematischen Verstehens

Science.gov (United States)

Lowsky, Martin

Die im Titel genannte Aussage findet sich in den Lebenserinnerungen von Laurent Schwartz (1915-2002), einem der fruchtbarsten Mathematiker, Mitglied der Gruppe Bourbaki. Im Original lautet die Aussage: "un objet concret est un objet abstrait auquel on a fini par s'habituer." Schwartz erläutert sie am Beispiel des Integrals über {e^{-1/2{x^2}}} , das den Wert Wurzel aus 2π hat und in dem sich also die Zahlen e und π verknüpfen. Was Schwartz aber vor allem ausdrücken will, ist dies: Das mathematische Verständnisd geht langsam vor sich und es bedarf der Anstrengung. "Es ist eine Frage der Zeit und der Energie", sagt Schwartz, und gerade dies mache es so schwer, die höhere Mathematik unter das Volk zu bringen. Das Lernen und Lehren von Mathematik laufe eben mühevoll und langsam ab.

Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option nuclear reactor

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This document describes the specific dispositions relative to the nuclear reactor domain, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the nuclear reactor and of the retraining, the Passerelle formation, are presented. (A.L.B.)

[Saints and illnesses in faith and paleopathological evidences].

Science.gov (United States)

Fulcheri, Ezio

2006-01-01

The exhumation of the natural mummies of Beata Margherita di Savoia (1390-1464) and of St. Caterina Fieschi Adorno (1447-1510) has not been followed by autopsy or histological exams. The aim has been to preserve the integrity of the saints' corpses. We have thus proceeded to a confrontation between data gathered from chronicles and hagiographies and radiological exams and macroscopic observations. The article aims at establishing a model for a multidisciplinar approach to paleopathological research, integrating historical research and medical knowledge.

Evaluation of Codisposal Viability for TH/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel

International Nuclear Information System (INIS)

Radulescu, H.

2001-01-01

There are more than 250 forms of US Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The Fort Saint Vrain reactor (FSVR) SNF has been designated as the representative fuel for the Th/U carbide fuel group. The FSVR SNF consists of small particles (spheres of the order of 0.5-mm diameter) of thorium carbide or thorium and high-enriched uranium carbide mixture, coated with multiple, thin layers of pyrolytic carbon and silicon carbide, which serve as miniature pressure vessels to contain fission products and the U/Th carbide matrix. The coated particles are bound in a carbonized matrix, which forms fuel rods or ''compacts'' that are loaded into large hexagonal graphite prisms. The graphite prisms (or blocks) are the physical forms that are handled in reactor loading and unloading operations, and which will be loaded into the DOE standardized SNF canisters. The results of the analyses performed will be used to develop waste acceptance criteria. The items that are important to criticality control are identified based on the analysis needs and result sensitivities. Prior to acceptance to fuel from the Th/U carbide fuel group for disposal, the important items for the fuel types that are being considered for disposal under the Th/U carbide fuel group must be demonstrated to satisfy the conditions determined in this report

Evaluation of Codisposal Viability for TH/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel

Energy Technology Data Exchange (ETDEWEB)

H. radulescu

2001-09-28

There are more than 250 forms of US Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The Fort Saint Vrain reactor (FSVR) SNF has been designated as the representative fuel for the Th/U carbide fuel group. The FSVR SNF consists of small particles (spheres of the order of 0.5-mm diameter) of thorium carbide or thorium and high-enriched uranium carbide mixture, coated with multiple, thin layers of pyrolytic carbon and silicon carbide, which serve as miniature pressure vessels to contain fission products and the U/Th carbide matrix. The coated particles are bound in a carbonized matrix, which forms fuel rods or ''compacts'' that are loaded into large hexagonal graphite prisms. The graphite prisms (or blocks) are the physical forms that are handled in reactor loading and unloading operations, and which will be loaded into the DOE standardized SNF canisters. The results of the analyses performed will be used to develop waste acceptance criteria. The items that are important to criticality control are identified based on the analysis needs and result sensitivities. Prior to acceptance to fuel from the Th/U carbide fuel group for disposal, the important items for the fuel types that are being considered for disposal under the Th/U carbide fuel group must be demonstrated to satisfy the conditions determined in this report.

Electric currents above Saint-Santin 3. A preliminary study of disturbances: June 6, 1978; March 22, 1979; March 23, 1979

International Nuclear Information System (INIS)

Mazaudier, C.

1985-01-01

This paper presents three case studies of ionospheric disturbances in electric fields, currents, and winds during periods of geomagnetic storms. These disturbances are detected by the Saint-Santin incoherent scatter radar. The disturbances are shown to originate from two distinct physical mechanism: (1) penetration of electric fields to lower latitudes during times of rapid change in magnetospheric convection; and (2) the action of the disturbed ionospheric dynamo driven by storm-induced wind disturbances. The storm of June 6, 1978, shows a simple illustration of penetrative convection electric fields. The storm of March 22, 1979, gives additional examples of this effect both when the B/sub Z/ component of the interplanetary fields turns southward and northward. The observed events on March 23 are clearly identifiable as the delayed response of the disturbance ionospheric dynamo

Neutron Spectrum Parameters In Inner Irradiation Channel Of The Nigeria Research Reactor-1 (NIRR-1) For Use In Absolute And KO-NAA Methods

International Nuclear Information System (INIS)

Jonah, S.A; Balogun, G.I; Mayaki, M.C.

2004-01-01

In Nigeria, the first Nuclear Reactor achieved critically on February 03, 2004 at about 11:35 GMT and has been commissioned or training and research. It is a Miniature Neutron Source Reactor (MNSR), code-named Nigeria Research Reactor-1 (NIRR-1). NIRR-1 has a tan-in-pool structural configuration and a nominal thermal power rating of 30 Kw. With a built-in clean old core excess reactivity of 3.77 mk determined during the on-site zero and critically experimental, the reactor can operate for a n.cm-2 .s-1 in the inner irradiation channels). Under these conditions, the reactor can operate with the same fuel loading for over ten years with a burn-up of <1%. A detailed description of operating characteristics for NIRR-1, measured during the on-site zero-power and criticality experiments has been given elsewhere. In order to extend its utilization to include absolute and ko-NAA methods, the neutron spectrum parameters in the irradiation channels: power and critically experiments has been given elsewhere. In order to extend it's the irradiation channels: thermal-to-epithermal flux ration, F; and epithermal flux shape factor, a in both the inner and outer irradiation channels must be determined experimentally. In this work, we have developed and experimental procedure for monitoring the neutron spectrum parameters in an inner irradiation channel based on irradiation and gamma-ray counting of detector foils via (n,y), (n,p) and (n,a) dosimetry reactions. Results obtained indicate that a thermal neutron flux of (5.14+-0.02) x 1011 n/c m2.s determined by foil activation method in the inner irradiation channel, B2, at a power level of 15.5 kw corresponds to the flux indicators on the control console and the micro-computer control system respectively. Other parameters of the neutron spectrum determined for inner irradiation channel B2, are: a -0.0502+0.003; 18.92+-0.14; F = 3.87=0.23. The method was validated through the comparison of our result with published neutron spectrum

[On the medical and publishing activities of the community of Saint Eugene].

Science.gov (United States)

2012-01-01

The article deals with the role the physicians played in organization and functioning of the Community of Saint Eugene in St. Petersburg in 1882-1918. The typography production of the Community being of interest for history of medicine is examined.

Colloquium act 'Nogent - 2001'

International Nuclear Information System (INIS)

Lagadec, P.; Lacoste, A.C.; Lazar, Ph.; Eimer, M.; Pouilloux, M.; Pellat, R.; Sene, R.; Schmitt, P.

2006-01-01

This colloquium is essentially devoted to the nuclear crisis and its management. As regards the nuclear crisis, it is especially about the behavior of the C.L.I. (local commissions of information) of the communication, the errors to be avoided and possible surprises. Several experiences are reported: the crisis exercise at the nuclear center of electric production (C.N.P.E.) of Saint-Laurent-des-Eaux, the experience of Cogema La hague in communication, transparency and communication for secret installations, the experience of an independent expert from the group of scientists for the information on nuclear (G.S.I.E.N.) and the local commission of information of Fessenheim. (N.C.)

Colloquium act 'Nogent - 2001'; Acte du colloque 'Nogent - 2001'

Energy Technology Data Exchange (ETDEWEB)

Lagadec, P. [Ecole Polytechnique, 75 - Paris (France); Lacoste, A.C. [Ministere de l' Economie, des Finances et de l' Industrie, Dir. de la Surete des Installation Nucleaires, 75 - Paris (France); Lazar, Ph. [Conseil Superieur de la Surete et de l' Information Nucleaires (CSSIN), 75 - Paris (France); Eimer, M. [Commissions locales d' Information et de Surveillance (CLIS), 41 - Saint Laurent des Eaux (France); Pouilloux, M. [Cogema la Hague, 50 - Beaumont Hague (France); Pellat, R. [CEA, 75 - Paris (France); Sene, R. [Groupement des Scientifiques pour l' Information sur l' Energie Nucleaire, 91 - Orsay (France); Schmitt, P. [CLS de Fessenheim, 68 (France)

2006-07-01

This colloquium is essentially devoted to the nuclear crisis and its management. As regards the nuclear crisis, it is especially about the behavior of the C.L.I. (local commissions of information) of the communication, the errors to be avoided and possible surprises. Several experiences are reported: the crisis exercise at the nuclear center of electric production (C.N.P.E.) of Saint-Laurent-des-Eaux, the experience of Cogema La hague in communication, transparency and communication for secret installations, the experience of an independent expert from the group of scientists for the information on nuclear (G.S.I.E.N.) and the local commission of information of Fessenheim. (N.C.)

Das Weiblich-Männliche in der saint-simonistischen Debatte um 1830

Directory of Open Access Journals (Sweden)

Paola Ferruta

2009-12-01

Full Text Available D’une part, ma contribution interroge les concepts saint-simoniens de « masculin » et de « féminin » en se basant sur le cas concret de Pierre Leroux, adepte du saintsimonisme dès 1830 à Paris ; d’autre part, elle revient sur la notion d’identité sexuée, ainsi que sur sa variabilité intrinsèque. L’initiative politique et théorétique de Leroux au sein du groupe saint-simonien présente un intérêt historique, car elle a notamment participé à la diffusion au cours du XIXe siècle des croyances en la métempsychose et en des « vérités mystiques ». Ces « vérités mystiques » ont contribué à définir les identités de « genre » dans la pensée de Leroux et à façonner autour de 1840 son concept de « solidarité ». Or la question d’une « politique de la solidarité », et particulièrement de la « solidarité de genre » – c’est-à-dire d’une solidarité féminine qui ne fasse pas du féminisme une politique identitaire – est réactualisée dans le débat contemporainDie saint-simonistischen Begriffe „männlich“ und „weiblich“ sollen hier anhand des Falles von Pierre Leroux, einem Pariser Aktivisten des Saint-Simonismus, betrachtet werden. Es wird u. a. dessen Vorstellung von geschlechtlicher Identität und ihrer inhärenten Variabilität ins Auge gefasst. Die politische und theoretische Initiative Leroux’ ist insofern von historischem Interesse als sie zur Verbreitung des Glaubens an die Metempsychose und an „mystische Wahrheiten“ beitrug. Diese „mystischen Wahrheiten“ steuerten in Leroux’ Denken zur Definition der Geschlechteridentitäten bei und formten um 1840 seinen Begriff von „Solidarität“. Die Frage der „Politik der Solidarität“ ist heute noch aktuell, insbesondere einer „Geschlechtsidentität“, d. h. einer weiblichen Solidarität, die den Feminismus nicht als Identitätspolitik artikuliert.

Declaration of the G8 of Saint Petersburg, the 16 July 2006 on the world energy security

International Nuclear Information System (INIS)

2006-01-01

This document presents in a first part the energy problems which the G8 is confronted with, the response of the international community and the declaration on the principles of the world energy security. The second part is devoted to the action plan of Saint Petersburg, actions in the following domains: reinforcement of the world energy markets transparency and stability, improvement of the investments climate in the energy sector, reinforcement of the energy efficiency and the energy conservation, diversification of the energies resources, security of the vital energy infrastructures, decrease of the energy dearth, fight against the climatic change and help to the sustainable development. (A.L.B.)

Training and research on the nuclear reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

1998-01-01

The VR-1 training reactor is a light water reactor of the pool type using enriched uranium as the fuel. The moderator is demineralized light water, which also serves as the neutron reflector, biological shielding, and coolant. Heat evolved during the fission process is removed by natural convection. The reactor is used in the education of students in the field of reactor and neutron physics, dosimetry, nuclear safety, and instrumentation and control systems for nuclear facilities. Although primarily intended for students in various branches of technology (power engineering, nuclear engineering, physical engineering), this specialized facility is also used by students of faculties educating future natural scientists and teachers. Typical tasks trained at the VR-1 reactor include: measurement of delayed neutrons; examination of the effect of various materials on the reactivity of the reactor; measurement of the neutron flux density by various procedures; measurement of reactivity by various procedures; calibration of reactor control rods by various procedures; approaching the critical state; investigation of nuclear reactor dynamics; start-up, control and operation of a nuclear reactor; and investigation of the effect of a simulated nucleate boil on reactivity. In addition to the education of university-level students, training courses are also organized for specialists in the Czech nuclear programme

THE APOSTLE PAUL: THEOLOGIAN-MISSIONARY AND PASTOR-THEOLOGIAN. TOWARDS A DEEPER UNDERSTANDING OF SAINT PAUL

Directory of Open Access Journals (Sweden)

Eckhart Schnabel

2013-04-01

Full Text Available This Article is an attempt to shed light on a few texts of the acts of the Apostles and of the epistles which are viewed as sources documenting the life and activity of Saint Paul. The author attempts to settle a number of questions regarding the authenticity of sources illustrating the life of Saint Paul. Similar questions are often raised by those who write and publish guides and textbooks for the teaching of the Pauline corpus. The author agrees with the overwhelming positive judgment of the academic world regarding the authenticity of the pastoral epistles, but at the same time he notes a number of objections to their authenticity proposed by the same forum: inconsistencies within the vocabulary of the texts themselves, their linguistic style, and their theological argumentation. The author concludes that these objections are inconclusive and the features enumerated by those who object constitute in reality only minor exceptions, inconsequential when taking into account the entire Pauline corpus. The author also examines the authenticity and historical accuracy of the account of the life of Saint Paul as given in the Acts of the Apostles. A few Biblicists claim that the account in Acts is merely legendary and is to be regarded as a type of early Christian folklore. The author disagrees with this opinion, backing up his position with the evidence that both the Acts of the Apostles and the Pastoral Epistles agree in historical detail and background. The author concludes with a further consideration regarding the correct method guiding biblical research on Saint Paul. He opines that such research must view the biblical texts in a correct historical perspective

Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Appendix B, foreign research reactor spent nuclear fuel characteristics and transportation casks. Volume 2

International Nuclear Information System (INIS)

1995-03-01

This is Appendix B of a draft Environmental Impact Statement (EIS) on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. It discusses relevant characterization and other information of foreign research reactor spent nuclear fuel that could be managed under the proposed action. It also discusses regulations for the transport of radioactive materials and the design of spent fuel casks

Recherche sur les sous-declarations de décés, Saint Marc, Haiti, 2012

Directory of Open Access Journals (Sweden)

Stela Nazareth Meneghel

2014-11-01

Full Text Available Ce travail se réfère à une étude exploratoire menée dans la ville de Saint Marc, une commune d'environ 257,863 habitants en 2012, localisée dans le département d'Artibonite/Haïti. L'objectif est rechercher le flux d'informations concernant le système de mortalité et l'existence de non-déclarations de décès. Les décès survenus dans le mois de janvier 2013 ont fait l'objet d'une enquête dans cinq institutions de la ville de Saint Marc: l'Hôpital Saint Nicolas (HSN, la Mairie, le Bureau d'État Civil (BEC, le Cimetière et la Cathédrale. L'hôpital a été l'institution où l'on a rencontré le plus grand nombre de décès enregistrés. On a procédé au comptage des décès, à partir de la liste nominale des registres hospitaliers, en ajoutant les décè...

Marées et touristes au Mont-Saint-Michel

Directory of Open Access Journals (Sweden)

Fernand Verger

2001-09-01

Full Text Available L’imaginaire collectif fait la plus grande place au phénomène des grandes marées dans la baie du Mont-Saint-Michel, mais la fréquentation touristique n’est que faiblement déterminée par l’occurrence des grandes marées, malgré l’existence d’un public spécifique, relativement peu nombreux, attiré par le spectacle du mascaret.

History of 100-B Area

International Nuclear Information System (INIS)

Wahlen, R.K.

1989-10-01

The initial three production reactors and their support facilities were designated as the 100-B, 100-D, and 100-F areas. In subsequent years, six additional plutonium-producing reactors were constructed and operated at the Hanford Site. Among them was one dual-purpose reactor (100-N) designed to supply steam for the production of electricity as a by-product. Figure 1 pinpoints the location of each of the nine Hanford Site reactors along the Columbia River. This report documents a brief description of the 105-B reactor, support facilities, and significant events that are considered to be of historical interest. 21 figs

Methodology for the assessment of innovative nuclear reactors and fuel cycles. Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2004-12-01

an innovative nuclear energy system (INS) to meet the overall target of sustainable energy supply. As well, the initial development of the INPRO method for the assessment of nuclear energy systems was carried out. The Basic Principles, User Requirements, and Criteria and the INPRO method of assessment, taken together, comprise the INPRO methodology. The INPRO methodology provides the possibility to take into account local, regional and global boundary conditions of IAEA Member States, including those of both developing and developed countries. Phase 1A was completed in June of 2003 with the publication of IAEA-TECDOC-1362, Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles, which documented the results of the Phase 1A work. The next step of INPRO was immediately launched. In this step, referred to as Phase 1B (first part), INPRO arranged for some 14 case studies to be performed, by national teams or by individual experts from seven countries, to test and provide feedback on the applicability, consistency and completeness of the INPRO methodology. This report documents changes to the basic principles, user requirements, criteria and the method of assessment that resulted from the second step of INPRO (referred to as Phase 1B (first part)), which started in June 2003 and ended in December 2004. During this step, Member States and individual experts performed 14 case studies with the objective of testing and validating the INPRO methodology. Based on the feedback from these case studies and numerous consultancies mostly held at the IAEA, the INPRO methodology has been significantly updated and revised, as documented in this report. The ongoing and future activities of INPRO will lead to further modifications to the INPRO methodology, based on the feedback received from Member States in light of their experience in applying the methodology. Thus, additional reports will be issued, as appropriate, to update the INPRO methodology

8 CFR 286.1 - Definitions.

Science.gov (United States)

2010-01-01

..., Marie-Galante, Martinique, Miquelon, Montserrat, Saba, Saint Barthélemy, Saint Christopher, Saint Eustatius, Saint Kitts-Nevis, Saint Lucia, Saint Maarten, Saint Martin, Saint Pierre, Saint Vincent and...

Three saints with deformed extremities in an Italian Renaissance altarpiece.

Science.gov (United States)

Albury, W R; Weisz, G M

2017-03-01

A fifteenth-century Florentine altarpiece painted by the Pollaiuolo brothers, Antonio (1433-1498) and Piero (1443-1496), shows three saints with evident deformities of the hands and feet. The pathologies concerned are tentatively identified, and various rationales for their presence in the painting are discussed. Of particular importance is the location of the altarpiece in a chapel which houses the tomb of the Cardinal of Portugal, Prince James of Lusitania (1433-1459). It is argued that both the artistic style of the day and the religious symbolism of the Cardinal's funeral chapel contributed to the artists' decision to portray the saints with deformities. An unnatural curvature of the fifth finger was apparently considered elegant in fifteenth-century paintings, and the depiction of bare feet with hallux valgus gave them a shape which approximated and could have been caused by fashionable pointed shoes. But in addition, deformities in religious art could be symbolic of suffering and martyrdom, a theme which the Cardinal's chapel emphasised in a number of ways. It is suggested therefore that the Pollaiuolo altarpiece reconciles these two disparate factors, portraying genuine deformities in a way that was artistically stylish and symbolically meaningful.

Chalon/Saint-Marcel manufacturing plant; L'usine de Chalon/Saint-Marcel

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

AREVA is the world leader in the design and construction of nuclear power plants, the manufacture of heavy components, and the supply of nuclear fuel and nuclear services such as maintenance and inspection. The Equipment Division provides the widest range of nuclear components and equipment, manufactured at its two facilities in Jeumont, northern France, and St. Marcel, in Burgundy. The St. Marcel plant, set on 35 ha (87.5 acres) near Chalon-sur-Saone, was established in 1973 in a region with a long history of specialized metalworking and mechanical activities to meet the demand for non-military nuclear requirements in France. The site offers two advantages: - excellent facilities for loading and transporting heavy components on the Saone river, - it's proximity to other group sites. Since its completion in 1975, the Chalon/St. Marcel facility has manufactured all the heavy components for French pressurized water reactors (PWRs) ranging from 900 MW to 1500 MW. It has also completed a significant number of export contracts that have made AREVA world leader. Nearly 600 heavy components (reactor vessels, steam generators, pressurizers and closure heads) have been manufactured or are currently being manufactured since the plant opened in 1975. The plant is at the heart of the manufacturing chain for nuclear steam supply systems (NSSS) supplied by AREVA. On the basis of engineering data, the plant manufactures reactor vessels, reactor vessel internals, steam generators, pressurizers and related components such as accumulators, auxiliary heat exchangers and supporting elements. Vessel upper internals Other similar components such as reactor vessels for boiling water reactors (BWR) or high temperature reactors (HTR) and other types of steam generators can also be manufactured in the plant (for example Once Through Steam Generators - OTSG). The basic activities performed at Chalon/St. Marcel are metalworking and heavy machining. These activities are carried out in

The light water integral reactor with natural circulation of the coolant at supercritical pressure B-500 SKDI

International Nuclear Information System (INIS)

Silin, V.A.; Voznesensky, V.A.; Afrov, A.M.

1993-01-01

Pressure increase in the primary circuit over the critical value gives a possibility to construct the B-500SKDI (500 MWe) lightwater integral reactor with natural circulation of the coolant in the vessel with a diameter less than 5 m. The given reactor has a high safety level, simple operability, its specific capital cost and fuel expenditure being lower as compared to a conventional PWR. The development of the reactor is carried out taking into consideration verified technical decisions of current NPPs on the basis of Russian LWR technology. (orig.)

Thermal and hydraulic characteristics of the JEN-1 Reactor; Caracteristicas hidraulicas y termicas del Reactor JEN-1

Energy Technology Data Exchange (ETDEWEB)

Otra Otra, F; Leira Rey, G

1971-07-01

In this report an analysis is made of the thermal and hydraulic performances of the JEN-1 reactor operating steadily at 3 Mw of thermal power. The analysis is made separately for the core, main heat exchanger and cooling tower. A portion of the report is devoted to predict the performances of these three main components when and if the reactor was going to operate at a power higher than the maximum 3 Mw attainable today. Finally an study is made of the unsteady operation of the reactor, focusing the attention towards the pumping characteristics and the temperatures obtained in the fuel elements. Reference is made to several digital calculation programmes that nave been developed for such purpose. (Author) 21 refs.

IEA-R1 reactor - Spent fuel management

International Nuclear Information System (INIS)

Mattos, J.R.L. De

1996-01-01

Brazil currently has one Swimming Pool Research Reactor (IEA-R1) at the Instituto de Pesquisas Energeticas e Nucleares - Sao Paulo. The spent fuel produced is stored both at the Reactor Pool Storage Compartment and at the Dry Well System. The present situation and future plans for spent fuel storage are described. (author). 3 refs, 2 figs, 2 tabs

Dissolved inorganic carbon, alkalinity, temperature, salinity and other variables collected from discrete sample and profile observations using CTD, bottle and other instruments from the LOUIS S. ST. LAURENT in the Baffin Bay, Davis Strait and others from 1997-08-03 to 1997-08-18 (NODC Accession 0114432)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — NODC Accession 0114432 includes chemical, discrete sample, physical and profile data collected from LOUIS S. ST. LAURENT in the Baffin Bay, Davis Strait, Hudson...

Dissolved inorganic carbon, alkalinity, temperature, salinity and other variables collected from discrete sample and profile observations using CTD, bottle and other instruments from the LOUIS S. ST. LAURENT in the Beaufort Sea and Northwest Passage from 1997-08-31 to 1997-09-16 (NODC Accession 0116061)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — NODC Accession 0116061 includes chemical, discrete sample, physical and profile data collected from LOUIS S. ST. LAURENT in the Beaufort Sea and Northwest Passage...

International Working Group on Fast Reactors Sixth Annual Meeting. Summary Report

International Nuclear Information System (INIS)

1973-01-01

The Agenda of the Meeting was as follows: 1. Review of IWGFR Activities - 1a. Approval of the minutes of the Fifth IWGFR Meeting. 1b. Report by Scientific Secretary regarding the activities of the Group. 2. Comments on National Programmes on Fast Breeder Reactors. 3. International Coordination of the Schedule for Major Fast Reactor Meetings and other major international meetings having a predominant fast reactor interest. 4. Consideration of Conferences on Fast Reactors. 4a. IAEA Symposium on Fuel and Fuel Elements for Fast Reactors, Brussels, Belgium 2-6 July 1973. 4b. International Symposium on Physics of Fast Reactors, Tokyo, Japan, 16 to 23 October 1973. 4c. International Conference on Fast Reactor Power Stations, London, UK, 11 to 14 March 1974 . 4d. Suggestions of the IWGFR members on other conferences. 5. Consideration of a Schedule for Specialists' Meetings in 1973-74. 6. Other Business - 6a. First-aid in Sodium Burns. 6b. Principles of Good Practice for Safe Operation of Sodium Circuits. 6c. Bibliography on Fast Reactors. 7. The Date and Place of the Seventh Annual Meeting of the IWGFR

Le système du risque à Saint-Martin (Petites Antilles françaises

Directory of Open Access Journals (Sweden)

Virginie Duvat

2008-11-01

Full Text Available L’île de Saint-Martin constitue un terrain particulièrement intéressant pour étudier le système du risque naturel et les conditions de la co-évolution territoire/catastrophes. Les mécanismes qui s’y observent renforcent sa vulnérabilité et l’efficacité du retour d’expérience est affaiblie par des blocages d’ordre politique et juridique.The island of Saint-Martin is an interesting case study for a systemic approach applied to cyclone hazards and the co-evolution of territory and disaster management. The mecanisms which can be observed increase its vulnerability and the progress of hazard management policies is weakened by political and juridical bottlenecks.

Compressive strength evolution of thermally-stressed Saint Maximin limestone.

Science.gov (United States)

Farquharson, J.; Griffiths, L.; Baud, P.; Wadsworth, F. B.; Heap, M. J.

2017-12-01

The Saint Maximin quarry (Oise, France) opened in the early 1600s, and its limestone has been used extensively as masonry stone, particularly during the classical era of Parisian architecture from the 17th century onwards. Its widespread use has been due to a combination of its regional availability, its high workability, and its aesthetic appeal. Notable buildings completed using this material include sections of the Place de la Concorde and the Louvre in Paris. More recently, however, it has seen increasing use in the construction of large private residences throughout the United States as well as extensions to private institutions such as Stanford University. For any large building, fire hazard can be a substantial concern, especially in tectonically active areas where catastrophic fires may arise following large-magnitude earthquakes. Typically, house fires burn at temperatures of around 600 °C ( 1000 F). Given the ubiquity of this geomaterial as a building stone, it is important to ascertain the influence of heating on the strength of Saint Maximin limestone (SML), and in turn the structural stability of the buildings it is used in. We performed a series of compressive tests and permeability measurements on samples of SML to determine its strength evolution in response to heating to incrementally higher temperatures. We observe that the uniaxial compressive strength of SML decreases from >12 MPa at room temperature to 400 °C). We anticipate that this substantial weakening is in part a result of thermal microcracking, whereby changes in temperature induce thermal stresses due to a mismatch in thermal expansion between the constituent grains. This mechanism is compounded by the volumetric increase of quartz through its alpha - beta transition at 573 °C, and by the thermal decomposition of calcite. To track the formation of thermal microcracks, we monitor acoustic emissions, a common proxy for microcracking, during the heating of an SML sample. The

Radiological status of the Saint-Pierre (Cantal) uranium mine and of its environment. Volume 1 + volume 2 + volume 3

International Nuclear Information System (INIS)

2006-01-01

The first volume reports detailed investigations performed by the CRIIRAD (sampling and radiological controls of sediments, and more particularly of waters and aquatic plants) in different areas about the Saint-Pierre uranium mine in France (Cantal department). Measurements were performed by gamma spectrometry. The second part concerns external exposure and the radiological characterization of soils. The third part reports the study of the presence of radon in outdoor and indoor air. For each of these aspects, methodological information is given as well as a great quantity of measurement results

TR-EDB: Test Reactor Embrittlement Data Base, Version 1

Energy Technology Data Exchange (ETDEWEB)

Stallmann, F.W.; Wang, J.A.; Kam, F.B.K. [Oak Ridge National Lab., TN (United States)

1994-01-01

The Test Reactor Embrittlement Data Base (TR-EDB) is a collection of results from irradiation in materials test reactors. It complements the Power Reactor Embrittlement Data Base (PR-EDB), whose data are restricted to the results from the analysis of surveillance capsules in commercial power reactors. The rationale behind their restriction was the assumption that the results of test reactor experiments may not be applicable to power reactors and could, therefore, be challenged if such data were included. For this very reason the embrittlement predictions in the Reg. Guide 1.99, Rev. 2, were based exclusively on power reactor data. However, test reactor experiments are able to cover a much wider range of materials and irradiation conditions that are needed to explore more fully a variety of models for the prediction of irradiation embrittlement. These data are also needed for the study of effects of annealing for life extension of reactor pressure vessels that are difficult to obtain from surveillance capsule results.

TR-EDB: Test Reactor Embrittlement Data Base, Version 1

International Nuclear Information System (INIS)

Stallmann, F.W.; Wang, J.A.; Kam, F.B.K.

1994-01-01

The Test Reactor Embrittlement Data Base (TR-EDB) is a collection of results from irradiation in materials test reactors. It complements the Power Reactor Embrittlement Data Base (PR-EDB), whose data are restricted to the results from the analysis of surveillance capsules in commercial power reactors. The rationale behind their restriction was the assumption that the results of test reactor experiments may not be applicable to power reactors and could, therefore, be challenged if such data were included. For this very reason the embrittlement predictions in the Reg. Guide 1.99, Rev. 2, were based exclusively on power reactor data. However, test reactor experiments are able to cover a much wider range of materials and irradiation conditions that are needed to explore more fully a variety of models for the prediction of irradiation embrittlement. These data are also needed for the study of effects of annealing for life extension of reactor pressure vessels that are difficult to obtain from surveillance capsule results

Dissolved inorganic carbon, alkalinity, temperature, salinity and other variables collected from discrete sample and profile observations using CTD, bottle and other instruments from the LOUIS S. ST. LAURENT in the Arctic Ocean and Beaufort Sea from 1997-09-24 to 1997-10-15 (NODC Accession 0113984)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — NODC Accession 0113984 includes chemical, discrete sample, physical and profile data collected from LOUIS S. ST. LAURENT in the Arctic Ocean and Beaufort Sea from...

Modernization and Refurbishment of the RECH-1 Reactor

Energy Technology Data Exchange (ETDEWEB)

Daie, J. [Nuclear Application Department, Chilean Nuclear Energy Commission (CCHEN), Santiago (Chile)

2014-08-15

The Chilean Nuclear Energy Commission (Comisión Chilena de Energía Nuclear, or CCHEN) has operated the RECH-1 research reactor since 1974. This reactor is located at La Reina Nuclear Centre in Santiago, Chile. It is a pool type reactor using LEU MTR fuel assemblies, light water as moderator and coolant, and beryllium as reflector. The reactor has been operated at the nominal power of 5 MW in a continuous shift of 20 hours per week, 48 weeks per year. The main utilizations of the RECH-1 reactor are radioisotope production and neutron activation analysis. Among the most relevant refurbishment and modernization campaigns undertaken at the reactor are: full core conversion to the use of LEU fuel, replacement of the cooling tower, improvement of the containment building by changing the doors and gates and by a better sealant for the penetrations, introduction of an additional source of water by connecting the raw water supply system to the emergency cooling system, improvement of the emergency ventilation system, introduction of a fire detection and alarm system for detection and mitigation to protect the I&C racks, introduction of a radioactive liquid release for those generated at the reactor, introduction of a delay tank degasification system and renewal of the environmental monitoring system. At present we are assessing the possibility of replacing the old analog electronics of control for new digital systems. Detailed descriptions of these diverse activities are presented in the paper. (author)

Latter-Day Saint Women and Leadership: The Influence of Their Religious Worldview

Science.gov (United States)

Madsen, Susan R.

2016-01-01

The article examines theories, assumptions, concepts, experiences, and practices from the Latter-day Saints' (LDS, or the Mormons) religious worldview to expand existing theoretical constructs and implications of leadership development and education for women. The article elucidates LDS doctrine and culture regarding women and provides specific…

Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1; Simulacion de un reactor FBR con geometria hexagonal-Z usando el codigo PARCS 3.1

Energy Technology Data Exchange (ETDEWEB)

Reyes F, M. C.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Filio L, C., E-mail: rf.melisa@gmail.com [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2013-10-15

The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S{sub 2} and P{sub 1}. Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

Extensive utilisation of VR-1 reactor for nuclear education and training

International Nuclear Information System (INIS)

Rataj, J.

2010-01-01

The paper presents utilisation of the VR-1 reactor for nuclear education and training at national and international level. VR-1 reactor has been operating by the Czech Technical University since December 1990. The reactor is a pool-type light water reactor based on enriched uranium (19.7% 235 U) with maximum thermal power 1kW and for short time period up to 5kW. The moderator of neutrons is light water, which is also used as a reflector, a biological shielding and a coolant. Heat is removed from the core by natural convection. The pool disposition of the reactor facilitates access to the core, setting and removing of various experimental samples and detectors, easy and safe handling of fuel assemblies. The reactor core can contain from 17 to 21 fuel assemblies IRT-4M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The reactor is equipped with several experimental devices; e.g. horizontal, radial and tangential channels used to take out a neutron beam, reactivity oscillator for dynamics study and bubble boiling simulator. The reactor has been used very efficiently especially for education and training of university students and NPP's specialists for more than 18 years. The VR-1 reactor is utilised within various national and international activities such as Czech Nuclear Education Network (CENEN), European Nuclear Education Network and also Eastern European Research Reactor Initiative (EERRI). The reactor is well equipped for education and training not only by the experimental facility itself but also by incessant development of training methods and improvement of education experiments. The education experiments can be combined into training courses attended by students according to their study specialization and knowledge level. The training programme is aimed to the reactor and neutron physics, dosimetry, nuclear safety, and control of nuclear installations. Every year, approximately 250 university students undergo

El diario de un escritor en Encuentro en Saint-Nazaire de Ricardo Piglia

Directory of Open Access Journals (Sweden)

Amor Arelis Hernández Peñaloza

2016-01-01

Full Text Available En este artículoestudiamos el género diario íntimo a través de la nouvelleEncuentro en Saint-Nazaire(1988 que contiene el ”Diario de un loco”del escritor ficticio Stephen Stevensen. Este uso ficcional del diario, dentro delmarco de la estructura de la obra literaria adquiere un sentido diferente porque renuncia a la comunicación de algo íntimo y secreto, para convertirse en literatura, en ”comunicación estética”. Asimismopretendemosevidenciar la importancia y la magnitud del género diario en la unidad narrativa de un autor como Ricardo Piglia. Junto a esto, el ejemplo de Encuentro en Saint- Nazairenos ayudará a mostrar las características de este tipo de prosa pigliana, que funciona como un laboratorio de la escritura.

Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option nuclear reactor-borne

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This document describes the specific dispositions relative to the nuclear reactor-borne domain, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the nuclear reactor-borne and of the retraining, the Passerelle formation, are presented. (A.L.B.)

The St-Laurent-des-Eaux nuclear power plant, at the service of a safe, competitive and CO2-free power generation in the heart of the Centre region

International Nuclear Information System (INIS)

2010-01-01

In less than 20 years, Electricite de France (EDF) has built up a competitive park of 58 nuclear power plants, with no equivalent elsewhere, which represents an installed power of 63.1 GW (85% of EDF's power generation). Inside this nuclear park, the national power generation centre of St-Laurent-des-Eaux comprises two production units of 900 MW each (1800 MW as a whole). The facility generated 12.4 billion kWh in 2009, i.e. 2.5% of the French national power generation and 71% of the energy consumed in the Centre region. This brochure presents the life of the power plant under various aspects: power generation, safety priority and culture, maintenance investments, respect of the environment, long-term fuel and wastes management, local economical involvement, transparency and public information, key figures and dates. (J.S.)

Annual report on JEN-1 and JEN-2 Reactors; Informe periodico de Reactores JEN-1 y JEN-2 correpondiente al ano 1972

Energy Technology Data Exchange (ETDEWEB)

Montes Ponce de Leon, J.

1974-07-01

In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

Rotary Bed Reactor for Chemical-Looping Combustion with Carbon Capture. Part 1: Reactor Design and Model Development

KAUST Repository

Zhao, Zhenlong

2013-01-17

Chemical-looping combustion (CLC) is a novel and promising technology for power generation with inherent CO2 capture. Currently, almost all of the research has been focused on developing CLC-based interconnected fluidized-bed reactors. In this two-part series, a new rotary reactor concept for gas-fueled CLC is proposed and analyzed. In part 1, the detailed configuration of the rotary reactor is described. In the reactor, a solid wheel rotates between the fuel and air streams at the reactor inlet and exit. Two purging sectors are used to avoid the mixing between the fuel stream and the air stream. The rotary wheel consists of a large number of channels with copper oxide coated on the inner surface of the channels. The support material is boron nitride, which has high specific heat and thermal conductivity. Gas flows through the reactor at elevated pressure, and it is heated to a high temperature by fuel combustion. Typical design parameters for a thermal capacity of 1 MW have been proposed, and a simplified model is developed to predict the performances of the reactor. The potential drawbacks of the rotary reactor are also discussed. © 2012 American Chemical Society.

[Department of Otorhinolaryngology of the I.P. Pavlov Saint-Peterburg First State Medical University].

Science.gov (United States)

Karpishchenko, S A

This article is designed to report the results of the analysis ofacademic, scientific, and clinical activities of the Department of Otorhinolaryngology of the I.P. Pavlov Saint-Peterburg First State Medical University.

Saint Francis Xavier on Jesuit School Stages of the Bohemian Province

Czech Academy of Sciences Publication Activity Database

Bobková, Kateřina; Jacková, Magdaléna

2015-01-01

Roč. 25, č. 2 (2015), s. 135-155 ISSN 0515-3190 R&D Projects: GA ČR GPP406/12/P823 Institutional support: RVO:68378068 ; RVO:67985963 Keywords : St. Francis Xavier * Jesuit saints * Jesuit theatre * neolatin drama * school theatre * Avancini, Nicolaus * Engel, Arnoldus Subject RIV: AJ - Letters, Mass-media, Audiovision; AB - History (HIU-Y)

The research reactors their contribution to the reactors physics

International Nuclear Information System (INIS)

Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

2000-01-01

The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

Electrical system regulations of the IEA-R1 reactor

International Nuclear Information System (INIS)

Mello, Jose Roberto de; Madi Filho, Tufic

2013-01-01

The IEA-R1 reactor of the Nuclear and Energy Research Institute (IPEN-CNEN/SP), is a research reactor open pool type, designed and built by the U.S. firm Babcock and Wilcox, having, as coolant and moderator, deionized light water and beryllium and graphite, as reflectors. Until about 1988, the reactor safety systems received power from only one source of energy. As an example, it may be cited the control desk that was powered only by the vital electrical system 220V, which, in case the electricity fails, is powered by the generator group: no-break 220V. In the years 1989 and 1990, a reform of the electrical system upgrading to increase the reactor power and, also, to meet the technical standards of the ABNT (Associacao Brasileira de Normas Tecnicas) was carried out. This work has the objective of showing the relationship between the electric power system and the IEA-R1 reactor security. Also, it demonstrates that, should some electrical power interruption occur, during the reactor operation, this occurrence would not start an accident event. (author)

Modernization of control instrumentation and security of reactor IAN - R1

International Nuclear Information System (INIS)

Gonzalez, J. M.

1993-01-01

The program to modernize IAN-R1 research reactor control and safety instrumentation has been carried out considering two main aspects: updating safety philosophy requirements and acquiring the newest reactor control instrumentation controlled by computer, following the present criteria internationally recognized, for safety and reliable reactor operations and the latest developments of nuclear electronic technology. The new IAN-R1 reactor instrumentation consist of two wide range neutron monitoring channels, commanded by microprocessor a data acquisition system and reactor control, (controlled by computers). The reactor control desk is providing through two displays; all safety and control signals to the reactor operators; furthermore some signals like reactor power, safety and period signals are also showed on digital bar graphics, which are hard wired directly from the neutron monitoring channels

Saints' Relics in Scuola di S. Giorgio degli Schiavoni: An Anti-Ottoman Pantheon

Directory of Open Access Journals (Sweden)

Ana Marinković

2018-04-01

Full Text Available The intensified military campaigns against the Ottomans in the second half of the fifteenth century palpably influenced the cult of saints venerated in Scuola di S. Giorgio degli Schiavoni, both by assimilating new saints, as well as strenghtening the existing cults through indulgences and relic acquisitions. The initial pair of patron saints – St George and St Tryphon, the city patrons of Bar and Kotor – delineated the geographical area where the majority of confraternity members originated from, that is, the Venetian Albania. The inclusion of St Jerome, the patron of Dalmatia, to the confraternal pantheon by Cardinal Bessarion's indulgence issued in 1464, in addition to rounding up the holy patronage to all the Eastern Adriatic Venetian dependencies, also marked the beginning of a strong anti-Ottoman motivation in the scuola's hagiographic horizon. The triple endowment of the Scuola in 1502 – relic acquisition, granting of indulgence, and commission of Carpaccio's monumental cycle – continued to work on the same line, and added to the practical aspect of spiritual support to the members of Venetian troops provenient of the Eastern Adriatic. However, the saints whose relics are today kept in the altar of the lower hall, including the patron saint of the Republic of Dubrovnik, point to an even wider devotional agenda, possibly arranged after the Battle of Lepanto, as the comparative analysis of the reliquaries show.   Le campagne militari contro gli Ottomani intensificatesi nella seconda metà del XV secolo influenzarono palesemente il culto dei santi venerati nella Scuola di S. Giorgio degli Schiavoni, sia attraverso l'assimilazione di nuovi santi, sia tramite il rafforzamento del culto già esistente verso le indulgenze e l'impulso all'acquisizione di reliquie. La prima coppia di santi patroni - San Giorgio e San Trifone, patroni della città di Bar e Cattaro - delimitano l'area geografica da cui proviene la maggior parte dei membri

Operation and maintenance of 1MW PUSPATI TRIGA reactor

International Nuclear Information System (INIS)

Adnan Bokhari; Mohammad Suhaimi Kassim

2006-01-01

The Malaysian Research Reactor, Reactor TRIGA PUSPATI (RTP) has been successfully operated for 22 years for various experiments. Since its commissioning in June 1982 until December 2004, the 1MW pool-type reactor has accumulated more than 21143 hours of operation, corresponding to cumulative thermal energy release of about 14083 MW-hours. The reactor is currently in operation and normally operates on demand, which is normally up to 6 hours a day. Presently the reactor core is made up of standard TRIAGA fuel element consists of 8.5 wt%, 12 wt% and 20 wt% types; 20%-enriched and stainless steel clad. Several measures such as routine preventive maintenance and improving the reactor support systems have been taken toward achieving this long successful operation. Besides normal routine utilization like other TRIGA reactors, new strategies are implemented for effective increase in utilization. (author)

Christian Feasts dedicated to Saints – an Interdisciplinary Perspective

Directory of Open Access Journals (Sweden)

Carmen-Maria Bolocan

2012-06-01

Full Text Available Our paper is an interdisciplinary approach, of linguistic and theological analysis of a few lexemes that define saints who became popular in the Romanian culture and spirituality. Our ancient church, a fundamental part of our culture, has always been a coagulant factor for the unity of the Romanians worldwide. And this is also proven by the use of the religious vocabulary in all the anthropological, territorial, socio-professional and socio-cultural variants of the national Romanian language.

Business plan of a food truck in Saint Petersburg

OpenAIRE

Zavyalova, Ekaterina

2017-01-01

The purpose of the thesis was to investigate how to write a proper business plan and then implement gained knowledge in creating a business plan of a food truck in Saint Petersburg. A business plan serves as a guide for an entrepreneur in the process of company establishment and enables to gain funding from potential investors. The primary objective was to study essential components of a business plan. The theoretical framework comprises of core issues on company establishment and desc...

Perspectives on reactor safety. Revision 1

International Nuclear Information System (INIS)

Haskin, F.E.; Hodge, S.A.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Perspectives on reactor safety. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

International Nuclear Information System (INIS)

Eustache, S.

1999-01-01

This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

Enrichment reduction calculations for the DIDO reactor. App. B

International Nuclear Information System (INIS)

Constantine, G.; Javadi, M.; Thick, E.

1985-01-01

The possibility has been raised that DIDO/PLUTO type heavy water moderated reactors can be operated with fuel of lower than the 75% enrichment material currently in use with the object of increasing the proliferation resistance of the fuel cycle. This paper sets out to examine the reactor physics aspects of enrichment reductions to 45% and 20% for Harwell's MTR's as part of an IAEA collaborative exercise currently being conducted to examine the topic in a more general way for the whole class of heavy water moderated reactors. The reactor physics tool used at Harwell is WIMSE, the Winfrith Improved Multigroup Scheme, a suite of linked reactor physics codes which has been used extensively for light water, heavy water and graphite moderated thermal reactors. The course of the calculations and the WIMSE modules involved in this study are described briefly

Annual report on JEN-1 and JEN-2 Reactors

International Nuclear Information System (INIS)

Montes Ponce de Leon, J.

1974-01-01

In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

Advances in Reactor Physics, Mathematics and Computation. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, volume one, are divided into 6 sessions bearing on: - session 1: Advances in computational methods including utilization of parallel processing and vectorization (7 conferences) - session 2: Fast, epithermal, reactor physics, calculation, versus measurements (9 conferences) - session 3: New fast and thermal reactor designs (9 conferences) - session 4: Thermal radiation and charged particles transport (7 conferences) - session 5: Super computers (7 conferences) - session 6: Thermal reactor design, validation and operating experience (8 conferences).

Radiation levels in the poll surface of IEA-R1 reactor

International Nuclear Information System (INIS)

Pasqualetto, H.

1978-01-01

A theoretical model for the calculation of the radioactivity level in the pool surface of the research reactor IEA-RI (INSTITUTO DE ENERGIA ATOMICA, BRAZIL) is developed. The radioactivity is caused by radionuclides (Mainly 24 Na and 27 Mg) produced by nuclear reactions of neutrons with: a) oxygen of the water b); gaseous elements dissolved in water (Ar,N); c) structural materials of the fuel can. Considerations about expected radiation level after eventual increase of reactor power from 2 MW to 10 MW are also presented [pt

Dissolved inorganic carbon, alkalinity, temperature, salinity and other variables collected from discrete sample and profile observations using CTD, bottle and other instruments from the LOUIS S. ST. LAURENT in the Arctic Ocean, Beaufort Sea and North Greenland Sea from 1994-07-24 to 1994-09-01 (NODC Accession 0113983)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — NODC Accession 0113983 includes chemical, discrete sample, physical and profile data collected from LOUIS S. ST. LAURENT in the Arctic Ocean, Beaufort Sea and North...

Nuclear safety and radiation protection report of the Saint-Laurent-Des-Eaux nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 46, 74 and 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures carried out in 2012. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process) as well as the other pollutions. The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of the Saint-Laurent-Des-Eaux nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 46, 74 and 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures carried out in 2013. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process) as well as the other pollutions. The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Saint-Laurent-Des-Eaux nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 46, 74 and 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures carried out in 2014. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process) as well as the other pollutions. The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Reactor utilization, Part 1

International Nuclear Information System (INIS)

Martinc, R.; Stanic, A.

1981-01-01

The reactor operating plan for 1981 was subject to the needs of testing operation with the 80% enriched fuel and was fulfilled on the whole. This annex includes data about reactor operation, review of shorter interruptions due to demands of the experiments, data about safety shutdowns caused by power cuts. Period of operation at low power levels was used mostly for activation analyses, and the operation at higher power levels were used for testing and regular isotope production. Detailed data about samples activation are included as well as utilization of the reactor as neutron source and the operating plan for 1982 [sr

Nuclear power plant reliability database management

International Nuclear Information System (INIS)

Meslin, Th.; Aufort, P.

1996-04-01

In the framework of the development of a probabilistic safety project on site (notion of living PSA), Saint Laurent des Eaux NPP implements a specific EDF reliability database. The main goals of this project at Saint Laurent des Eaux are: to expand risk analysis and to constitute an effective local basis of thinking about operating safety by requiring the participation of all departments of a power plant: analysis of all potential operating transients, unavailability consequences... that means to go further than a simple culture of applying operating rules; to involve nuclear power plant operators in experience feedback and its analysis, especially by following up behaviour of components and of safety functions; to allow plant safety managers to outline their decisions facing safety authorities for notwithstanding, preventive maintenance programme, operating incident evaluation. To hit these goals requires feedback data, tools, techniques and development of skills. The first step is to obtain specific reliability data on the site. Raw data come from plant maintenance management system which processes all maintenance activities and keeps in memory all the records of component failures and maintenance activities. Plant specific reliability data are estimated with a Bayesian model which combines these validated raw data with corporate generic data. This approach allow to provide reliability data for main components modelled in PSA, to check the consistency of the maintenance program (RCM), to verify hypothesis made at the design about component reliability. A number of studies, related to components reliability as well as decision making process of specific incident risk evaluation have been carried out. This paper provides also an overview of the process management set up on site from raw database to specific reliability database in compliance with established corporate objectives. (authors). 4 figs

Nuclear power plant reliability database management

Energy Technology Data Exchange (ETDEWEB)

Meslin, Th [Electricite de France (EDF), 41 - Saint-Laurent-des-Eaux (France); Aufort, P

1996-04-01

In the framework of the development of a probabilistic safety project on site (notion of living PSA), Saint Laurent des Eaux NPP implements a specific EDF reliability database. The main goals of this project at Saint Laurent des Eaux are: to expand risk analysis and to constitute an effective local basis of thinking about operating safety by requiring the participation of all departments of a power plant: analysis of all potential operating transients, unavailability consequences... that means to go further than a simple culture of applying operating rules; to involve nuclear power plant operators in experience feedback and its analysis, especially by following up behaviour of components and of safety functions; to allow plant safety managers to outline their decisions facing safety authorities for notwithstanding, preventive maintenance programme, operating incident evaluation. To hit these goals requires feedback data, tools, techniques and development of skills. The first step is to obtain specific reliability data on the site. Raw data come from plant maintenance management system which processes all maintenance activities and keeps in memory all the records of component failures and maintenance activities. Plant specific reliability data are estimated with a Bayesian model which combines these validated raw data with corporate generic data. This approach allow to provide reliability data for main components modelled in PSA, to check the consistency of the maintenance program (RCM), to verify hypothesis made at the design about component reliability. A number of studies, related to components reliability as well as decision making process of specific incident risk evaluation have been carried out. This paper provides also an overview of the process management set up on site from raw database to specific reliability database in compliance with established corporate objectives. (authors). 4 figs.

Prevalence of overweight, obesity and underweight among 5-year-old children in Saint Lucia by three methods of classification and a comparison with historical rates.

Science.gov (United States)

Gardner, K; Bird, J; Canning, P M; Frizzell, L M; Smith, L M

2011-01-01

The study aimed to determine if child obesity rates have risen in the Caribbean nation of Saint Lucia, as found globally, and whether under-nutrition coexists, as in other developing nations. The average adult in Saint Lucia is overweight, thus considerable child obesity might be expected, but there are no current data. Heights and weights were obtained from a sample (n= 425) of the 2001 birth cohort of Saint Lucian children measured during the nation-wide 2006/2007 Prior to School Entry Five-Year Assessment. Prevalence of overweight, obesity and underweight were estimated by Centers for Disease Control (CDC), Cole et al. and new World Health Organization (WHO) methods. Previously reported 1976 estimates, including children ≤60 months of age only, based on National Centre for Health Statistics curves, were adjusted to new WHO equivalents using an algorithm developed by Yang and de Onis, and compared with rates in our subsample of children ≤60 months of age (n= 99). Regardless of classification method, overweight and obesity rates were high: 14.4% and 9.2% (WHO); 11.3% and 12.0% (CDC); and 9.9% and 7.1% (Cole et al.), respectively. Underweight estimates also varied: 4.7% (WHO); 11.3% (CDC) and 6.6% (Cole et al.). Obesity in our young subsample (15.2%; WHO) was more than 3 times the adjusted 1976 rate (4.3%). Obesity among Saint Lucian pre-schoolers has tripled in 30 years. Our findings also suggest that this country, like many undergoing a 'nutrition transition', faces the dual challenge of over-nutrition and under-nutrition. Routine monitoring of overweight and underweight is needed in Saint Lucia, as is the implementation and evaluation of programmes to address these problems. © 2010 Blackwell Publishing Ltd.

Refurbishment of Pakistan research reactor (PARR-1) for stainless steel lining of the reactor pool

International Nuclear Information System (INIS)

Salahuddin, A.; Israr, M.; Hussain, M.

2002-01-01

Pakistan Research Reactor-1 (PARR-1) is a pool-type research reactor. Reactor aging has resulted in the increase of water seepage from the concrete walls of the reactor pool. To stop the seepage, it was decided to augment the existing pool walls with an inner lining of stainless steel. This could be achieved only if the pool walls could be accessed unhindered and without excessive radiation doses. For this purpose a partial decommissioning was done by removing all active core components including standard/control fuel elements, reflector elements, beam tubes, thermal shield, core support structure, grid plate and the pool's ceramic tiles, etc. An overall decommissioning program was devised which included procedures specific to each item. This led to the development of a fuel transport cask for transportation, and an interim fuel storage bay for temporary storage of fuel elements (until final disposal). The safety of workers and the environment was ensured by the use of specially designed remote handling tools, appropriate shielding and pre-planned exposure reduction procedures based on the ALARA principle. During the implementation of this program, liquid and solid wastes generated were legally disposed of. It is felt that the experience gained during the refurbishment of PARR-1 to install the stainless steel liner will prove useful and better planning and execution for the future decommissioning of PARR-1, in particular, and for other research reactors like PARR-2 (27 kW MNSR), in general. Furthermore, due to the worldwide activities on decommissioning, especially those communicated through the IAEA CRP on 'Decommissioning Techniques for Research Reactors', the importance of early planning has been well recognized. This has made possible the implementation of some early steps like better record keeping, rehiring of trained manpower, and creation of interim and final waste storage. (author)

Enhancing the IT Infrastructure at Saint Philip's Hospital: Point-of-Care Solutions

Science.gov (United States)

Naydenova, Iva; White, Bruce

2013-01-01

Healthcare has become a rapidly changing field. With the introduction of value-based purchasing to determine reimbursement of Medicare providers based on the quality of care in addition to outcomes in treatment, the environment is becoming ever more competitive. Saint Philip's Hospital is among the largest non-profit hospitals in the nation…

RA research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1985

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Badrljica, R.; Majstorovic, D.; Sanovic, V.

1985-01-01

According to the plan, RA reactor was to be in operation in mid September 1985. But, since the building of the emergency cooling system, nor the reconstruction of the existing special ventilation system were not finished until the end of August reactor was not operated during 1985. During the previous four years reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care, which was cancelled in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981-1984. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks have started: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. IAEA has approved the amount of 1,300,000 US dollars for the renewal of the instrumentation [sr

New instrumentation for the IPR-R1 reactor of CDTN

International Nuclear Information System (INIS)

Carvalho, P.V.R. de.

1992-01-01

The Nuclear Engineering Institute reactor instrumentation area has developed systems and equipment for reactor operation and safety. In such way, the new I and C for IEN Argonauta reactor and the nuclear instrumentation for IPEN critical facility were built. This paper describes our real work, the new I and C systems for IPR-R1, a Triga type reactor, located at CDTN (Belo Horizonte - MG). (author)

Neutron flux measurement and thermal power calibration of the IAN-R1 TRIGA reactor

Energy Technology Data Exchange (ETDEWEB)

Sarta Fuentes, Jose A.; Castiblanco Bohorquez, Luis A

2008-10-29

The IAN-R1 TRIGA reactor in Colombia was initially fueled with MTR-HEU enriched to 93% U-235, operated since 1965 at 10 kW, and was upgraded to 30 kW in 1980. General Atomics achieved in 1997 the conversion of HEU fuel to LEU fuel TRIGA type, and upgraded the reactor power to 100 kW. Since the IAN-R1 TRIGA reactor was in an extended shutdown during seven years, it was necessary to repeat some results of the commissioning test conducted in 1997. The thermal power calibration was carried out using the calorimetric method. The reactor was operated approximately at 20 kW during 3.5 hours, with manual power corrections since the automatic control system failed and with the forced refrigeration off. During the calorimetric experiment, the pool temperature was measured with a RTD which is installed near to the core. The dates were collected in intervals of 30 minutes. For establishing thermal power reactor, the water temperature versus the running were registered. For a calculated tank volume of 16 m{sup 3}, the tank constant calculated for the IAN-R1 TRIGA reactor is 0.0539 C/kW-hr. The reactor power determined was 19 kW. The core configuration is a rectangular grid plate that holds a combination of 4-rod and 3-rod clusters. The core contains 50 fuel rods with LEU fuel TRIGA (UZr H1.6) type enriched to 19.7%. The radial reflector consists of twenty graphite elements six of which are used for isotope production. The top an bottom reflectors are the cylindrical graphite end reflectors which are installed above and below of the active fuel section in each fuel rod. The spatial dependence of thermal neutron flux was measured axially in the 3-rod clusters 4C, 3D, 5E and in the 4F graphite element. The spatial distribution of the thermal neutron was determined using a self-powered detector and the absolute value of thermal neutron flux was determined by a gold activation detector. The (n, b- ) reaction is applied to determine the relative spatial distribution of thermal

Neutronic characteristics of linear-assembly breed-and-burn reactors

International Nuclear Information System (INIS)

Petroski, Robert; Forget, Benoit; Forsberg, Charles

2012-01-01

Highlights: ► Simple models used to characterize general behavior of linear-assembly B and B reactors. ► Diffusion theory model developed to explain axial distributions, height vs. reactivity. ► Neutron excess concept reformulated to include linear-assembly B and B reactors. ► Designed model of B and B reactor started using melt-refined B and B reactor used fuel. ► Computed doubling time of fuel cycle requiring no chemical separations. - Abstract: Linear-assembly breed-and-burn (B and B) reactors are B and B reactors that use axially connected assemblies similar to conventional LWR or fast reactor fuel assemblies. Methods for analyzing linear-assembly B and B reactors and their fuel cycles are developed and applied. General neutronic characteristics of linear-assembly B and B reactors are analyzed, including the effects that burnup, shuffling sequence, and radial and axial size have on equilibrium-cycle k-effective. The mechanisms that give rise to a highly peaked axial burnup distribution are explained, and a method for predicting peak burnup vs. k-effective based on infinite-medium depletion calculations is developed. Next, the neutron excess concept from previous studies of B and B reactors is extended to apply to linear-assembly B and B reactors, which allows the amount of starter fuel needed to establish a given equilibrium cycle to be calculated. Several example applications of the neutron excess formulation are given. First, an example model of a linear-assembly B and B reactor is analyzed to find the neutron excess cost of an equilibrium cycle. Second, simple one-dimensional models are used to predict the neutron excess value obtainable from different starter fuel configurations. Finally, these ideas are applied to design a fuel cycle consisting of linear-assembly B and B reactors and fuel recycling via a melt refining process. The neutron excess concept is used to design an appropriate starter fuel configuration made from melt refined fuel, which

Fusion reactor physics and technology. Progress report, October 1, 1978-June 30, 1979

International Nuclear Information System (INIS)

Conn, R.W.; Kulcinski, G.L.; Maynard, C.W.

1979-01-01

During the present contract period, work has been carried out in the following areas: (a) The NUWMAK tokamak reactor design was completed and distributed throughout the community. In particular, specific work was completed on divertorless tokamak operation in NUWMAK, Ti alloy assessment, materials resource implications of NUWMAK style reactors, and an economic analysis; (b) Tandem mirror reactor technology studies were carried out on tandem mirror physics, the role of rf heating, power balance studies, the design of high field magnets, and blanket/shield design in TMR's; (c) work at Wisconsin is contributing to the evolving picture of an optimum TMR; (d) the WHIST tokamak reactor plasma transport code developed at Wisconsin has been extended in two directions; (e) Work on ICRF heating in tokamak reactors, both in terms of physics and launching structure design, has been completed and published

MELOX fuel fabrication plant: Operational feedback and future prospects

International Nuclear Information System (INIS)

Hugelmann, D.; Greneche, D.

2000-01-01

As of December 1, 1998, 32 Europeans LWRs are loaded with MOX fuel. It clearly means that plutonium recycling in MOX fuels is a mature industry, with successful operational experience in fabrication plants in some European countries, especially in France. Indeed, the recycling of plutonium generated in LWRs is one of the objectives of the full Reprocessing-Conditioning-Recycling (RCR) strategy chosen by France in the 70's. The most impressive results of this strategy, is the fact that 31 of the 32 reactors are loaded with MOX fuels supplied by the COGEMA Group from the same efficient fabrication process, the MIMAS process, improved for the MELOX plant to become the A-MIMAS process. In France, 17 reactors are already loaded and 11 additional reactors are technically suited to do so. Indeed, the EDF MOX program plans to use MOX in 28 of its 57 reactors. An EDF 900 MWe reactor core contains 157 assemblies of 264 rods each. 52 fuel assemblies per year are necessary for a 'UO 2 3-batches-MOX 3-batches' core management. In this case, a third of the UO 2 and a third of the MOX assemblies are replaced yearly, that means 36 UO 2 fuel assemblies and 16 MOX fuel assemblies. Some MOX fuelled reactors have now switched from the previously described core management to a so-called 'hybrid core management'. In this case, a quarter of UO 2 assemblies is replaced yearly. The first EDF reactor loaded with MOX fuel was Saint-Laurent B1, in 1987. The in-core experience, based on several hundred assemblies loaded, with reloading on a 1/3 cycle basis, shows that there is no operational difference between UO 2 and MOX fuels, both in terms of performance and safety. MOX fueling of 900 MWe EDF's PWRs, with a limited in-core MOX ratio of 30%, has needed only minor adaptations, such as addition of control rods, modification of the boron concentration in the cooling system and precaution against radiation exposure, easy to set up (optimisation of the fresh MOX fuel handling process, remote

Dos lienzos firmados por Alonso del Arco en la parisina iglesia Saint-François de Sales

Directory of Open Access Journals (Sweden)

Delenda, Odile

2004-09-01

Full Text Available El inventario detallado realizado en las iglesias de París por los conservadores des Oeuvres d'Art Religieuses et Civiles del ayuntamiento de la capital francesa, puede reservar gratas sorpresas. Muy recientemente Guénola Groud, conservateur du Patrimoine y su equipo, pudieron localizar en la «Salle des mariages» de la nueva iglesia de Saint-François-de-Sales (Paris, XVIIème dos importantes lienzos de medio punto, la Adoración de los Pastores (Fig. 2 y la Adoración de los Magos (Fig. 1 firmados por el pintor Alonso del Arco (1635-1704 colaborador y discípulo de Antonio Pereda. Existen en efecto dos iglesias Saint-François-de-Sales. La más antigua, de 1873, está situada en la calle Brémontier mientras que la más reciente, construida entre 1911 y 1913, tiene su entrada principal en la calle Ampère…

An extended conventional fuel cycle for the B and W mPower{sup TM} small modular nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Scarangella, M. J. [Babcock and Wilcox Company, 109 Ramsey Place, Lynchburg, VA 24502 (United States)

2012-07-01

The B and W mPower{sup TM} reactor is a small pressurized water reactor (PWR) with an integral once-through steam generator and a thermal output of about 500 MW; it is intended to replace aging fossil power plants of similar output. The core is composed of 69 reduced-height PWR assemblies with the familiar 17 x 17 fuel rod array. The Babcock and Wilcox Company (B and W) is offering a core loading and cycle management plan for a four-year cycle based on its presumed attractiveness to potential customers. This option is a once-through fuel cycle in which the entire core is discharged and replaced after four years. In addition, a conventional fuel utilization strategy, employing a periodic partial reload and shuffle, was developed as an alternative to the four-year once-through fuel cycle. This study, which was performed using the Studsvik core design code suite, is a typical multi-cycle projection analysis of the type performed by most fuel management organizations such as fuel vendors and utilities. In the industry, the results of such projections are used by the financial arms of these organizations to assist in making long-term decisions. In the case of the B and W mPower reactor, this analysis demonstrates flexibility for customers who consider the once-through fuel cycle unacceptable from a fuel utilization standpoint. As expected, when compared to the once-through concept, reloads of the B and W mPower reactor will achieve higher batch average discharge exposure, will have adequate shut-down margin, and will have a relatively flat hot excess reactivity trend at the expense of slightly increased peaking. (authors)

WWER-440 type reactor core

International Nuclear Information System (INIS)

Mizov, J.; Svec, P.; Rajci, T.

1987-01-01

Assemblies with patly spent fuel of enrichment within 5 and 36 MWd/kg U or lower than the maximum enrichment of freshly charged fuel are placed in at least one of the peripheral positions of each hexagonal sector of the WWER-440 reactor type core. This increases fuel availability and reduces the integral neutron dose to the reactor vessel. The duration is extended of the reactor campaign and/or the mean fuel enrichment necessary for the required duration of the period between refuellings is reduced. Thus, fuel costs are reduced by 1 up to 3%. The results obtained in the experiment are tabulated. (J.B.). 1 fig., 3 tabs

The results of virological surveillance for intrauterine infections in Saint-Petersburg

Directory of Open Access Journals (Sweden)

E. A. Murina

2014-01-01

Full Text Available The purpose of researchis the determiningthe etiological structure ofintrauterine infections in Saint-Petersburg pediatric patients, pregnant women andinfants born to them using a variety of virological methods.Methods: serum from 164 children aged from 1 month to 14 years with diagnosis of «intrauterine infection». Serum from 80 pregnant women, collected in each trimester (total – 240 samples, their 42 children (at the age of 1–2 and 4–6  months of life, total – 82 samples. Immunoglobulin Mand G (IgM and IgGto herpes virus type 1, cytomegalovirus (CMV, Toxoplasma gondii, mycoplasma and chlamydia, rubella, Epstein-Barr virus (EBV and parvovirus B19, as well as IgG avidity,were determined by ELISA in all these samples. Theimmunoblot (Western blot, using the «Immunoblot2000» with test kits from «Euroimmun AG» (Germany, was applied to confirm cases. Statistical analysis wasperformed with theprograms Microsoft Excel, Statistica6.Results: cytomegalovirus, herpes virus 1st type and Epstein-Barr virus infections are dominate in the structure of intrauterine ones (45%, 23% and 14%, respectively. Laboratory evidence ofreactivationof cytomegalovirus (35% ofpregnant womenin the 2nd and/or 3rd trimesters and acuteparvovirus infection (15% of cases were found. Specific IgM to cytomegalovirus were detected in 6,2% ofchildren in the firstsix months of life.Conclusions: with the aim of early detection of cytomegalovirus reactivation and acute parvovirus infection it isnecessary to monitor pregnant women with the definition of specific IgM, IgG and avidity IgG. The procedure to using immunoblotting in the diagnosis of intrauterine infectionsneeds to be further study.

Major update of Safety Analysis Report for Thai Research Reactor-1/Modification 1

Energy Technology Data Exchange (ETDEWEB)

Tippayakul, Chanatip [Thailand Institute of Nuclear Technology, Bangkok (Thailand)

2013-07-01

Thai Research Reactor-1/Modification 1 (TRR-1/M1) was converted from a Material Testing Reactor in 1975 and it had been operated by Office of Atom for Peace (OAP) since 1977 until 2007. During the period, Office of Atom for Peace had two duties for the reactor, that is, to operate and to regulate the reactor. However, in 2007, there was governmental office reformation which resulted in the separation of the reactor operating organization from the regulatory body in order to comply with international standard. The new organization is called Thailand Institute of Nuclear Technology (TINT) which has the mission to promote peaceful utilization of nuclear technology while OAP remains essentially the regulatory body. After the separation, a new ministerial regulation was enforced reflecting a new licensing scheme in which TINT has to apply for a license to operate the reactor. The safety analysis report (SAR) shall be submitted as part of the license application. The ministerial regulation stipulates the outlines of the SAR almost equivalent to IAEA standard 35-G1. Comparing to the IAEA 35-G1 standard, there were several incomplete and missing chapters in the original SAR of TRR1/M1. The major update of the SAR was therefore conducted and took approximately one year. The update work included detail safety evaluation of core configuration which used two fuel element types, the classification of systems, structures and components (SSC), the compilation of detail descriptions of all SSCs and the review and evaluation of radiation protection program, emergency plan and emergency procedure. Additionally, the code of conduct and operating limits and conditions were revised and finalized in this work. A lot of new information was added to the SAR as well, for example, the description of commissioning program, information on environmental impact assessment, decommissioning program, quality assurance program and etc. Due to the complexity of this work, extensive knowledge was

Ecole d’été de probabilités de Saint-Flour XXXII

CERN Document Server

2004-01-01

This is yet another indispensable volume for all probabilists and collectors of the Saint-Flour series, and is also of great interest for mathematical physicists. It contains two of the three lecture courses given at the 32nd Probability Summer School in Saint-Flour (July 7-24, 2002). Boris Tsirelson's lectures introduce the notion of nonclassical noise produced by very nonlinear functions of many independent random variables, for instance singular stochastic flows or oriented percolation. Two examples are examined (noise made by a Poisson snake, the Brownian web). A new framework for the scaling limit is proposed, as well as old and new results about noises, stability, and spectral measures. Wendelin Werner's contribution gives a survey of results on conformal invariance, scaling limits and properties of some two-dimensional random curves. It provides a definition and properties of the Schramm-Loewner evolutions, computations (probabilities, critical exponents), the relation with critical exponents of planar...

Reactor building

International Nuclear Information System (INIS)

Ebata, Sakae.

1990-01-01

At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

Fracture assessment of the Oskarshamn 1 reactor pressure vessel under cold over-pressurization

International Nuclear Information System (INIS)

Sattari-Far, I.

2001-03-01

The major motivation of this study was to develop a methodology for fracture assessment of surface defects in the 01 reactor pressure vessel under cold loading scenarios, particularly the cold over-pressurization event. According to a previous study, the FENIX project, the cold over-pressurization of the O1 reactor is a limiting loading case, as the ductile/brittle transition temperature (RT NDT ) of certain welds in the O1 beltline region may be over 100 deg C at the-end-of-life condition. The FENIX project gave values of the acceptable and critical crack depth to be equal to the thickness of the cladding layer (about 6 mm) under this load case using the ASME K Ic reference curve methodology. This study is aimed to develop a methodology to give a more precise fracture assessment of the O1 reactor under cold loading scenarios. Some of the main objectives of this study have been as below: To prepare a material which can simulate the mechanical properties and RT NDT of the O1 reactor at the end-of-life conditions. To conduct a fracture mechanics test program to cover the essential influencing factors, such as crack geometry (shallow and deep cracks) and loading condition (uniaxial and biaxial) on the cleavage fracture toughness. To perform fracture mechanics analyses to identify a suitable methodology for assessment of the experimental results. To study the responses of engineering fracture assessment methods to the experimental results from the clad specimens. To propose a fracture assessment procedure for determination of the acceptable and critical flaw sizes in the 01 reactor under the cold loading events. A test program consisted of experiments on standard SEN(B) specimens and clad beams, containing surface cracks was conducted during the course of this project. A total of nine clad beams and clad cruciform specimens were tested under uniaxial and biaxial loading. The test material is reactor steel of type A 508 Grade B, which is specially heat-treated to

Thermal hydraulic analysis of the IPR-R1 TRIGA reactor

International Nuclear Information System (INIS)

Veloso, Marcelo Antonio; Fortini, Maria Auxiliadora

2002-01-01

The subchannel approach, normally employed for the analysis of power reactor cores that work under forced convection, have been used for the thermal hydraulic evaluation of a TRIGA Mark I reactor, named IPR-R1, at 250 kW power level. This was accomplished by using the PANTERA-1P subchannel code, which has been conveniently adapted to the characteristics of natural convection of TRIGA reactors. The analysis of results indicates that the steady state operation of IPR-R1 at 250 kW do not imply risks to installations, workers and public. (author)

Fission product monitoring of TRISO coated fuel for the advanced gas reactor-1 experiment

International Nuclear Information System (INIS)

Scates, Dawn M.; Hartwell, John K.; Walter, John B.; Drigert, Mark W.; Harp, Jason M.

2010-01-01

The US Department of Energy has embarked on a series of tests of TRISO coated particle reactor fuel intended for use in the Very High Temperature Reactor (VHTR) as part of the Advanced Gas Reactor (AGR) program. The AGR-1 TRISO fuel experiment, currently underway, is the first in a series of eight fuel tests planned for irradiation in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The AGR-1 experiment reached a peak compact averaged burnup of 9% FIMA with no known TRISO fuel particle failures in March 2008. The burnup goal for the majority of the fuel compacts is to have a compact averaged burnup greater than 18% FIMA and a minimum compact averaged burnup of 14% FIMA. At the INL the TRISO fuel in the AGR-1 experiment is closely monitored while it is being irradiated in the ATR. The effluent monitoring system used for the AGR-1 fuel is the Fission Product Monitoring System (FPMS). The FPMS is a valuable tool that provides near real-time data indicative of the AGR-1 test fuel performance and incorporates both high-purity germanium (HPGe) gamma-ray spectrometers and sodium iodide [NaI(Tl)] scintillation detector-based gross radiation monitors. To quantify the fuel performance, release-to-birth ratios (R/B's) of radioactive fission gases are computed. The gamma-ray spectra acquired by the AGR-1 FPMS are analyzed and used to determine the released activities of specific fission gases, while a dedicated detector provides near-real time count rate information. Isotopic build up and depletion calculations provide the associated isotopic birth rates. This paper highlights the features of the FPMS, encompassing the equipment, methods and measures that enable the calculation of the release-to-birth ratios. Some preliminary results from the AGR-1 experiment are also presented.

Research and development of a super fast reactor (12). Considerations for the reactor characteristics

International Nuclear Information System (INIS)

Goto, Shoji; Ishiwatari, Yuki; Oka, Yoshiaki

2008-01-01

A research program aimed at developing the Super Fast Reactor (Super FR) has been entrusted by the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan since December 2005. It includes the following three projects. (A) Development of the Super Fast Reactor concept. (B)Thermal-hydraulic experiments. (C) Materials development. Tokyo Electric Power Company (TEPCO) has joined this program and works on part (A) together with the University of Tokyo. From the utility's viewpoint, it is important to consider the most desirable characteristics for Super FR to have. Four issues were identified in project (A), (1) Fuel design, (2) Reactor core design, (3) Safety, and (4) Plant characteristics of Super FR. This report describes the desired characteristics of Super FR with respect to item (1) fuel design and item (2) Reactor core design, as compared with a boiling water reactor (BWR) plant. The other two issues will be discussed in this project, and will also be considered in the design process of Super FR. (author)

New human machine interface for VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Sklenka, L.; Chab, V.

2002-01-01

The contribution describes a new human machine interface that was installed at the VR-1 training reactor. The human machine interface update was completed in the summer 2001. The human machine interface enables to operate the training reactor. The interface was designed with respect to functional, ergonomic and aesthetic requirements. The interface is based on a personal computer equipped with two displays. One display enables alphanumeric communication between a reactor operator and the control and safety system of the nuclear reactor. Messages appear from the control system, the operator can write commands and send them there. The second display is a graphical one. It is possible to represent there the status of the reactor, principle parameters (as power, period), control rods' positions, the course of the reactor power. Furthermore, it is possible to set parameters, to show the active core configuration, to perform reactivity calculations, etc. The software for the new human machine interface was produced in the InTouch developing environment of the WonderWare Company. It is possible to switch the language of the interface between Czech and English because of many foreign students and visitors at the reactor. The former operator's desk was completely removed and superseded with a new one. Besides of the computer and the two displays, there are control buttons, indicators and individual numerical displays of instrumentation there. Utilised components guarantee high quality of the new equipment. Microcomputer based communication units with proper software were developed to connect the contemporary control and safety system with the personal computer of the human machine interface and the individual displays. New human machine interface at the VR-1 training reactor improves the safety and comfort of the reactor utilisation, facilitates experiments and training, and provides better support of foreign visitors.(author)

[The embroidery work of the lady at Saint-Anne Hospital].

Science.gov (United States)

Thillaud, Pierre L; Postel, Jacques

2014-01-01

In July 1974, a 72 old woman had been a patient for forty years in Sainte-Anne Hospital, Ward C. As she had again a violent brawl with her neighbour patient, she revealed being a tremendous artist. She had been confined on account of dementia paralytica in the Mecca of malariotherapy, and passionately devoted herself to embroidery. Her fancy work was rather a matter for Jean Dubuffet's art through its perfect expression and deserved being known.

L’entre-soi élitaire à Saint-Barthélemy

NARCIS (Netherlands)

Cousin, B.; Chauvin, S.

2012-01-01

Après un siècle de dénuement, l’île antillaise de Saint-Barthélemy a connu un développement continu depuis sa « découverte » par la grande bourgeoisie américaine à la fin des années 1950. Centrées autour de la villégiature de luxe, les activités économiques de l’île ont nécessité le recours

Reactor Engineering Department annual report (April 1, 1987 - March 31, 1988)

International Nuclear Information System (INIS)

1988-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1987 (April 1, 1987 - March 31, 1988). The major activities in the Department concerns the programs of the high temperature gas-cooled reactor, the high conversion light water reactor, the advanced fission reactor system and the fusion reactor at JAERI and the fast breeder reactor at PNC. The report contains the latest progress in nuclear data and group constants, theoretical methods and code development, reactor physics experiments and analyses, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control/diagnosis and robotics, as well as the new topics from this fiscal year on advanced reactors system design studies and technique developments related the facilities in the Department. Also described are the activities of the Research Committee on Reactor Physics. (author)

Historical basis of the Miracula of Saint Symeon in Stefan the First-Crowned’s life of Symeon

Directory of Open Access Journals (Sweden)

Komatina Ivana

2014-01-01

Full Text Available The paper is devoted to the research of the so-called Catalog of Miracles in the Life of Saint Symeon by Stefan the First-Crowned. Because the miracles are divided in the Life into those in which Symeon-Nemanja is revealed as a Saint, and those in which his heir Stefan the First-Crowned conquers the enemies of the Serbian State with his help, the attention is paid on research of their historical basis and chronological frame, as well as their religious essence. [Projekat Ministarstva nauke Republike Srbije, br. 177029: Srednjovekovne srpske zemlje (13-15. vek: politički, privredni, društveni i pravni procesi

Prospect of realizing nuclear fusion reactors

International Nuclear Information System (INIS)

1989-01-01

This Report describes the results of the research work on nuclear fusion, which CRIEPI has carried out for about ten years from the standpoint of electric power utilities, potential user of its energy. The principal points are; (a) economic analysis (calculation of costs) based on Japanese analysis procedures and database of commercial fusion reactors, including fusion-fission hybrid reactors, and (b) conceptual design of two types of hybrid reactors, that is, fission-fuel producing DMHR (Demonstration Molten-Salt Hybrid Reactor) and electric-power producing THPR (Tokamak Hybrid Power Reactor). The Report consists of the following chapters: 1. Introduction. 2. Conceptual Design of Hybrid Reactors. 3. Economic Analysis of Commercial Fusion Reactors. 4. Basic Studies Applicable Also to Nuclear Fusion Technology. 5. List of Published Reports and Papers; 6. Conclusion. Appendices. (author)

Subintegrality, invertible modules and Laurent polynomial extensions

Indian Academy of Sciences (India)

Department of Mathematics, Indian Institute of Technology Bombay, Powai,. Mumbai 400 076 .... An inclusion A ⊆ B of rings is called anodal or an anodal extension, if every b ∈ B such that (b2−b) ..... India for financial support. References.

Flux distribution measurements in the Bruce B Unit 6 reactor using a transportable traveling flux detector system

International Nuclear Information System (INIS)

Leung, T.C.; Drewell, N.H.; Hall, D.S.; Lopez, A.M.

1987-01-01

A transportable traveling flux detector (TFD) system for use in power reactors has been developed and tested at Chalk River Nuclear Labs. in Canada. It consists of a miniature fission chamber, a motor drive mechanism, a computerized control unit, and a data acquisition subsystem. The TFD system was initially designed for the in situ calibration of fixed self-powered detectors in operating power reactors and for flux measurements to verify reactor physics calculations. However, this system can also be used as a general diagnostic tool for the investigation of apparent detector failures and flux anomalies and to determine the movement of reactor internal components. This paper describes the first successful use of the computerized TFD system in an operating Canada deuterium uranium (CANDU) power reactor and the results obtained from the flux distribution measurements. An attempt is made to correlate minima in the flux profile with the locations of fuel channels so that future measurements can be used to determine the sag of the channels. Twenty-seven in-core flux detector assemblies in the 855-MW (electric) Unit 6 reactor of the Ontario Hydro Bruce B Generating Station were scanned

Department of Reactor Technology annual progress report 1 January -31 December 1977

International Nuclear Information System (INIS)

1978-04-01

The work of the Department of Reactor Technology within the following fields is described: reactor engineering, reactor operation, structural reliability, system reliability, reactor physics, fuel management, reactor accident analysis for LOCA and ECC, containment analysis, experimental heat transfer, reactor core dynamics and power plant simulators, experimental activation measurements and neutron radiography at the DR 1 reactor, underground storage of gas, solar heating and underground heat storage, wind power. (author)

Qualification of JEFF3.1.1 library for high conversion reactor calculations using the ERASME/R experiment

Energy Technology Data Exchange (ETDEWEB)

Vidal, J. F.; Noguere, G.; Peneliau, Y.; Santamarina, A. [CEA, DEN, DER/SPRC/LEPh, Cadarache, F-13108 Saint-Paul-lez-Durance (France)

2012-07-01

With its low CO{sub 2} production, Nuclear Energy appears to be an efficient solution to the global warming due to green-house effect. However, current LWR reactors are poor uranium users and, pending the development of Fast Neutron Reactors, alternative concepts of PWR with higher conversion ratio (HCPWR) are being studied again at CEA, first studies dating from the middle 80's. In these French designs, low moderation ratio has been performed by tightening the lattice pitch, achieving a conversion ratio of 0.8-0.9 with a MOX fuel coming from PWR UOX recycling. Theses HCPWRs are characterized by a harder neutron spectrum and the calculation uncertainties on the fundamental neutronics parameters are increased by a factor 3 regarding a standard PWR lattice, due to the major contribution of the Plutonium isotopes and of the epithermal energy range to the reaction rates. In order to reduce these uncertainties, a 3-year experimental validation program called ERASME has been performed by CEA from 1984 to 1986 in the EOLE reactor. Monte Carlo analysis of the ERASME/R experiments with the Monte Carlo code TRIPOLI4 allowed the qualification of the recommended JEFF.3.1.1 library for major neutronics parameters. K{sub eff} of the MOX under-moderated lattice is over-predicted by 440 {+-} 830 pcm (2{sigma}); the conversion ratio, indicator of the good use of uranium, is also slightly over-predicted: 2 % {+-} 4 % (2{sigma}) and the same for B4C absorber rods worth and soluble boron worth, over-predicted by 2 %, both in the 2 standard deviations range. The radial fission maps of heterogeneities (water-holes, B4C and fertile rods) are well reproduced: maximal (C-E)/E dispersion is 1.3 %, maximal power peak error is 2.7 %. The void reactivity worth is the only parameter poorly calculated with an overprediction of +12.4% {+-} 1.5%. ERASME/R analysis of MOX reactivity, void effect and spectral indexes will contribute to the reevaluation of {sup 241}Am and Plutonium isotopes

Grouping of HLW in partitioning for B/T (burning and/or transmutation) treatment with neutron reactors based on three criteria

International Nuclear Information System (INIS)

Kitamoto, Mulyanto; Kitamoto, Asashi

1995-01-01

A grouping concept of HLW in partitioning for B/T (burning and/or transmutation) treatment by fission reactor was developed in order to improve the disposal in waste management from the safety aspect. The selecting and grouping concept was proposed herein, such as Group MA1 (Np, Am, and unrecovered U and Pu), Group MA2 (Cm, and trace quantity of Cf, etc.), Group A (Tc and I), Group B (Cs and Sr) and Group R (the partitioned remains of HLW), judging from the three criteria for B/T treatment, based on (1) the concept of the potential risk estimated by the hazard index for long-term tendency based on ALI (2) the concept of the relative dose factor related to the adsorbed migration rate transferred through ground water, and (3) the concept of the decay acceleration factor, the burning and/or transmutation characteristics for recycle B/T treatment. (author)

Reactor Engineering Department annual report (April 1, 1988 - March 31, 1989)

International Nuclear Information System (INIS)

1989-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1988 (April 1, 1988 - March 31, 1989). The Department has promoted cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and also to PNC's fast reactor project. Other major Department's programs are the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Application of a high energy accelerator to the nuclear engineering is also preliminarily assessed. The report also contains the latest progress in various basic researches as nuclear data and group constants, theoretical methods and code development, reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/ diagnosis and technical developments related to the reactor physics facilities. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Assessment of torsatrons as reactors

International Nuclear Information System (INIS)

Lyon, J.F.; Painter, S.L.

1992-12-01

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R 0 = 6.6-8.8 m, on-axis magnetic field B 0 = 4.8-7.5 T, B max (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions

An annotated checklist of scale insects (Hemiptera: Coccoidea) of Saint Lucia, Lesser Antilles .

Science.gov (United States)

Malumphy, Chris

2014-07-31

An annotated list of 83 scale insect species (Hemiptera: Sterorrhyncha: Coccoidea) recorded from Saint Lucia is presented, based on data gathered from UK quarantine interceptions, samples collected in an urban coastal habitat in the North West of the Island in 2013, and published records. Thirty-three species (40%) are recorded for the first time for the country, including Dysmicoccus joannesiae (Costa Lima), a South American mealybug, and Poliaspoides formosana (Takahashi), an Asian armoured scale insect pest of bamboo, which are new for the Caribbean region. The economic, environmental and social impacts caused by introduced exotic species of scale insect are discussed. Two predatory midges Diadiplosis ?coccidivora (Felt) and Diadiplosis multifila (Felt) (Diptera: Cecidomyiidae) are recorded for the first time from Saint Lucia. The latter species was observed causing 90% mortality of a large infestation of passion vine mealybug Planococcus minor (Maskell) on soursop fruit. 

Parametric study of the low-enriched uranium integrated Fort-Saint-Vrain element; comparative evaluation with the interacting tubular element

International Nuclear Information System (INIS)

Cerles, J.M.; Carvallo, G.; Vallepin, C.

1971-11-01

This paper presents a study of the influence of the different geometric and neutronic parameters on the calculation of the cycle with low-enriched uranium in a Fort-Saint-Vrain type brick. The study is divided in two parts: a stage of physics, essentially neutronics; an economical part where the costs are taken into account. At the level of studies of neutronics and costs, a parallel comparison is developed between the brick Fort-Saint-Vrain and the interacting tubular element, and even thorium. 6 refs. 29 figs [fr

Nondestructive post-irradiation examination of Loop-1, S1 and B1 rods

International Nuclear Information System (INIS)

Bratton, R.L.

1997-05-01

As a part of the Pacific Northwest National Laboratory's Tritium Target Development Program, eleven tritium target rods were irradiated in the Advanced Test Reactor located at the Idaho National Engineering and Environmental Laboratory during 1991. Both nondestructive and destructive post-irradiation examination on all eleven rods was planned under the Tritium Target Development Program. Funding for the program was reduced in 1991 resulting in the early removal of the program experiments before reaching their irradiation goals. Post-irradiation examination was only performed on one of the irradiated rods at the Pacific Northwest National Laboratory before the program was terminated in 1992. On December 6, 1995, the Secretary of Energy announced the pursuit of the Commercial Light-Water Reactor option for producing tritium establishing the Tritium Target Qualification Program at the Pacific Northwest National Laboratory. This program decided to pursue nondestructive and destructive post-irradiation examination of the ten remaining rods from the previous program. The ten rods comprise three experiments. The Loop-1 experiment irradiated eight target rods in a loop configuration for 217 irradiation days. The other two rods were irradiated in two separate irradiation experiments, designated as S1 and B1 for 143 effective full-power days, but at different power levels. After the ten rods were transferred from the ATR Canal to the Hot Fuels Examination Facility, the following examinations were performed: (1) visual examination and photography; (2) neutron radiography; (3) axial gamma scanning; (4) contact profilometry measurement; (5) bow and length measurements; (6) rod puncture and plenum gas analysis/measurement of plenum gas quantity; (7) void volume determination; and (8) internal pressure determination. This report presents the data collected during these examinations

Thai Research Reactor (TRR-1/M1) Neutron Beam Measurements

International Nuclear Information System (INIS)

Ratanatongchai, Wichian

2009-07-01

Full text: Neutron beam tube of neutron radiography facility at Thai Research Reactor (TRR-1/M1) Thailand Institute of Nuclear Technology (public organization) is a divergent beam. The rectangular open-end of the beam tube is 16 cm x 17 cm while the inner-end is closed to the reactor core. The neutron beam size was measured using 20 cm x 40 cm neutron imaging plate. The measurement at the position 100 cm from the end of the collimator has shown that the beam size was 18.2 cm x 19.0 cm. Gamma ray in neutron the beam was also measured by the identical position using industrial X ray film. The area of gamma ray was 27.8 cm x 31.1 cm with the highest intensity found to be along the neutron beam circumference

New measuring and protection system at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Jurickova, M.

2006-01-01

The contribution describes the new measuring and protection system of the VR-1 training reactor. The measuring and protection system upgrade is an integral part of the reactor I and C upgrade. The new measuring and protection system of the VR-1 reactor consists of the operational power measuring and the independent power protection systems. Both systems measure the reactor power and power rate, initiate safety action if safety limits are exceeded and send data (power, power rate, status, etc.) to the reactor control system. The operational power measuring system is a full power range system that receives signal from a fission chamber. The signal is evaluated according to the reactor power either in the pulse or current mode. The current mode utilizes the DC current and Campbell techniques. The new independent power protection system operates in the two highest reactor power decades. It receives signals from a boron chamber and evaluates it in the pulse mode. Both systems are computer based. The operational power measuring and independent power protection systems are diverse - different types and location of chambers, completely different hardware, software algorithms for the power and power rate calculations, software development tools and teems for the software manufacturing. (author)

Reactor Engineering Department annual report (April 1, 1990 - March 31, 1991)

International Nuclear Information System (INIS)

1991-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1990 (April 1, 1990 - March 31, 1991). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Reactor Engineering Department annual report (April 1, 1991-March 31, 1992)

International Nuclear Information System (INIS)

1992-08-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1991 (April 1, 1991-March 31, 1992). The major Department's programs promoted in the year are assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researchers on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative work to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Further contributions to a new tectonic interpretation of the Sainte Victoire Mountain (Provence, France)

Energy Technology Data Exchange (ETDEWEB)

Ricour, J.; Monteau, R.; Laville, P.; Agryriadis, I.

2016-10-01

A new tectonic interpretation of the Sainte Victoire Mountain (north of Marseille, south eastern France) is proposed, principally invoking vertical movements and providing evidence which suggests an uplift which may be still active today in the western part. Some new observations confirm our hypothesis. (Author)

MX 8: the next generation high capacity system for the transport of fresh MOX fuel

International Nuclear Information System (INIS)

Potelle, F.; Issard, H.

1998-01-01

The choice of reprocessing policy was made a long time ago in France, leading to the development of an advanced Pu recycling industry. In 1987, Saint Laurent was the first French reactor to be loaded with fresh MOX fuel. Transnucleaire, then in charge of transport packaging development, created the FS 69 concept, derived from the classical RCC concept for the transport of UO 2 fresh fuel. On the other hand, Cogema, as the main actor in the field of fuel cycle and thus in transport matters, developed the associated security truck and security caisson in order to provide the transport system with the acceptable Physical Protection devices required by French Authorities. As a whole, the security truck and the FS 69 have now been used for more than ten years with a remarkable level of efficiency and safety. Indeed, more than 600 fresh MOX fuel elements have been delivered, without any incident, both regarding safety or fuel integrity requirements. But, as a matter of fact, the replacement of FS 69 transport system is now scheduled for several reasons. First of all, the burnups achieved with UO 2 fuel progressed together with its enrichment within the last ten years, and the MOX 'equivalence' also implies that its Pu content be increased to enhance its reactor performances: from 5.25 % of Pu content today, the MOX fuel will reach 7% tomorrow, and almost 10% the day after tomorrow. Lastly, the reprocessing/recycling policy has been confirmed and amplified, leading to an increasing number of 'moxified' reactors. As a consequence, the French utility (EDF), the fuel designer (Fragema, the joint venture between Framatome and Cogema), the fuel manufacturer (Cogema), and the transporter (Transnucleaire) joined in a specific working group devoted to the development of the MX 8, the next generation high capacity system for the land transport of MOX fuel. (authors)

Puentes de Saint-André-de-Cubzac y de Angers Francia

Directory of Open Access Journals (Sweden)

Mathivat, J.

1978-02-01

Full Text Available The development of the technique of prefabricated voussoir bridges during the past years has been made possible by the progress achieved in various fields which are developed here, namely: 1 the improvement of the joint between arch stones by the adoption of multiplenotch joints where the adhesive plays a less important part, 2 the increase ín the cross dimensions of the voussoirs as well as in their unit weight, which reduces the number of joints, as well as the diversification of the forms, which can lead to the elimination of the cross prestress, 3 the improvement of the methods of placing and of the design of the lifting rigs: mobile lifting equipement carried by the deck, launching girder. The study of these different factors is supplemented and illustrated by the presentation of two recent works: the freeway bridges of Saint-André-de-Cubzac and the bridge on the Loire near Angers.

El desarrollo de la técnica de los puentes de dovelas prefabricadas ha experimentado un fuerte incremento, durante los últimos años, a causa de: 1 Mejoramiento de las juntas entre dovelas, por adopción de sistemas dotados de dentado múltiple, en cuyo caso el papel de la cola es menos primordial. 2 Aumento de las dimensiones transversales de las dovelas, así como de su peso unitario, lo cual reduce el número de juntas, así como la diversificación de las formas, con lo cual se puede conseguir la supresión del pretensado transversal. 3 Mejoras introducidas en los métodos de colocación y en el diseño de los aparatos de elevación: equipo móvil de elevación soportado por el propio tablero, viga de lanzamiento. El estudio de estos distintos factores se ha ilustrado con la presentación de dos obras recientemente ejecutadas, a saber: los puentes de autopista de Saint-André-de-Cubzac y el puente del Loira, cerca de Angers.

To report the obtained results in the simulation with the FCS-11 and Presto codes of the two first operation cycles of the Laguna Verde Unit 1 reactor; Reportar los resultados obtenidos en la simulacion con los codigos FCS-11 y PRESTO de los dos primeros ciclos de operacion del reactor Laguna Verde Unidad 1

Energy Technology Data Exchange (ETDEWEB)

Montes T, J.L.; Moran L, J.M.; Cortes C, C.C

1990-08-15

The objective of this work is to establish a preliminary methodology to carry out analysis of recharges for the reactor of the Laguna Verde U-1, by means of the evaluation of the state of the reactor core in its first two operation cycles using the FCS2 and Presto-B codes. (Author)

Thermohydraulic analysis for power increase of IEAR-1 reactor

International Nuclear Information System (INIS)

Umbehaun, Pedro E.; Bastos, Jose L.F.

1996-01-01

In this work has been presented the reactor core thermohydraulic model of IEAR-1, aiming its power operation increase from 2MW to 5MW. The design criteria adopted have been established in Safety Series 35. Three configurations of reactor core were analysed: fuel elements 20, 25 and 30

Decommissioning and decontrolling the R1-reactor

International Nuclear Information System (INIS)

Bergman, C.; Holmberg, B.T.

1985-01-01

Sweden's first nuclear reactor - the research reactor R1 - situated in bedrock under the Royal Technical Institute of Stockholm, has in the period 1981-1983 been subject to a complete decommissioning. The National Institute for Radiation Protection has followed the work in detail, and has after the completion of the decommissioning performed measurements of radioactivity on site. The report gives an account of the work the Institute has done in preparation for- and during decommissioning and specifically report on the measurements for classification of the local as free for non-nuclear use. (aa)

Centro Federal de Comunidad Saint Louis - EE.UU.

Directory of Open Access Journals (Sweden)

Hellmuth, George

1980-04-01

Full Text Available The Community Federal Center lies in the outskirts of the town of Saint Louis. It was conceived and designed by the project authors — in a style characteristic of them — as a suburban architectonic complex for office use. The work, standing out over an open stretch of land, has an ample base, with a volume that is neither the actual tower of the city centre nor the classic low rural construction. The building's architectonic language permits an integration, by sympathy, in the context of the neighbouring uni-family housing zone, without naturally being assimilated in them, due to the disparity of functions. It is achieved through a fracture of scaled volumes, breaking the classic coldness of the big office building, whilst at the same time thanks to its robustness, it indicates the activity housed inside.

El Community Federal Center está emplazado en las afueras de la ciudad de Saint Louis. Fue concebido y diseñado por los autores del proyecto —en un estilo que les es característico—, como un complejo arquitectónico suburbano destinado a oficinas. La obra, que se eleva sobre un terreno despejado, es amplía de base, presentando un volumen que no es ni la torre propia del centro urbano ni la clásica construcción rural de baja altura. El lenguaje arquitectónico del edificio permite una integración, por simpatía, en el contexto de la zona de viviendas unifamiliares cercana, sin llegar, naturalmente, a asimilarse a ellas dada la disparidad de funciones. Se lleva a cabo por medio de una fractura de volúmenes, escalonados, que rompen la frialdad clásica del gran edificio de oficinas, sin dejar de indicar, por su robustez, la actividad que alberga en su interior.

Useful Brazilian plants listed in the field books of the French naturalist Auguste de Saint-Hilaire (1779-1853).

Science.gov (United States)

Brandão, Maria G L; Pignal, Marc; Romaniuc, Sergio; Grael, Cristiane F F; Fagg, Christopher W

2012-09-28

Information regarding the use of beneficial, native Brazilian plants was compiled by European naturalists in the 19th century. The French botanist Auguste de Saint-Hilaire (1779-1853) was one of the most important such naturalists; however, his manuscripts (field books) have not yet been studied, especially in the context of useful plants. To present data documented by Saint-Hilaire in his field book regarding the use of native plants by the Brazilians. Data on useful plants were obtained from field books (six volumes) deposited in the Muséum national d' Histoire naturelle in Paris, France. The vernacular names of the plants, registered as "N.V." or "Nom Vulg." in the field book, were carefully searched. Traditional information about these plants was translated and organised using a computer. The botanical identification of each plant was determined and updated from the original descriptions and names cited in the field books by A. de Saint-Hilaire. Correlated pharmacological studies were obtained from PubMed. A total of 283 useful plants were recorded from the field books and 165 (58.3%) could be identified to genus or species. Fifty-eight different traditional uses were registered for the identified plants; the most common were as purgatives and febrifuges. Other data recovered were related to edible fruits and plants with interesting sensorial characteristics. For the few species that have been subjected to laboratory studies, the efficacy of the recorded traditional uses was confirmed. The data recorded by the French naturalist A. de Saint-Hilaire represent a rich, unexplored source of information regarding the traditional uses of Brazilian plants. Copyright © 2012 Elsevier Ireland Ltd. All rights reserved.

Upgrading of the research reactors FRG-1 and FRG-2

International Nuclear Information System (INIS)

Krull, W.

1981-01-01

In 1972 for the research reactor FRG-2 we applied for a license to increase the power from 15 MW to 21 MW. During this procedure a public laying out of the safety report and an upgrading procedure for both research reactors - FRG-1 (5 MW) and FRG-2 - were required by the licensing authorities. After discussing the legal background for licensing procedures in the Federal Republic of Germany the upgrading for both research reactors is described. The present status and future licensing aspects for changes of our research reactors are discussed, too. (orig.) [de

Levels of insecticide resistance to deltamethrin, malathion, and temephos, and associated mechanisms in Aedes aegypti mosquitoes from the Guadeloupe and Saint Martin islands (French West Indies).

Science.gov (United States)

Goindin, Daniella; Delannay, Christelle; Gelasse, Andric; Ramdini, Cédric; Gaude, Thierry; Faucon, Frédéric; David, Jean-Philippe; Gustave, Joël; Vega-Rua, Anubis; Fouque, Florence

2017-02-10

In the Guadeloupe and Saint Martin islands, Aedes aegypti mosquitoes are the only recognized vectors of dengue, chikungunya, and Zika viruses. For around 40 years, malathion was used as a mosquito adulticide and temephos as a larvicide. Since the European Union banned the use of these two insecticide molecules in the first decade of the 21st century, deltamethrin and Bacillus thuringiensis var. israelensis are the remaining adulticide and larvicide, respectively, used in Guadeloupe. In order to improve the management of vector control activities in Guadeloupe and Saint Martin, we investigated Ae. aegypti resistance to and mechanisms associated with deltamethrin, malathion, and temephos. Ae. aegypti mosquitoes were collected from six different localities of Guadeloupe and Saint Martin. Larvae were used for malathion and temephos bioassays, and adult mosquitoes for deltamethrin bioassays, following World Health Organization recommendations. Knockdown resistance (Kdr) genotyping for V1016I and F1534C mutations, and expression levels of eight enzymes involved in detoxification mechanisms were examined in comparison with the susceptible reference Bora Bora strain. Resistance ratios (RR 50 ) calculated for Ae. aegypti larvae showed high resistance levels to temephos (from 8.9 to 33.1-fold) and low resistance levels to malathion (from 1.7 to 4.4-fold). Adult females displayed moderate resistance levels to deltamethrin regarding the time necessary to affect 50% of individuals, varying from 8.0 to 28.1-fold. Molecular investigations on adult mosquitoes showed high resistant allele frequencies for V1016I and F1534C (from 85 to 96% and from 90 to 98%, respectively), as well as an overexpression of the glutathione S-transferase gene, GSTe2, the carboxylesterase CCEae3a, and the cytochrome genes 014614, CYP6BB2, CYP6M11, and CYP9J23. Ae. aegypti populations from Guadeloupe and Saint Martin exhibit multiple resistance to organophosphates (temephos and malathion), and

Computational methodology for the Oak Ridge Research Reactor (ORR) and Bulk Shielding Reactor (BSR): cross-section and validation. Volume 1

International Nuclear Information System (INIS)

Miller, L.F.; Williams, M.L.

1986-03-01

A neutronics library suitable for low-enrichment uranium (LEU) and high-enrichment uranium (HEU) fueled cores for both the Oak Ridge Research Reactor (ORR) and the Bulk Shielding Reactor (BSR) is documented herein. The library is obtained from version V of the Evaluated Nuclear Data File (ENDF/B-V) and contains 223 nuclides weighted over a variety of region-dependent neutron spectra. Self-shielding and zone-weighting effects are incorporated with 227-group calculations for several reactor-core configurations. Libraries are archived for both transport and diffusion theory seven-group calculations. Complete listings of processing details are included so that libraries with different specifications can be easily obtained. Results from validation calculations indicate that the neutronics libraries obtained from this effort are suitable for neutronics computations for the ORR and BSR. 12 refs., 5 figs., 15 tabs

RA Research reactor Annual report 1981 - Part 1, Operation, maintenance and utilization of the RA reactor

International Nuclear Information System (INIS)

Sotic, O.; Milosevic, M.; Martinc, R.; Kozomara-Maic, S.; Cupac, S.; Radivojevic, J.; Stamenkovic, D.; Skoric, M.

1981-12-01

The RA nuclear reactor stopped operation after March 1979 campaign due to appearance of aluminium oxyhydrates deposits on the surface of fuel element claddings. Relevant decisions of the Sanitary inspection body of the Ministry of health and the Director General of the 'Boris Kidric' Institute of nuclear sciences, Vinca, banned further reactor operation until reasons caused aluminium oxyhydrates deposition are investigated and removed to enable regular reactor operation. Until the end of 1979 and during 1980, after a series of analyses and findings that caused cease of reactor operation, all the preparatory actions needed for restart were performed. Due to the fact that there is no emergency cooling system and no appropriate filtering system at the reactor, and according to the new regulations about start up of nuclear facilities, the Sanitary inspection body made a decision about temporary licence for reactor start-up meaning performance of the 'zero experiment' limiting the operating power to 1% of the nominal power. Accordingly the reactor was restarted on January 21 1981. Criticality was reached with the core made of 80% enriched fuel elements only. After the experiment was finished by the end of March a permission was demanded for operation at higher power levels at full power. Taking into account the state of the reactor components the operating licence was issued limiting the power to 2 MW until reconstruction of the ventilation system and construction of the emergency cooling system are fulfilled. Program of testing operation started on September 15 1981 increasing gradually the operating power. Thus the reactor was operated at 2 MW power for 15 days during November and December. The total production achieved in 1981 was 1698 MWh. This enabled isotopes production at the reactor during last two months. Control and maintenance of the reactor components and systems was done regularly and efficiently within limits imposed by availability of spare parts. The

Safe Management Of Fast Reactors: Towards Sustainability

International Nuclear Information System (INIS)

Dreimanis, Andrejs

2015-01-01

An interdisciplinary systemic approach to socio-technical optimization of nuclear energy management is proposed, by recognizing a) the rising requirements to nuclear safety being realized using fast reactors (FR), b) the actuality to maintain and educate qualified workforce for fast reactors, c) the reactor safety and public awareness as the keystones for improving attitude to implement novel reactors. Knowledge management and informational support firstly is needed in: 1) technical issues: a) nuclear energy safety and reliability, b) to develop safe and economic technologies; 2) societal issues: a) general nuclear awareness, b) personnel education and training, c) reliable staff renascence, public education, stakeholder involvement, e).risk management. The key methodology - the principles being capable to manage knowledge and information issues: 1) a self-organization concept, 2) the principle of the requisite variety. As a primary source of growth of internal variety is considered information and knowledge. Following questions are analyzed indicating the ways of further development: a) threats in peaceful use of nuclear energy, b) basic features of nuclear risks, including terrorism, c) human resource development: basic tasks and instruments, d) safety improvements in technologies, e) advanced research and nuclear awareness improvement There is shown: public education, social learning and the use of mass media are efficient mechanisms forming a knowledge-creating community thereby reasoning to facilitate solution of key socio-technical nuclear issues: a) public acceptance of novel nuclear objects, b) promotion of adequate risk perception, and c) elevation of nuclear safety level and adequate risk management resulting in energetic and ecological sustainability. (author)

History of psychosurgery at Sainte-Anne Hospital, Paris, France, through translational interactions between psychiatrists and neurosurgeons.

Science.gov (United States)

Zanello, Marc; Pallud, Johan; Baup, Nicolas; Peeters, Sophie; Turak, Baris; Krebs, Marie Odile; Oppenheim, Catherine; Gaillard, Raphael; Devaux, Bertrand

2017-09-01

Sainte-Anne Hospital is the largest psychiatric hospital in Paris. Its long and fascinating history began in the 18th century. In 1952, it was at Sainte-Anne Hospital that Jean Delay and Pierre Deniker used the first neuroleptic, chlorpromazine, to cure psychiatric patients, putting an end to the expansion of psychosurgery. The Department of Neuro-psychosurgery was created in 1941. The works of successive heads of the Neurosurgery Department at Sainte-Anne Hospital summarized the history of psychosurgery in France. Pierre Puech defined psychosurgery as the necessary cooperation between neurosurgeons and psychiatrists to treat the conditions causing psychiatric symptoms, from brain tumors to mental health disorders. He reported the results of his series of 369 cases and underlined the necessity for proper follow-up and postoperative re-education, illustrating the relative caution of French neurosurgeons concerning psychosurgery. Marcel David and his assistants tried to follow their patients closely postoperatively; this resulted in numerous publications with significant follow-up and conclusions. As early as 1955, David reported intellectual degradation 2 years after prefrontal leucotomies. Jean Talairach, a psychiatrist who eventually trained as a neurosurgeon, was the first to describe anterior capsulotomy in 1949. He operated in several hospitals outside of Paris, including the Sarthe Psychiatric Hospital and the Public Institution of Mental Health in the Lille region. He developed stereotactic surgery, notably stereo-electroencephalography, for epilepsy surgery but also to treat psychiatric patients using stereotactic lesioning with radiofrequency ablation or radioactive seeds of yttrium-90. The evolution of functional neurosurgery has been marked by the development of deep brain stimulation, in particular for obsessive-compulsive disorder, replacing the former lesional stereotactic procedures. The history of Sainte-Anne Hospital's Neurosurgery Department sheds

Fusion reactor materials

International Nuclear Information System (INIS)

Sethi, V.K.; Scholz, R.; Nolfi, F.V. Jr.; Turner, A.P.L.

1980-01-01

Data are given for each of the following areas: (1) effects of irradiation on fusion reactor materials, (2) hydrogen permeation and materials behavior in alloys, (3) carbon coatings for fusion applications, (4) surface damage of TiB 2 coatings under energetic D + and 4 He + irradiations, and (5) neutron dosimetry

Department of Reactor Technology: annual progress report 1 January - 31 December 1976

International Nuclear Information System (INIS)

1977-06-01

The work of the Department of Reactor Technology within the following fields is described: reactor engineering, structural reliability, system reliability, radiation fiels in nuclear power plants, reactor physics, fuel management, fission product decay analysis, steady-state thermo-hydraulics, reactor accident analysis for LOCA and ECC, containment analysis, experimental heat transfer, reactor core dynamics and power plant simulators, control rod ejection accident analysis, economic studies for power plants, experimental activation measurements and neutron radiography at the DR 1 reactor. (author)

Recuperation of the energy released in the G-1, an air-cooled graphite reactor core; Recuperation de l'energie degagee dans G 1 pile a graphite refroidie a l'air

Energy Technology Data Exchange (ETDEWEB)

Chambadal, P [Electricite de France (EDF), 75 - Paris (France); Pascal, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The CEA (in his five-year setting plan) has objective among others, the realization of the two first french reactors moderated with graphite. The construction of the G-1 reactor in Marcoule, first french plutonic core, is achieved so that it will diverge in the beginning of 1956 and reach its full power in the beginning of the second semester of the same year. In this report we will detail the specificities of the reactor and in particular its cooling and energy recuperation system. The G-1 reactor being essentially intended to allow the french technicians to study the behavior of an energy installation supply taking its heat in a nuclear source as early as possible. (M.B.) [French] Le Commissariat a l'Energie Atomique (dans le cadre du plan quinquennal) a entre autres objectifs, la realisation des deux premiers reacteurs francais moderes au graphite. La construction du reacteur G-1 a Marcoule, premiere pile plutonigene francaise, est realise afin qu'il puisse diverger au debut de 1956 et atteindre sa pleine puissance au debut du second semestre de la meme annee. Dans ce rapport nous detaillerons les specificites du reacteur et en particulier son systeme de refroidissement et de recuperation d'energie. Le reacteur G-1 etant essentielement destine a permettre aux techniciens francais d'etudier le plus tot possible le comportement d'une installation productrice d'energie empruntant sa chaleur a une source nucleaire. (M.B.)

High Leptospira seroprevalence in captive and wild-caught vervet monkeys ( Chlorocebus sabeus) on the Caribbean island of Saint Kitts.

Science.gov (United States)

Rajeev, Sreekumari; Conan, Anne; Pratt, Nicola; Beierschmitt, Amy; Palmour, Roberta

2017-11-01

Leptospirosis is a zoonotic disease of global importance. Very little information is available on Leptospira infection in nonhuman primates. We report herein a high seroprevalence (49.4%; 95% confidence interval: 41.6-57.2%) to Leptospira serovars in vervet monkeys ( Chlorocebus sabeus) on the Caribbean island of Saint Kitts. Monkeys bred in captivity ( n = 81) had a significantly higher seroprevalence compared to wild-caught monkeys ( n = 81; p Leptospira serovars and seroconversion occurs in wild and captive vervet monkeys on the Caribbean island of Saint Kitts. Further studies are warranted to better understand epidemiology, transmission, pathology, and possible reservoir status in this species.

Chalon/Saint-Marcel manufacturing plant

International Nuclear Information System (INIS)

2008-01-01

AREVA is the world leader in the design and construction of nuclear power plants, the manufacture of heavy components, and the supply of nuclear fuel and nuclear services such as maintenance and inspection. The Equipment Division provides the widest range of nuclear components and equipment, manufactured at its two facilities in Jeumont, northern France, and St. Marcel, in Burgundy. The St. Marcel plant, set on 35 ha (87.5 acres) near Chalon-sur-Saone, was established in 1973 in a region with a long history of specialized metalworking and mechanical activities to meet the demand for non-military nuclear requirements in France. The site offers two advantages: - excellent facilities for loading and transporting heavy components on the Saone river, - it's proximity to other group sites. Since its completion in 1975, the Chalon/St. Marcel facility has manufactured all the heavy components for French pressurized water reactors (PWRs) ranging from 900 MW to 1500 MW. It has also completed a significant number of export contracts that have made AREVA world leader. Nearly 600 heavy components (reactor vessels, steam generators, pressurizers and closure heads) have been manufactured or are currently being manufactured since the plant opened in 1975. The plant is at the heart of the manufacturing chain for nuclear steam supply systems (NSSS) supplied by AREVA. On the basis of engineering data, the plant manufactures reactor vessels, reactor vessel internals, steam generators, pressurizers and related components such as accumulators, auxiliary heat exchangers and supporting elements. Vessel upper internals Other similar components such as reactor vessels for boiling water reactors (BWR) or high temperature reactors (HTR) and other types of steam generators can also be manufactured in the plant (for example Once Through Steam Generators - OTSG). The basic activities performed at Chalon/St. Marcel are metalworking and heavy machining. These activities are carried out in strict

Neutron radiation damage studies in the structural materials of a 500 MWe fast breeder reactor using DPA cross-sections from ENDF / B-VII.1

Science.gov (United States)

Saha, Uttiyoarnab; Devan, K.; Bachchan, Abhitab; Pandikumar, G.; Ganesan, S.

2018-04-01

The radiation damage in the structural materials of a 500 MWe Indian prototype fast breeder reactor (PFBR) is re-assessed by computing the neutron displacement per atom (dpa) cross-sections from the recent nuclear data library evaluated by the USA, ENDF / B-VII.1, wherein revisions were taken place in the new evaluations of basic nuclear data because of using the state-of-the-art neutron cross-section experiments, nuclear model-based predictions and modern data evaluation techniques. An indigenous computer code, computation of radiation damage (CRaD), is developed at our centre to compute primary-knock-on atom (PKA) spectra and displacement cross-sections of materials both in point-wise and any chosen group structure from the evaluated nuclear data libraries. The new radiation damage model, athermal recombination-corrected displacement per atom (arc-dpa), developed based on molecular dynamics simulations is also incorporated in our study. This work is the result of our earlier initiatives to overcome some of the limitations experienced while using codes like RECOIL, SPECTER and NJOY 2016, to estimate radiation damage. Agreement of CRaD results with other codes and ASTM standard for Fe dpa cross-section is found good. The present estimate of total dpa in D-9 steel of PFBR necessitates renormalisation of experimental correlations of dpa and radiation damage to ensure consistency of damage prediction with ENDF / B-VII.1 library.

Irradiation routine in the IPR-R1 Triga reactor

International Nuclear Information System (INIS)

Maretti Junior, F.

1980-01-01

Information about irradiations in the IPR-R1 TRIGA reactor and procedures necessary for radioisotope solicitation are presented All procedures necessary for asking irradiation in the reactor, shielding types, norms of terrestrial and aerial expeditions, payment conditions, and catalogue of disposable isotopes with their respective saturation activities are described. (M.C.K.)

Chooz B

International Nuclear Information System (INIS)

Barillot, Pascale; Baize, Jean-Marc

1997-01-01

This EDF press communique give information related to the exploitation of the Chooz B NPP. A calendar of the Chooz B1 and B2 NPPs exploitation is given as well as information about the local economic impact. The exploitation of the PWR reactors of the French nuclear sector corresponds to a accumulated experience of 600 year-reactor. Significant technological evolution has been recorded, namely in the test-control system, the turbo-alternator group 'Arabelle' and in the vapor generators. The reactor safety is based on the high professionalism of the exploitation personnel, on the computer-assisted behaviour allowing the choice of operators and on the conception based upon the experience accumulated by the French nuclear power plants, equivalent to 600 year-reactor operation. EDF operates a system of continual surveillance which allows the monitoring the environmental effects caused by the NPP exploitation. The following issues concerning the environment impact are reported in this document: - The effluent releases in the environment; - Health studies conducted in the NPPs' neighbourhood; - New authorizations for waste release; - Radioactive waste management. The report also mentions the French-Belgian partnership in the PWR construction, the socio-economic regional impact of the EDF activities related with the Chooz NPP operation, and the partnership with the associated service companies. Six appendices are attached to the report containing the following information: - A general layout of Chooz NPP; - Chooz B key figures; Chooz B key data; - Security and public information; - Evolution of PWR system in France; - World's nuclear systems

Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1

International Nuclear Information System (INIS)

Reyes F, M. C.; Del Valle G, E.; Filio L, C.

2013-10-01

The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S 2 and P 1 . Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

Benchmark of the CASMO-3G/MICROBURN-B codes for Commonwealth Edison boiling water reactors

International Nuclear Information System (INIS)

Wheeler, J.K.; Pallotta, A.S.

1992-01-01

The Commonwealth Edison Company has performed an extensive benchmark against measured data from three boiling water reactors using the Studsvik lattice physics code CASMO-3G and the Siemens Nuclear Power three-dimensional simulator code MICROBURN-B. The measured data of interest for this benchmark are the hot and cold reactivity, and the core power distributions as measured by the traversing incore probe system and gamma scan data for fuel pins and assemblies. A total of nineteen unit-cycles were evaluated. The database included fuel product lines manufactured by General Electric and Siemens Nuclear Power, wit assemblies containing 7 x 7 to 9 x 9 pin configurations, several water rod designs, various enrichments and gadolina loadings, and axially varying lattice designs throughout the enriched portion of the bundle. The results of the benchmark present evidence that the CASMO-3G/MICROBURN-B code package can adequately model the range of fuel and core types in the benchmark, and the codes are acceptable for performing neutronic analyses of Commonwealth Edison's boiling water reactors

Neutron density optimal control of A-1 reactor analoque model

International Nuclear Information System (INIS)

Grof, V.

1975-01-01

Two applications are described of the optimal control of a reactor analog model. Both cases consider the control of neutron density. Control loops containing the on-line controlled process, the reactor of the first Czechoslovak nuclear power plant A-1, are simulated on an analog computer. Two versions of the optimal control algorithm are derived using modern control theory (Pontryagin's maximum principle, the calculus of variations, and Kalman's estimation theory), the minimum time performance index, and the quadratic performance index. The results of the optimal control analysis are compared with the A-1 reactor conventional control. (author)

Baldrige Award cites two hospitals. Baptist, Saint Luke's hospitals honored for quality, performance.

Science.gov (United States)

Rees, Tom

2004-01-01

Baptist Hospital Inc., Pensacola, Fla.; and Saint Luke's Hospital, Kansas City, Mo., have received the prestigious Malcolm Baldrige National Quality Award in the category of healthcare. Named for a former secretary of commerce, the award recognizes efficiency, effectiveness and excellence. The two hospitals are among only seven companies in the U.S. to be so recognized this year.

In-service inspection of pool type research reactors

International Nuclear Information System (INIS)

Rajamani, K.

2002-01-01

In the case of Apsara Reactor, it has been proposed to carry out major modifications in the near future. It is planned to modify the core suitably with a heavy water reflector tank to demonstrate the Multiple Purpose Research Reactor concept. The core structure will be a stationary one and will be located at the 'B' position of the pool. The modified reactor will be operated at 1 MW power level. Suitable methodologies are evolved for carrying out a planned ISI for this modified reactor

Department of Reactor Technology annual progress report 1 January - 31 December 1978

International Nuclear Information System (INIS)

1979-04-01

The activities of the department of reactor technology at Risoe during 1978 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

New optical museum at Saint-Petersburg for education and training

Science.gov (United States)

Vasil'ev, V. N.; Stafeef, S. K.; Tomilin, M. G.

2009-06-01

Nowadays the educational problem of teaching optics and photonics is to attract the young generation to the wonderful and magic world of light, optical science, technology and systems. The main issue is to explain that in the course of last several hundred years optics has been representing the most clear world view for humanity. In fact, the optics itself is a multidisciplinary complex of independent scientific directions, and, moreover, it has always been a generator of new fields of knowledge. Besides, optics and photonics are the fields within which the most fundamental problems of today's reality are to be resolved. It is absolutely necessary to encourage our scholars in getting optics and photonics education as an alternative physical basis to gaining solely computer knowledge. The main obstacle is the poor connection between program of optical education and the real optical researches, disintegration of different branches of the optical science, the demographic situation, some problems with teaching mathematics and physics at schools, and the collision between traditional educational methods and the mentality of the new generation. In Russia the Saint-Petersburg State University of Information Technologies, Mechanics and Optics offers partial solution to these problems: the organization of a real place for interactive optical science in a form of a new museum of optics, intended for education and training, seems to be the most effective way. This was the main reason for establishing such a museum in Saint-Petersburg at the end of 2008.

Motifs et manifestations de l’amour de l’homme pour Dieu et l’amour du prochain selon Saint Basile le Grand

Directory of Open Access Journals (Sweden)

Ernest Janczyk

2017-04-01

Full Text Available This article addresses the issue of the motivation of the fundamental order of love for God and the neighbour which Saint Basil the Great used in his doctrine. Based on an analysis of the texts of Saint Basil, this article demonstrates the intimate relationship that should exist between the love for God and the love for man. The ideal of this relationship is represented, according to the analysis, by Jesus Christ, the only Saviour of the world.

Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

International Nuclear Information System (INIS)

1997-10-01

This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department's programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC's fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

Reactor engineering department annual report. April 1, 1993-March 31, 1994

International Nuclear Information System (INIS)

1994-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1993 (April 1, 1993-March 31, 1994). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees organized by the Department are also summarized in this report. (author)

Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department`s programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

Reactor engineering department annual report. April 1, 1994 - March 31, 1995

International Nuclear Information System (INIS)

1995-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Modification of the IAN-R1 reactor

International Nuclear Information System (INIS)

Jaime, J.; Ahumada, S.; Spin, R.A.

1990-01-01

The IAN-R1 reactor is the only nuclear reactor operating in Colombia; it is installed at the Institute of Nuclear Affairs (AIN) in Bogota, which is an official body coming under the Ministry of Mining and Energy. This reactor started operation in January 1965 with a rated power of 10 kW and was modified a year later to operate at 20 kW, which has been its rated power up to the present. Given its importance for the application of nuclear technology in Columbia for various purposes, principally in the areas of neutron activation analysis, determination of uranium content in minerals using the delayed neutron counting method, production of certain radioisotopes such as 198 Au and 82 Br for engineering applications, and production of radioactive material for teaching and research purposes, research has been in progress for some years into ways of increasing its power. The study on experimental requirements and on the demand for locally produced radioisotopes came to the conclusion that its power should be increased to 1000 kW, which would allow the facility to remain on the same site. The modification includes conversion of the core to low-enriched fuel, operation up to 1 MW, modification of the shielding, renovation of instrumentation and installation of a radioisotope processing plant. When the reactor is modified we will be able to produce other radioisotopes for applications in nuclear medicine, industry and engineering; at the same time, the safety of the facility will be optimized and the experimental facilities improved

Fracture assessment of the Oskarshamn 1 reactor pressure vessel under cold over-pressurization

Energy Technology Data Exchange (ETDEWEB)

Sattari-Far, I. [DNV Technical Consulting AB, Stockholm (Sweden)

2001-03-01

The major motivation of this study was to develop a methodology for fracture assessment of surface defects in the 01 reactor pressure vessel under cold loading scenarios, particularly the cold over-pressurization event. According to a previous study, the FENIX project, the cold over-pressurization of the O1 reactor is a limiting loading case, as the ductile/brittle transition temperature (RT{sub NDT}) of certain welds in the O1 beltline region may be over 100 deg C at the-end-of-life condition. The FENIX project gave values of the acceptable and critical crack depth to be equal to the thickness of the cladding layer (about 6 mm) under this load case using the ASME K{sub Ic} reference curve methodology. This study is aimed to develop a methodology to give a more precise fracture assessment of the O1 reactor under cold loading scenarios. Some of the main objectives of this study have been as below: To prepare a material which can simulate the mechanical properties and RT{sub NDT} of the O1 reactor at the end-of-life conditions. To conduct a fracture mechanics test program to cover the essential influencing factors, such as crack geometry (shallow and deep cracks) and loading condition (uniaxial and biaxial) on the cleavage fracture toughness. To perform fracture mechanics analyses to identify a suitable methodology for assessment of the experimental results. To study the responses of engineering fracture assessment methods to the experimental results from the clad specimens. To propose a fracture assessment procedure for determination of the acceptable and critical flaw sizes in the 01 reactor under the cold loading events. A test program consisted of experiments on standard SEN(B) specimens and clad beams, containing surface cracks was conducted during the course of this project. A total of nine clad beams and clad cruciform specimens were tested under uniaxial and biaxial loading. The test material is reactor steel of type A 508 Grade B, which is specially heat

La estructura del poder en la "Mémoires" de Saint-Simon

OpenAIRE

Robles Vázquez, Carmen

2004-01-01

Análisis de las diferentes formas en que Saint-Simon presenta en sus Memorias el poder, y de qué manera se manifiesta éste en sus aspectos económicos, políticos, religiosos, familiares y sociales, tanto durante los últimos años del reinado de Luis XIV como durante la regencia de Felipe de Orleáns en una sociedad teocrática y absolutista, fuertemente jerarquizada, característica del Antiguo Régimen.

Dose estimation in B16 tumour bearing mice for future irradiation in the thermal column of the TRIGA reactor after B/Gd/LDL adduct infusion

Energy Technology Data Exchange (ETDEWEB)

Protti, N., E-mail: nicoletta.protti@pv.infn.it [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy); Ballarini, F.; Bortolussi, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy); Bruschi, P. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy); Stella, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy); Geninatti, S.; Alberti, D.; Aime, S. [University of Torino, Chemistry Department, via Nizza 52, 10126 Torino (Italy); Altieri, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy)

2011-12-15

To test the efficacy of a new {sup 10}B-vector compound, the B/Gd/LDL adduct synthesised at Torino University, in vivo irradiations of murine tumours are in progress at the TRIGA Mark II reactor of the Pavia University. A localised B16 melanoma tumour is generated in C57BL/6 mice and subsequently infused with the adduct. During the irradiation, the mouse will be put in a shield to protect the whole body except the tumour in the back-neck area. To optimise the treatment set-up, MCNP simulations were performed. A very simplified mouse model was built using MCNP geometry capabilities, as well as the geometry of the shield made of 99% {sup 10}B enriched boric acid. A hole in the shield is foreseen in correspondence of the back-neck region. Many configurations of the shield were tested in terms of neutron flux, dose distribution and mean induced activity in the tumour region and in the radiosensitive organs of the mouse. In the final set-up, up to five mice can be treated simultaneously in the reactor thermal column and the neutron fluence in the tumour region for 10 min of irradiation is of about 5 Multiplication-Sign 10{sup 12} cm{sup -2}.

Development of 'low activation superconducting wire' for an advanced fusion reactor

International Nuclear Information System (INIS)

Hishinuma, Y.; Yamada, S.; Sagara, A.; Kikuchi, A.; Takeuchi, T.; Matsuda, K.; Taniguchi, H.

2011-01-01

In the D-T burning plasma reactor beyond ITER such as DEMO and fusion power plants assuming the steady-state and long time operation, it will be necessary to consider carefully induced radioactivity and neutron irradiation properties on the all components for fusion reactors. The decay time of the induced radioactivity can control the schedule and scenarios of the maintenance and shutdown on the fusion reactor. V 3 Ga and MgB 2 compound have shorter decay time within 1 years and they will be desirable as a candidate material to realize 'low activation and high magnetic field superconducting magnet' for advanced fusion reactor. However, it is well known that J c -B properties of V 3 Ga and MgB 2 wires are lower than that of the Nb-based A15 compound wires, so the J c -B enhancements on the V 3 Ga and MgB 2 wires are required in order to apply for an advanced fusion reactor. We approached and succeeded to developing the new process in order to improve J c properties of V 3 Ga and MgB 2 wires. In this paper, the recent activities for the J c improvements and detailed new process in V 3 Ga and MgB 2 wires are investigated. (author)

Measurement of β/Λ ratio in IEA-R1 reactor using noise technique

International Nuclear Information System (INIS)

Moreira, J.M.L.; Kassar, E.

1986-01-01

The ratio β/Λ for the IEA-R1 reactor is obtained experimentally through the noise analysis technique. This technique is based on the determination of the power spectral density of the reactor neutron population, with the reactor in a subcritical state driven by a 'white' neutron source. A ratio β/Λ of 43,5 s -1 is estimated from the break frequency of the measured transfer function of the IEA-R1 reactor. (Author) [pt

Facts and fiction: the death of Saint Ignatius of Loyola.

Science.gov (United States)

Rosenman, L D

1996-01-01

The biography of Ignatius of Loyola, the sainted founder of the Society of Jesus (the Jesuits), ends with his death in curious circumstances. A careful search of the available sources written from the time of his death in 1556 to the present has reviewed the evidence. The evidence does not support the claims for a diagnosis that has been used for four centuries. So-called historical "facts" simply are the opinions of historians. Ignatius may have suffered from hyperparathyroidism that led to his death rather than from a cholangioportal venous fistula.

A review of Strobopagurus Lemaitre, 1989 (Crustacea, Decapoda, Paguroidea, Parapaguridae, with description of a new species

Directory of Open Access Journals (Sweden)

Rafael Lemaitre

2004-09-01

Full Text Available Species of the parapagurid genus Strobopagurus Lemaitre, 1989 are reviewed based primarily on abundant specimens obtained during French campaigns across the Indo-Pacific region. A new species, S.breviacus, is described. The genus contains two other species, S. gracilipes (A. Milne-Edwards, 1891, the type of the genus, and S.sibogae (de Saint Laurent, 1972. One taxon, Parapagurus kilburni Kensley, 1973, originally described from off eastern Africa, has been found to be a junior synonym of S.sibogae. An updated diagnosis of the genus, and diagnoses and comparative illustrations of all three species, are presented together with a key to aid in their identification. Information on live coloration is provided for S.gracilipes and S. sibogae; live coloration of S. breviacus is not known.

On the Life and Deeds of San Precario, Patron Saint of Precarious Workers and Lives

Directory of Open Access Journals (Sweden)

Marcello Tarì

2005-01-01

Full Text Available Noi siamo la generazione post-socialista, la generazione del dopo guerra fredda, della fine delle burocrazie verticali e del controllo sull'informazione. Siamo un movimento globale e neuropeo, che porta avanti la rivoluzione democratica scaturita dal Sessantotto mondiale e lotta contro la distopia neoliberista oggi al culmine. Siamo ecoattivisti e mediattivisti, siamo i libertari della Rete e i metroradicali dello spazio urbano, siamo le mutazioni transgender del femminismo globale, siamo gli hacker del terribile reale. Siamo gli agitatori del precariato e gli insorti del cognitariato. Siamo anarcosindacalisti e postsocialisti. Siamo tutti migranti alla ricerca di una vita migliore. E non ci iconosciamo in voi, stratificazioni tetre e tetragone di ceti politici sconfitti già nel XX secolo. Non ci riconosciamo nella sinistra italyana.Manifesto Bio/Pop del Precariato Metroradicale, 20042004 has marked the beginning of the spreading "cult" of San Precario, Patron Saint of precarious, casual, sessional, temporary, flexible and fractional workers. The Saint appears in public spaces in occasion of rallies, marches, interventions and demonstrations, and its popularity has lead to development of a precise and colorful iconography, hagiography and rituals. This popularity conversely is also the sign of the gravity of the issue of precarity in Italy and Europe .San Precario epitomises current Italian activist practices. These practices, although specifically Italian, intersect with similar realities in Europe and are based on mythopoetic narratives and actions and mediatic embodiments. This paper analysis a variety of texts produced around San Precario, from posters, saint cards, product cards, videos, "official" narratives, personal accounts, relating them to the political debate surrounding precarity.

Application of conjugate gradient method to Commix-1B three-dimensional momentum equation

International Nuclear Information System (INIS)

King, J.B.; Domanus, H.

1987-01-01

Conjugate gradient method which is a special case of the variational method was implemented in the momentum section of the COMMIX-1B thermal hydraulics code. The comparisons between this method and the conventional iterative method of Successive Over Relation (S.O.R.) were made. Using COMMIX-1B, three steady state problems were analyzed. These problems were flow distribution in a scaled model of the Clinch River Fast Breeder Reactor outlet plenum, flow of coolant in the cold leg and downcomer of a PWR and isothermal air flow through a partially blocked pipe. It was found that if the conjugate gradient method is used, the execution time required to solve the resulting COMMIX-1B system of equations can be reduced by a factor of about 2 for the first two problems. For the isothermal air flow problem, the conjugate gradient method did not improve the execution time

Low-enrichment and long-life Scalable LIquid Metal cooled small Modular (SLIMM-1.2) reactor

Energy Technology Data Exchange (ETDEWEB)

El-Genk, Mohamed S., E-mail: mgenk@unm.edu [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM (United States); Nuclear Engineering Department, University of New Mexico, Albuquerque, NM (United States); Mechanical Engineering Department, University of New Mexico, Albuquerque, NM (United States); Chemical and Biological Engineering Department, University of New Mexico, Albuquerque, NM (United States); Palomino, Luis M.; Schriener, Timothy M. [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM (United States); Nuclear Engineering Department, University of New Mexico, Albuquerque, NM (United States)

2017-05-15

Beginning-Of-Life (BOL) spatial distributions of the fission power in the core at 100 MW{sub th}, and the negative temperature reactivity feedback effects. Besides decreasing the UN fuel enrichment, other parameters examined are the materials of the followers to the B{sub 4}C rods for RSS and RC, the rods in the radial blanket assemblies, and the thickness of the scalloped BeO walls of the UN fuel and radial blanket assemblies. Despite ∼13% lower fuel enrichment (15.35%) and ∼22% lower hot-clean excess reactivity ($6.29 versus $8.06 for SLIMM-1.0 at 100 MW{sub th}), the operation life of the SLIMM-1.2 is ∼6.8% longer (6.3 versus 5.9 FPY for SLIMM-1.0), and the total negative temperature reactivity feedback is slightly smaller. At BOL, the radial blanket assemblies in ring 4, and the six UN fuel assembles in ring 1 of the SLIMM-1.2 core generate 2% and 23% of the total reactor thermal power, respectively. The twelve and eighteen UN fuel assemblies in rings 2 and 3 of the SLIMM-1.2 core generate 38% and 37% of the reactor thermal power, respectively. At EOL, the thermal power generation by the UN assemblies in rings 1 and 2 of the SLIMM-1.2 core decreases to 21.5% and 35.9%, respectively, while that by the assemblies in rings 3 and 4 increases to 37.6% and 5%, respectively.

La théorie de la diplomatie dans le Saint Empire Romain

OpenAIRE

Weber, Wolfgang E. J.

2016-01-01

Principes Dans ce que l’on nomme officiellement, depuis 1500 environ jusqu’à sa fin en 1806, le Saint Empire romain de la nation allemande (Heiliges Römisches Reich Deutscher Nation), le développement de la théorie de la diplomatie, autrement dit de conceptions relatives aux diplomates et à la diplomatie, est le fait d’élites soucieuses de mieux comprendre des problèmes posé...

Remaining Sites Verification Package for the 120-B-1, 105-B Battery Acid Sump. Attachment to Waste Site Reclassification Form 2006-057

International Nuclear Information System (INIS)

Dittmer, L.M.

2006-01-01

The 120-B-1 waste site, located in the 100-BC-1 Operable Unit of the Hanford Site, consisted of a concrete battery acid sump that was used from 1944 to 1969 to neutralize the spent sulfuric acid from lead cell batteries of emergency power packs and the emergency lighting system. The battery acid sump was associated with the 105-B Reactor Building and was located adjacent to the building's northwest corner. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

RPV-1: A Virtual Test Reactor to simulate irradiation effects in light water reactor pressure vessel steels

International Nuclear Information System (INIS)

Jumel, Stephanie; Van-Duysen, Jean Claude

2005-01-01

Many key components in commercial nuclear reactors are subject to neutron irradiation which modifies their mechanical properties. So far, the prediction of the in-service behavior and the lifetime of these components has required irradiations in so-called 'Experimental Test Reactors'. This predominantly empirical approach can now be supplemented by the development of physically based computer tools to simulate irradiation effects numerically. The devising of such tools, also called Virtual Test Reactors (VTRs), started in the framework of the REVE Project (REactor for Virtual Experiments). This project is a joint effort among Europe, the United States and Japan aimed at building VTRs able to simulate irradiation effects in pressure vessel steels and internal structures of LWRs. The European team has already built a first VTR, called RPV-1, devised for pressure vessel steels. Its inputs and outputs are similar to those of experimental irradiation programs carried out to assess the in-service behavior of reactor pressure vessels. RPV-1 is made of five codes and two databases which are linked up so as to receive, treat and/or convey data. A user friendly Python interface eases the running of the simulations and the visualization of the results. RPV-1 is sensitive to its inputs (neutron spectrum, temperature, ...) and provides results in conformity with experimental ones. The iterative improvement of RPV-1 has been started by the comparison of simulation results with the database of the IVAR experimental program led by the University of California Santa Barbara. These first successes led 40 European organizations to start developing RPV-2, an advanced version of RPV-1, as well as INTERN-1, a VTR devised to simulate irradiation effects in stainless steels, in a large effort (the PERFECT project) supported by the European Commission in the framework of the 6th Framework Program

Consumer preferences and willingness to pay for compact fluorescent lighting: Policy implications for energy efficiency promotion in Saint Lucia

International Nuclear Information System (INIS)

Reynolds, Travis; Kolodinsky, Jane; Murray, Byron

2012-01-01

This article examines consumer willingness to pay for energy-saving compact fluorescent light bulbs using the results of a stated preferences study conducted in the Caribbean island nation of Saint Lucia. Geographic location, low income status, and age are found to affect willingness-to-pay for compact fluorescent lighting, while higher income status and other demographic variables appear to have minimal or no significant impacts. Energy efficiency knowledge is associated with increased willingness-to-pay for energy-efficient bulbs and with increased use of compact fluorescent lighting. Contrary to theoretical expectations, past purchase of compact fluorescent bulbs is found to have no impact on self-reported willingness to pay. We hypothesize that this null result is due to the recent emergence of low-cost, low-quality compact fluorescent bulbs in the Saint Lucian lighting market, which may be negatively influencing consumers' preferences and expectations regarding energy-efficient lighting. Findings support the argument that government-sponsored education and subsidy programs will likely result in increased use of energy-saving technologies in Saint Lucia. But such behavioral changes may not be sustained in the long run unless low quality bulbs – the “lemons” of the compact fluorescent lighting market – can be clearly identified by consumers. - Highlights: ▶ We model how knowledge, attitudes, and past purchase affect CFL adoption. ▶ Saint Lucian consumers have some knowledge of and favorable attitudes toward CFLs. ▶ Energy efficiency knowledge increases stated willingness-to-pay (WTP) for CFLs. ▶ Past purchase does not increase WTP; low-quality ‘lemons’ may influence consumers. ▶ Policy can lower consumer risks in lighting markets where low quality bulbs exist.

Fort Saint Vrain operational experience

International Nuclear Information System (INIS)

Fuller, C.H.

1989-01-01

Fort St. Vrain (FSV), on the system of the Public Service Company of Colorado, is the only high temperature gas-cooled (HTGR) power reactor in the United States. The plant features a helium-cooled reactor with a uranium-thorium fuel cycle. The paper describes the experience made during its operation. (author). 2 refs, 4 figs, 2 tabs

Neutronics Design of Helical Type DEMO Reactor FFHR-d1

Energy Technology Data Exchange (ETDEWEB)

Tanaka, T.; Sagara, A.; Goto, T.; Yanagi, N.; Masuzaki, S.; Tamura, H.; Miyazawa, J.; Muroga, T., E-mail: teru@nifs.ac.jp [National Institute for Fusion Science, Toki (Japan)

2012-09-15

Full text: Neutronics design study has been performed in a newly started conceptual design activity for a helical type DEMO reactor FFHR-d1. Features of the FFHR-d1 design are enlargement of the basic configurations of reactor components and extrapolation of plasma parameters from those of the helical type plasma experimental machine Large Helical Device (LHD) to achieve the highest feasibility. From the neutronics point of view, a blanket space of FFHR-d1 is severely limited at the inboard of the torus. This is due to the core plasma position shifting to the inboard side under the confinement condition extrapolated from LHD. The first step of the neutronics investigation using the MCNP code has been performed with a simple torus model simulating thin inboard blanket space. A Flibe+Be/Ferritic steel breeding blanket showed preferable performances for both tritium breeding and shielding, and has been adapted as a reference blanket system for FFHR-d1. The investigations indicate that a combination of a 15 cm thick breeding blanket, 55 cm thick WC+B4C shield, i.e., the blanket space of 70 cm, could suppress the fast neutron flux and nuclear heating in the helical coils to the design targets for the neutron wall loading of 1.5 MW/m{sup 2}. Since the outboard side can provide a large space for a 60 cm thick breeding blanket, a fully-covered tritium breeding ratio (TBR) of 1.31 has been obtained in the simple torus model. The neutronics design study has proceeded to the second step using a 3-D helical reactor model. The most important issue in the 3-D neutronics design is a compatibility with the helical divertor design. To achieve a higher TBR and shielding performance, the core plasma has to be covered by the breeding blanket layers as possible. However, the dimensions of the blanket layers are limited by magnetic field lines connecting an edge of the core plasma and divertor pumping ports. After repeating modification of the blanket configuration, the global TBR of 1

Ciguatera fish poisoning in an international ship crew in Saint John Canada: 2015.

Science.gov (United States)

Muecke, C; Hamper, L; Skinner, A L; Osborne, C

2015-11-05

An international ship crew presented for medical care in Saint John, New Brunswick, following rapid onset of gastrointestinal and in some cases neurological and cardiac symptoms after a common fish meal. Ciguatera poisoning was identified as the cause of illness. This report describes the public health investigation and management of this incident, including collaboration between the implicated provincial and federal authorities.

Reactor engineering department annual report. April 1, 1995 - March 31, 1996

International Nuclear Information System (INIS)

1996-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermalhydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermalhydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Reactor engineering department annual report. April 1, 1994 - March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author).

Reactor Engineering Department annual report. April 1, 1997 - March 31, 1998

Energy Technology Data Exchange (ETDEWEB)

Ochiai, Masaaki; Ohnuki, Akira; Ono, Toshihiko [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

1998-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1997 (April 1, 1997 - March 31, 1998). The major Department`s programs promoted in the year are the achievement of the world-strongest lasing of Free Electron Laser and the verification of the core thermal integrity during design basis events in PWRs. Other Major tasks of the Department are various basic researches on the advanced reactor system design studies, the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Reactor Engineering Department annual report. April 1, 1997 - March 31, 1998

International Nuclear Information System (INIS)

Ochiai, Masaaki; Ohnuki, Akira; Ono, Toshihiko

1998-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1997 (April 1, 1997 - March 31, 1998). The major Department's programs promoted in the year are the achievement of the world-strongest lasing of Free Electron Laser and the verification of the core thermal integrity during design basis events in PWRs. Other Major tasks of the Department are various basic researches on the advanced reactor system design studies, the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Reactor engineering department annual report. April 1, 1995 - March 31, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermalhydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermalhydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

A second level of the Saint Petersburg skyline

Science.gov (United States)

Krasnopolsky, Andrey; Bolotin, Sergey

2018-03-01

The article considers the history of the residential development in Saint Petersburg and states corresponding landmark dates. In recent years, changes in the altitude range of the residential development are noted, the influence of this factor on the formation of the city's silhouette is assessed. Reasons for such changes are identified. Attractiveness of high-rise residential complexes for living is assessed. Conclusions are made of tendencies in further housing construction development in terms of its altitude range. It is noted that it is possible to locate multi-storied buildings in the periphery of the city, taking into account specific visual characteristics of the construction site and silhouette of erected buildings; as for central districts, strict regulations regarding the altitude range are needed.

Convenio de contratación para el proyecto de la iglesia Saint-Pierre de Firminy-Vert

Directory of Open Access Journals (Sweden)

Merwan Chaverra Suárez

2010-12-01

Full Text Available Los pormenores del proceso de contratación para el encargo de la iglesia Saint-Pierre de Firminy-Vert, entre 1960 y 1963, corresponde al desglose de las conversaciones e intercambios de correspondencia entre el arquitecto y sus clientes, que dieron lugar a un número de versiones y variantes del proyecto, así como a dificultades administrativas y económicas, que se prolongaron en el tiempo, hasta la firma del contrato. El proyecto de la iglesia Saint-Pierre de Firminy-Vert cuenta con un dossier completo, guardado y archivado en la Fundación Le Corbusier, que garantiza poder efectuar un análisis total del proyecto, enfocándolo en una metodología que posibilite el entendimiento y la reconstrucción de los hechos a partir de las fuentes primarias.

Digital control of research reactors

International Nuclear Information System (INIS)

Crump, J.C. III.; Richards, W.J.; Heidel, C.C.

1991-01-01

Research reactors provide an important service for the nuclear industry. Developments and innovations used for research reactors can be later applied to larger power reactors. Their relatively inexpensive cost allows research reactors to be an excellent testing ground for the reactors of tomorrow. One area of current interest is digital control of research reactor systems. Digital control systems offer the benefits of implementation and superior system response over their analog counterparts. At McClellan Air Force Base in Sacramento, California, the Stationary Neutron Radiography System (SNRS) uses a 1,000-kW TRIGA reactor for neutron radiography and other nuclear research missions. The neutron radiography beams generated by the reactor are used to detect corrosion in aircraft structures. While the use of the reactor to inspect intact F-111 wings is in itself noteworthy, there is another area in which the facility has applied new technology: the instrumentation and control system (ICS). The ICS developed by General Atomics (GA) contains several new and significant items: (a) the ability to servocontrol on three rods, (b) the ability to produce a square wave, and (c) the use of a software configurator to tune parameters affected by the actual reactor core dynamics. These items will probably be present in most, if not all, future research reactors. They were developed with increased control and overall usefulness of the reactor in mind

Hudební události pražského kláštera alžbětinek v roce 1776

Czech Academy of Sciences Publication Activity Database

Michl, Jakub

2016-01-01

Roč. 8, 1-2 (2016), s. 130-148 ISSN 1803-7828 Institutional support: RVO:68378076 Keywords : Sisters of Saint Elizabeth * cantatas * oratorios * Rochus Elinger SJ * Emilián Rickert OCist. * Marie Deodata a Presentatione B. V. Mariae OSE (Anna Justina von Klausniz) * Marie Juliana a Septem SS. Patribus OSE * Prague * music in convents Subject RIV: AL - Art, Architecture, Cultural Heritage

Present and future activities of TRIGA RC-1 Reactor

International Nuclear Information System (INIS)

Festinesi, A.

1986-01-01

A summary of reactor activities is presented and discussed. The RC-1 reactor is used by ENEA's laboratories, research institutes and national industries for different aims: research, analysis materials behaviour under neutron flux, etc. To satisfy the requests increase it is important to signalize: - the realization of a new radiochemical laboratory for radioisotopes production, to be used in a medical and/or diagnostic field in general; - the realization of a tritium handling laboratory, to study tritium solubility, release and diffusion in different material (particularly in ceramic breeder as lithium aluminate) to support Italian programs on fusion technology; - a research activity on the reactors computerized control by a console of advanced conception. The aim of this activity is the development of an ergonomic control room that could be a reference point for the planning of the power reactor control rooms

High-rise construction in the Saint Petersburg agglomeration in 1703-1950s

Science.gov (United States)

Sementsov, Sergey; Akulova, Nadezhda; Kurakina, Severina

2018-03-01

Regularities of high-rise construction (implemented projects and developments) in Saint Petersburg and the Saint Petersburg agglomeration since the foundation of the city in 1703 till the 1950s are considered. Based on these regularities, a single spatially developed system of vertical dominants is formed. High-rise construction in the city and its suburbs started in the 1710s and continues up to the present time. In the considered decades (1703-1950s), high-rise construction mostly performed urban-planning functions (with vertical and symbolic dominants), relying on patterns of the visual perception of man-made landscapes under development. Since the 1710s, the construction of vertical dominants (mainly temples, spires of towers, lighthouses, etc.) of five ranks (depending on the altitude range and in relation to the background development) was conducted in territories of the entire agglomeration. These dominants were arranged in landscapes of the city and suburbs with almost mathematically precise accuracy and according to special regulations. Such dominants obtained particular descriptive and silhouette characteristics in accordance with the conditions of spatial perception. In some periods of city development, attempts were made to create monuments (symbolic dominants) of specific height and include those in the spatial system of high-rise dominants as significant elements of the city silhouette.

Neutronic studies in the enrichment reduction of research reactor IEAR-1

International Nuclear Information System (INIS)

Maiorino, J.R.; Fanaro, L.C.B.; Mai, L.A.; Ferreira, P.S.B.; Garone, J.G.M.

1987-01-01

In the present work the codes used by the Reactor Physics Division of IPEN-CNEN-SP in calculations for plate-type reactors are described analyzing research reactor IEAR-1. The IAEA model problem for a plate-type reactor 10 MW with high, medium and low enrichment is solved through different methodologies now in use at the RTF/IPEN-CNEN-SP (HAMMER and HAMMER-TECH-CITATION and LEO4-2DBP-UM) looking into the calculation capability for high to low enrichment conversion within the contract held with the IAEA (BRA-4661). Finally, present reactor configuration calculations are compared with experimental measurements with the aim to validate the calculation method. (Author)

Application of NDT and ISI to research reactor in the Czech Republic

International Nuclear Information System (INIS)

Peterka, F.

2001-01-01

Full text: The objectives of the proposed research project are: (a) to review the present status of ISI and NDT to VR-1 and LVR-15 research reactors. (b) to be involved in the development of the ISI programme for VR-1 and LVR-15 research reactors and medium and high power research reactors of WWER type. Dr. Peterka briefly described the activities on the VR-1 and LWR-15 reactors and presented an example of a procedure to apply liquid penetrant testing. (author)

Mirror Advanced Reactor Study (MARS). Final report. Volume 1-B. Commercial fusion electric plant

International Nuclear Information System (INIS)

Donohue, M.L.; Price, M.E.

1984-07-01

Volume 1-B contains the following chapters: (1) blanket and reflector; (2) central cell shield; (3) central cell structure; (4) heat transport and energy conversion; (5) tritium systems; (6) cryogenics; (7) maintenance; (8) safety; (9) radioactivity, activation, and waste disposal; (10) instrumentation and control; (11) balance of plant; (12) plant startup and operation; (13) plant availability; (14) plant construction; and (15) economic analysis

Mirror Advanced Reactor Study (MARS). Final report. Volume 1-B. Commercial fusion electric plant

Energy Technology Data Exchange (ETDEWEB)

Donohue, M.L.; Price, M.E. (eds.)

1984-07-01

Volume 1-B contains the following chapters: (1) blanket and reflector; (2) central cell shield; (3) central cell structure; (4) heat transport and energy conversion; (5) tritium systems; (6) cryogenics; (7) maintenance; (8) safety; (9) radioactivity, activation, and waste disposal; (10) instrumentation and control; (11) balance of plant; (12) plant startup and operation; (13) plant availability; (14) plant construction; and (15) economic analysis.

Maximization of burning and/or transmutation (B/T) capacity in coupled spectrum reactor (CSR) by fuel and core adjustment

International Nuclear Information System (INIS)

Aziz, F.; Kitamoto, Asashi.

1996-01-01

A conceptual design of burning and/or transmutation (B/T) reactor, based on a modified conventional 1150 MWe-PWR system, consisted of two core regions for thermal and fast neutrons, respectively, was proposed herein for the treatments of minor actinides (MA). In the outer region 237 Np, 241 Am, and 243 Am burned by thermal neutrons, while in the inner region 244 Cm was burned mainly by fast neutrons. The geometry of B/T fuel in the outer region was left the same with that of PWR, while in the inner region the B/T fuel was arranged in a tight-lattice geometry that allowed a higher fuel to coolant volume ratio. The maximization of B/T capacity in CSR were done by, first, increasing the radius of the inner region. Second, reducing the coolant to fuel volume ratio, and third, choosing a suitable B/T fuel type. The result of the calculations showed that the equilibrium of main isotopes in CSR can be achieved after about 5 recycle stages. This study also showed that the CSR can burn and transmute up to 808 kg of MA in a single reactor core effectively and safely. (author)

RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Kozomara-Maic, S.; Cupac, S.; Radivojevic, J.; Stamenkovic, D.; Skoric, M.; Miokovic, J.

1982-12-01

Reactor test operation started in September 1981 at 2 MW power with 80% enriched fuel continued during 1982 according to the previous plan. The initial reactor core was made of 44 fuel channel each containing 10 fuel slugs. The first half of 1982 was used for the needed measurements and analysis of operating parameters and functioning of reactor systems and equipment under operating conditions. Program concerned with the testing operation at higher power levels was started in the second half of this year. It was found that the inherent excess reactivity and control rod worths ensure safe operation according to the IAEA safety standards. Excess reactivity is high enough to enable higher power level of 4.7 MW during 4 monthly cycles each lasting 15-20 days. Favourable conditions for cooling exist for the initial core configuration. Effects of poisoning at startup on the reactivity and power density distribution were measured as well as initial spatial distribution of the neutron flux which was 3,9 10 13 cm -2 s -1 at 2 MW power. Modification of the calibration coefficient in the system for automated power level control was determined. All the results show that all the safety criteria and limitations concerned with fuel utilization are fulfilled if reactor power would be 4.7 MW. Additional testing operation at 3, 4, and 4.7 MW power levels will be needed after obtaining the licence for operating at nominal power. Transition from the initial core with 44 fuel channels to the equilibrium lattice configuration with 72 fuel channels each containing 10 fuel slugs, would be done gradually. Reactor was not operated in September because of the secondary coolant pipes were exchanged between Danube and the horizontal sedimentary. Control and maintenance of the reactor equipment was done regularly and efficiently dependent on the availability of the spare parts. Difficulties in maintenance of the reactor instrumentation were caused by unavailability of the outdated spare parts

Nuclear reactor

International Nuclear Information System (INIS)

Garabedian, G.

1988-01-01

A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

Identifying Key Stakeholder Groups for Implementing a Place Branding Policy in Saint Petersburg