"Velvet":Sous-titrage de l'épisode 1 de la série de R. Campos et G.R. Neira

OpenAIRE

De Corte, Inès

2017-01-01

Sous-titrage du premier épisode de la série "Velvet" réalisée par R. Campos et G.R. Neira et produite par Bambú Producciones. Contextualisation de la série dans l'histoire et dans les jeux d'influences de l'industrie de la mode afin d'évaluer l'adaptation de la série et sa crédibilité historique. Commentaires de traduction expliquant le processus de traduction, la réflexion et la méthodologie employées. Master [120] en traduction, Université catholique de Louvain, 2017

IPR-R1 TRIGA research reactor decommissioning plan

International Nuclear Information System (INIS)

Andrade Grossi, Pablo; Oliveira de Tello, Cledola Cassia; Mesquita, Amir Zacarias

2008-01-01

The International Atomic Energy Agency (IAEA) is concerning to establish or adopt standards of safety for the protection of health, life and property in the development and application of nuclear energy for peaceful purposes. In this way the IAEA recommends that decommissioning planning should be part of all radioactive installation licensing process. There are over 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 k W and it is being licensed for 250 k W, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented the basis of decommissioning plan, an overview and the end state / final goal of decommissioning activities for the IPR-R1, and the Brazilian ongoing activities about this subject. (author)

Nuclear material control at IEA-R1 nuclear research reactor

International Nuclear Information System (INIS)

1988-01-01

The control measurements system and verification of physical inventory for fuel elements used in the operation of IEA-R1 nuclear research reactor are described. The computer code used for burn-up calculation are shown. (E.G.) [pt

New digital control system for the operation of the Colombian research reactor IAN-R1

International Nuclear Information System (INIS)

Celis del A, L.; Rivero, T.; Bucio, F.; Ramirez, R.; Segovia, A.; Palacios, J.

2015-09-01

En 2011, Mexico won the Colombian international tender for the renewal of instrumentation and control of the IAN-R1 Reactor, to Argentina and the United States. This paper presents the design criteria and the development made for the new digital control system installed in the Colombian nuclear reactor IAN-R1, which is based on a redundant and diverse architecture, which provides increased availability, reliability and safety in the reactor operation. This control system and associated instrumentation met all national export requirements, with the safety requirements established by the IAEA as well as the requirements demanded by the Colombian Regulatory Body in nuclear matter. On August 20, 2012, the Colombian IAN-R1 reactor reached its first criticality controlled with the new system developed at Instituto Nacional de Investigaciones Nucleares (ININ). On September 14, 2012, the new control system of the Colombian IAN-R1 reactor was officially handed over to the Colombian authorities, this being the first time that Mexico exported nuclear technology through the ININ. Currently the reactor is operating successfully with the new control system, and has an operating license for 5 years. (Author)

IEA-R1 reactor core simulation with RELAP5 code

International Nuclear Information System (INIS)

Rocha, Ricardo Takeshi Vieira da; Belchior Junior, Antonio; Andrade, Delvonei Alves de; Sabundjian, Gaiane; Umbehaum, Pedro Ernesto; Torres, Walmir Maximo

2005-01-01

This paper presents a preliminary RELAP5 model for the IEA-R1 core. The power distribution is supplied by the neutronic code, CITATION. The main objective is to model the IEA-R1 core and validate the model through the comparison of the results to the ones from COBRA and PARET, which were used in the Final Safety Analysis Report (FSAR) for this plant. Preliminary calculations regarding some simulations are presented. Boundary conditions are simulated through time dependent components. Results obtained are compared to those available for the IEA-R1. This study will be continued considering a model for the whole plant. Important transient and accidents will be analysed in order to verify the Emergency Core Cooling System - ECCS efficiency to hold its function as projected to preserve the integrity of the reactor core and guarantee its cooling. (author)

NBR ISO 9001 Certification for activities carried out in IEA-R1 reactor

International Nuclear Information System (INIS)

Paiva, Rosemeire P.; Salvetti, Tereza C.

2005-01-01

Since its inauguration in 1957, the IEA-R1 research reactor has been used mainly for research, development and teaching by scientific community. In the last years, with the increase of the commercial radiopharmaceutical production by Radiopharmacy Center of IPEN, the IEA-R1 reactor was recognized as a service supplier for that center and has received a treatment more commercial from IPEN Management. In 1999 the radiopharmaceutical production obtained the NBR ISO 9002 Certification, since that the IPEN Management considered convenient to invest in the certification of its internal suppliers. In this context, in 2001 the Research Reactor Center (CRPq) began the implantation of a Quality Management System (QMS) based on NBR 9001: 2000 standard, for activities related to the operation and maintenance of the IEA-R1 research reactor and irradiation services. This QMS was structured to incorporate tools already implemented in order to complain the requirements related to nuclear and radiological safe for a nuclear installation established by the regulatory organism. The QMS is supported by a documentation system composed of approximately 150 documents including quality manual, business and action plans, operational procedures and work instruction. Carlos Alberto Vanzolini Foundation (FCAV), an INMETRO certified organism, certified the 'Operation and Maintenance of the IEA-R1 Research Reactor and Irradiation Services' in December 2002. In 2003 and 2004, the QMS was audited by FCAV that determined the maintenance of the certification. This work presents the main steps of the QMS implementation, including the difficulties found and results obtained in the process. (author)

Experience and research with the IEA-R1 Brazilian reactor

International Nuclear Information System (INIS)

Fulfaro, R.; Sousa, J.A. de; Nastasi, M.J.C.; Vinhas, L.A.; Lima, F.W.

1982-06-01

The IEA-R1 reactor of the Instituto de Pesquisas Energeticas e Nucleares, IPEN, of Sao Paulo, Brazil, a lightwater moderated swimming-pool research reactor of MTR type, went critical for the first time on September 16, 1957. In a general way, in these twenty four years the reactor was utilized without interruption by users of IPEN and other institutions, for the accomplishment of work in the field of applied and basic research, for master and doctoral thesis and for technical development. Some works performed and the renewal programme established for the IEA-R1 research reactor in which several improvements and changes were made. Recent activities in terms of production of radioisotopes and some current research programm in the field of Radiochemistry are described, mainly studies and research on chemical reactions and processes using radioactive tracers and development of radioanalytical methods, such as neutron activation and isotopic dilution. The research programmes of the Nuclear Physics Division of IPEN, which includes: nuclear spectroscopy studies and electromagnetic hyperfine interactions; neutron diffraction; neutron inelastic scattering studies in condensed matter; development and application of the technique of fission track register in solid state detectors; neutron radioactive capture with prompt gamma detection and, finally, research in the field of nuclear metrology, are presented. (Author) [pt

Experience and research with the IEA-R1 Brazilian reactor

International Nuclear Information System (INIS)

Fulfaro, R.; Sousa, J.A. de; Nastasi, M.J.C.; Vinhas, L.A.; Lima, F.W. de.

1982-06-01

The IEA-R1 reactor of the Instituto de Pesquisas Energeticas e Nucleares, IPEN, of Sao Paulo, Brazil, a lighwater moderated swimming-pool research reactor of MTR type, went critical for the first time on September 16, 1957. In a general way, in these twenty four years the reactor was utilized without interruption by users of IPEN and other institutions, for the accomplishment of work in the field of applied and basic research, for master and doctoral thesis and for technical development. Some works performed and the renewal programme established for the IEA-R1 research reactor in which several improvements and changes were made. Recent activities in terms of production of radioisotopes and some current research programm in the field of Radiochemistry are described, mainly studies and research on chemical reactions and processes using radioactive tracers and development of radioanalytical methods, such as neutron activation and isotopic dilution. It is also presented the research programmes of the Nuclear Physics Division of IPEN, which includes: nuclear spectroscopy studies and electromagnetic hyperfine interactions; neutron diffraction; neutron inelastic scattering studies in condensed matter; development and application of the technique of fission track register in solid state detectors; neutron radioactive capture with prompt gamma detection and, finally, research in the field of nuclear metrology. (Author) [pt

Modifications done in the IPR-R1 reactor and their auxiliary systems

International Nuclear Information System (INIS)

Maretti Junior, F.; Amorim, V.A. de; Coura, J.G.

1986-01-01

The improvements done in the IPR-R1 reactor for adequateness of operation conditions and increase of irradiation sample capability. The cooling systems, reactor pool, system of control rods were substituted. The optimization of transfer pneumatic system was done. (M.C.K.) [pt

FiR 1 reactor in service for boron neutron capture therapy (BNCT) and isotope production

International Nuclear Information System (INIS)

Auterinen, I.; Salmenhaara, S.E.J. . Author

2004-01-01

The FiR 1 reactor, a 250 kW Triga reactor, has been in operation since 1962. The main purpose for the existence of the reactor is now the Boron Neutron Capture Therapy (BNCT), but FiR 1 has also an important national role in providing local enterprises and research institutions in the fields of industrial measurements, pharmaceuticals, electronics etc. with isotope production and activation analysis services. In the 1990's a BNCT treatment facility was built at the FiR 1 reactor located at Technical Research Centre of Finland. A special new neutron moderator material Fluental TM (Al+AlF3+Li) developed at VTT ensures the superior quality of the neutron beam. Also the treatment environment is of world top quality after a major renovation of the whole reactor building in 1997. Recently the lithiated polyethylene neutron shielding of the beam aperture was modified to ease the positioning of the patient close to the beam aperture. Increasing the reactor power to 500 kW would allow positioning of the patient further away from the beam aperture. Possibilities to accomplish a safety analysis for this is currently under considerations. Over thirty patients have been treated at FiR 1 since May 1999, when the license for patient treatment was granted to the responsible BNCT treatment organization, Boneca Corporation. Currently three clinical trial protocols for tumours in the brain as well as in the head and neck region are recruiting patients. (author)

Borated stainless steel storage project to the spent fuel of the IEA-R1 reactor

International Nuclear Information System (INIS)

Rodrigues, Antonio Carlos Iglesias; Madi Filho, Tufic; Ricci Filho, Walter

2013-01-01

The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks to the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating circumstances, the storage will have capacity for approximately six years. Whereas the estimated useful life of the IEA-R1 is around twenty years, it will be necessary to increase the storage capacity for the spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. This work objective is the project of high capacity storage for spent fuel elements, using borated stainless steel, to answer the Reactor IEA-R1 demand and the security requirements of the International Atomic Energy Agency. (author)

Borated stainless steel storage project to the spent fuel of the IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, Antonio Carlos Iglesias; Madi Filho, Tufic; Ricci Filho, Walter, E-mail: acirodri@ipen.br, E-mail: tmfilho@ipen.br, E-mail: wricci@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks to the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating circumstances, the storage will have capacity for approximately six years. Whereas the estimated useful life of the IEA-R1 is around twenty years, it will be necessary to increase the storage capacity for the spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. This work objective is the project of high capacity storage for spent fuel elements, using borated stainless steel, to answer the Reactor IEA-R1 demand and the security requirements of the International Atomic Energy Agency. (author)

IEA-R1 research reactor: operational life extension and considerations regarding future decommissioning

International Nuclear Information System (INIS)

Frajndlich, Roberto

2009-01-01

The IEA-R1 reactor is a pool type research reactor moderated and cooled by light water and uses graphite and beryllium reflectors. The reactor is located at the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), in the city of Sao Paulo, Brazil. It is the oldest research reactor in the southern hemisphere and one of the oldest of this kind in the world. The first criticality of the reactor was obtained on September 16, 1957. Given the fact that Brazil does not have yet a definitive radioactive waste repository and a national policy establishing rules for the spent fuel storage, the institutions which operate the research reactors for more than 50 years in the country have searched internal solutions for continued operation. This paper describes the spent fuel assemblies and radioactive waste management process for the IEA-R1 reactor and the refurbishment and modernization program adopted to extend its lifetime. Some considerations about the future decommissioning of the reactor are also discussed which, in my opinion, might help the operating organization to make decisions about financial, legal and technical aspects of the decommissioning procedures in a time frame of 10-15 years(author)

Thermodynamique statistique résumés de cours et problèmes résolus

CERN Document Server

Chahine, C

1976-01-01

Le présent ouvrage est conçu pour une initiation à la thermodynamique statistique en présentant un très grand nombre d'applications sous forme de problèmes résolus, et en donnant des résumés de cours constitués de l'essentiel des résultats théoriques nécessaires pour traiter les applications chaque fois qu'est abordé un nouveau domaine. Partant d'un niveau élémentaire et rédigé de façon très progressive, ce livre qui se suffit à lui-même, permet de saisir l'aspect physique des phénomènes, et de faire le lien entre les statistiques élémentaires et les statistiques de Gibbs. Le lecteur pourra, soit résoudre effectivement les problèmes sans avoir recours à la solution et tirer alors tout le bénéfice d'une recherche personnelle, soit lire l'ensemble de l'énoncé et de la solution qui sont très détaillés, et forment ainsi un exposé très clair. L'ouvrage, qui développe principalement l'aspect physique des phénomènes, intéresse les étudiants en physique dès la 1ère année ...

Bahia et la réponse du peuple

Directory of Open Access Journals (Sweden)

Tahar Chikhaoui

2013-12-01

Full Text Available Que disent les révolutions arabes sur le cinéma ? La question est d'autant plus intéressante que jamais dans le monde arabe l'image au sens large n'a joué un rôle aussi décisif dans les bouleversements socio-politiques. Les petites caméras ont servi d'armes contres les dictatures et l'impact de la diffusion à travers les réseaux sociaux des images prises par ces caméras a été considérable. L'histoire du cinéma semble, du coup, s'être accélérée. Rétrospectivement, les films engagés réalisés depuis les années 1970 se sont éloignés dans le temps et ceux plus personnels des années 1980, 1990 et 2000 paraissent complètement décalés par rapport à la réalité. En analysant de près les rapports secrets, complexes, toujours décalés entre le mode d'expression de l'art cinématographique et la logique de l'évolution des événements sociopolitiques, on se rend mieux compte des illusions d'optique déroutantes dues à l'accélération de l'histoire et à l'imbrication de plus en plus grande des facteurs politiques, sociaux, culturels et technologiques. Et en considérant de plus près la nature de l'évolution récente de l'histoire du monde arabe, de l'accélération des modes de représentation politique et culturelle, on réalise mieux la place du cinéma et la nécessaire distinction des types d'image en circulation, de leur nature, de leur fonction. Et de mieux cerner les enjeux futurs, en tout cas d'y « voir » plus clair.

Reliability database of IEA-R1 Brazilian research reactor: Applications to the improvement of installation safety

International Nuclear Information System (INIS)

Oliveira, P.S.P.; Tondin, J.B.M.; Martins, M.O.; Yovanovich, M.; Ricci Filho, W.

2010-01-01

In this paper the main features of the reliability database being developed at Ipen-Cnen/SP for IEA-R1 reactor are briefly described. Besides that, the process for collection and updating of data regarding operation, failure and maintenance of IEA-R1 reactor components is presented. These activities have been conducted by the reactor personnel under the supervision of specialists in Probabilistic Safety Analysis (PSA). The compilation of data and subsequent calculation are based on the procedures defined during an IAEA Coordinated Research Project which Brazil took part in the period from 2001 to 2004. In addition to component reliability data, the database stores data on accident initiating events and human errors. Furthermore, this work discusses the experience acquired through the development of the reliability database covering aspects like improvements in the reactor records as well as the application of the results to the optimization of operation and maintenance procedures and to the PSA carried out for IEA-R1 reactor. (author)

Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

International Nuclear Information System (INIS)

Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira

2015-01-01

Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira, E-mail: ecfoliveira@hotmail.com, E-mail: lazara.castrillo@upe.br [Universidade de Pernambuco (UPE), Recife, PE (Brazil). Escola Politecnica de Pernambuco

2015-07-01

Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (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

Adipokines : rôle dans l’obésité et l’insulino‐résistance

Directory of Open Access Journals (Sweden)

Aubert Roberte

2003-03-01

Full Text Available Le tissu adipeux longtemps considéré comme un organe de stockage est maintenant reconnu comme un organe endocrine. Cette revue étudie l’action de 3 adipokines sécrétées par le tissu adipeux et impliquées dans le contrôle de l’homéostasie énergétique et l’insulino‐résistance, la leptine, l’adiponectine et la résistine. La découverte de la leptine a permis la compréhension des mécanismes centraux de la prise alimentaire et de la dépense énergétique. L’espoir que la leptine puisse intervenir dans le traitement de l’obésité a été déçu, mais elle joue un rôle important dans l’insulino‐sensibilité. L’adiponectine circulante est diminuée dans l’obésité et la perte pondérale augmente son taux. Elle améliore la sensibilité à l’insuline en agissant sur le métabolisme glucidique et lipidique. Bien que pour le moment le rôle de la résistine soit encore mal défini, les études chez l’animal suggèrent qu’elle soit impliqués dans l’insulino‐résistance. Chez l’homme il n’y a pas de relation entre l’expression de la résistine et l’obésité. On peut donc se demander si la résistine, dans l’espèce humaine, est bien le lien entre obésité et diabète de type 2.

Measurements and calculations of reactivity for the IEA-R1 reactor

International Nuclear Information System (INIS)

Ferreira, P.S.B.; Maiorino, J.R.; Yamaguchi, M.

1988-01-01

This work shows a measurement of reactivity parameters, such as integral and diferential control rod worth, local void coefficient, and moderator temperature coefficient for the research reactor IEA-R1. The measured values were compared with those calculated through HAMMER-CITATION codes, having shown good agreement. (author) [pt

Safe dismantling of the SVAFO research reactors R2 and R2-0 in Sweden

International Nuclear Information System (INIS)

ARNOLD, Hans-Uwe; BROY, Yvonne; Dirk Schneider

2017-01-01

The R2 and R2-0 reactors were part of the Swedish government's research program on nuclear power from the early 1960's. Both reactors were shut down in 2005 following a decision by former operator Studsvik Nuclear AB. The decommissioning of the R2 and R2-0 reactors is divided into three phases. The first phase - awarded to AREVA - involved dismantling of the reactors and associated systems in the reactor pool, treatment of the disassembled components as well as draining, cleaning and emptying the pool. In the second phase, the pool structure itself will be dismantled, while removal of remaining reactor systems, treatment and disposal of materials and clean-up will be carried out in the third stage. The entire work is planned to be completed before the end of this decade. The paper describes the several steps of phase 1 - starting with the team building, followed by the dismantling operations and covers challenges encountered and lessons learned as well. The reactors consist of 5.400 kg aluminum, 6.000 kg stainless steel restraint structures as well as, connection elements of the mostly flanged components (1.000 kg). The most demanding - from a radiological point of view - was the R2-0 reactor that was limited to ∼ 1 m"3 construction volumes but with an extremely heterogeneous activation profile. Based on the calculated radiological entrance data and later sampling, nuclide vectors for both reactors depending on the real placement of the single component and on the material (aluminum and stainless steel) were created. Finally, for the highest activated component from R2 reactor, 85 Sv/h were measured. The dismantling principles - adopted on a safety point of view - were the following: The always protected base area of the ponds served as a flexible buffer area for waste components and packaging. Specific protections were also installed on the walls to protect them from mechanical stress which may occur during dismantling work. A specific work platform was

Feasibility study of application of Prompt Gamma Neutron Activation Analysis (PGNAA) method in TRIGA IPR-R1 reactor

International Nuclear Information System (INIS)

Guerra, Bruno Teixeira

2016-01-01

The TRIGA Mark I IPR-R1 research reactor is located at Nuclear Technology Development Centre (CDTN), Brazilian Commission for Nuclear Energy (CNEN), in Belo Horizonte, Brazil. The reactor operates at 100 kW but the core configuration allows the increasing of the power up to 250 kW. It has been applied research, training and radioisotopes production. The establishment of the Prompt Gamma Neutron Activation Analysis (PGNAA) method at the TRIGA IPR-R1 reactor will significantly increase the types of matrices analysed as well as the number of chemical elements. Additionally it will complement the neutron activation analysis. This work presents a proposed design of a PGNAA facility to be installed at the TRIGA IPR-R1. The proposed design is based on a tube as a neutron guide from the reactor core, inside the reactor pool, 6 m below the room’s level where shall be located the rack containing the set sample/detector/shielding. Thus, the aim of this study is to verify the feasibility to establish the PGNAA method in IPR-R1 through theoretical study applying the Monte Carlo code. The feasibility of establishing the PGAA method at the IPR-R1 installations was evaluated through of the calculations of neutron flux, radioactive capture reaction rates and detection limits for some isotopes. According to the obtained results, it can be concluded that is possible to establish the PGAA method at the IPR-R1 reactor, even with some restrictions in its theoretical design calculated by MCNP. (author)

Digital Systems Implemented at the IPEN Nuclear Research Reactor (IEA-R1): Results and Necessities

International Nuclear Information System (INIS)

Nahuel-Cardenas, Jose-Patricio; Madi-Filho, Tufic; Ricci-Filho, Walter; Rodrigues-de-Carvalho, Marcos; Lima-Benevenuti, Erion-de; Gomes-Neto, Jose

2013-06-01

(Nuclear and Energy Research Institute) was founded in 1956 with the main purpose of doing research and development in the field of nuclear energy and its applications. It is located at the campus of University of Sao Paulo (USP), in the city of Sao Paulo, in an area of nearly 500, 000 m2. It has over 1.000 employees and 40% of them have qualification at master or doctor level The institute is recognized as a national leader institution in research and development (R and D) in the areas of radiopharmaceuticals, industrial applications of radiation, basic nuclear research, nuclear reactor operation and nuclear applications, materials science and technology, laser technology and applications. Along with the R and D, it has a strong educational activity, having a graduate program in Nuclear Technology, in association with the University of Sao Paulo, ranked as the best university in the country. The Federal Government Evaluation institution CAPES, granted to this course grade 6, considering it a program of Excellence. This program started at 1976 and has awarded 458 Ph.D. degrees and 937 master degrees since them. The actual graduate enrollment is around 400 students. One of major nuclear installation at IPEN is the IEA-R1 research reactor; it is the only Brazilian research reactor with substantial power level suitable for its utilization in researches concerning physics, chemistry, biology and engineering as well as for producing some useful radioisotopes for medical and other applications. IEA-R1 reactor is a swimming pool type reactor moderated and cooled by light water and uses graphite and beryllium as reflectors. The first criticality was achieved on September 16, 1957. The reactor is currently operating at 4.5 MW power level with an operational schedule of continuous 64 hours a week. In 1996 a Modernization Program was started to establish recommendations in order to mitigate equipment and structures ageing effects in the reactor components, detect and evaluate

Evaluation of power behavior during startup and shutdown procedures of the IPR-R1 Triga Reactor

International Nuclear Information System (INIS)

Zangirolami, Dante M.; Mesquita, Amir Z.; Ferreira, Andrea V.

2009-01-01

The IPR-R1 nuclear reactor of Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN is a TRIGA Mark I pool type reactor cooled by natural circulation of light water. In the IPR-R1, the power is measured by four nuclear channels, neutron-sensitive chambers, which are mounted around the reactor core: the Startup Channel for power indication during reactor startup; the Logarithmic Wide Range Power Monitoring Channel; the Linear Multi-Range Power Monitoring Channel and the Percent Power Safety Channel. A data acquisition system automatically does the monitoring and storage of all the reactor operational parameters including the reactor power. The startup procedure is manual and the time to reach the desired reactor power level is different on each irradiation which may introduces differences in induced activity of samples irradiated in different irradiations. In this work, the power evolution during startup and shutdown periods of IPR-R1 operation was evaluated and the mean values of reactor energy production in these operational phases were obtained. The analyses were performed on basis of the Linear Multi-Range Channel data. The results show that the sum of startup and shutdown periods corresponds to 1% of released energy for irradiations during 1h at 100kW. This value may be useful to correct experimental data in neutron activation experiments. (author)

Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model

International Nuclear Information System (INIS)

Costa, Antonella L.; Reis, Patricia Amelia L.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Mesquita, Amir Z.; Soares, Humberto V.

2010-01-01

The RELAP5 code is widely used for thermal hydraulic studies of commercial nuclear power plants. Current investigations and code adaptations have demonstrated that the RELAP5 code can be also applied for thermal hydraulic analysis of nuclear research reactors with good predictions. Therefore, as a contribution to the assessment of RELAP5/MOD3.3 for research reactors analysis, this work presents steady-state and transient calculation results performed using a RELAP5 model to simulate the IPR-R1 TRIGA research reactor at 50 kilowatts (kW) of power operation. The reactor is located in the Nuclear Technology Development Center (CDTN), Brazil. It is a 250 kW, light water moderated and cooled, graphite-reflected, open pool type research reactor. The development and the assessment of a RELAP5 model for the IPR-R1 TRIGA are presented. Experimental data were considered in the process of the RELAP5 model validation. The RELAP5 results were also compared with calculated data from the STHIRP-1 (Research Reactors Thermal Hydraulic Simulation) code. The results obtained have shown that the RELAP5 model for the IPR-R1 TRIGA reproduces the actual steady-state reactor behavior in good agreement with the available data.

Qualité et obligations de résultats

CERN Document Server

Guthapfel, C

1998-01-01

Un contrat de maintenance peut appartenir à deux grands types ; ceux où la prestation est définie par son contenu ou par son résultat. Dans l'exemple retenu, le résultat est exprimé principalement en terme d'état de référence à maintenir ; ce qui nécessite de définir préalablement l'état requis par rapport aux besoins exprimés ou implicites et l'écart toléré d'où une meilleure définition du besoin. Cette approche qualité responsabilise de manière plus complète le contractant par une facilité accrue de mesurer la conformité au besoin et la preuve de manquements aux obligations contractuelles est plus aisée à établir. Il faut toutefois noter un décalage entre les besoins exprimés et ressentis et la difficulté d'apprécier objectivement les résultats, d'où la nécessité d'améliorer et de formaliser les relations client/fournisseur. C'est uniquement sur ces bases que le partenariat, condition indispensable de l'efficience, peut se développer et les besoins être satisfaits au m...

Conceptual designs of tokamak reactor and R D

International Nuclear Information System (INIS)

Fukai, Yuzo; Yamato, Harumi; Sawada, Yoshio

1983-01-01

The conceptual design of both FER (Fusion Experimental Reactor) and R-project is now under way as the new step of JT-60. From the engineering viewpoint, these reactors, requiring D-T operation, have the challenge, such as the handling of tritium and components irradiated by neutron bombardment. Toshiba's design team is participating to these projects in order to realize the reactor and plant concept coping with the above objectives. This paper represents the conceptual design contributions of the FER and R-project as well as R D technology which are now under development, such as tritium handling app aratus, reactor materials, etc. (author)

Experience gained in refurbishing of the ET-R R-1 reactor in Egypt

Energy Technology Data Exchange (ETDEWEB)

Khattab, M; Dimitri, F; Chaath, K [Reactor department, nuclear research center atomic energy authority, Cairo, (Egypt)

1995-10-01

This paper describes the in-service program and rehabilitation plan of the control, measuring instrumentation and radiation monitoring equipment as well as the computerized safety logic and signaling systems. the in-service program includes reactor core and pressure vessels. Spent fuel tank and primary cooling circuit have been inspected. Current problems and future plan for improving the safety systems are discussed. 10 figs., 1 tab.

Experience gained in refurbishing of the ET-R R-1 reactor in Egypt

International Nuclear Information System (INIS)

Khattab, M.; Dimitri, F.; Chaath, K.

1995-01-01

This paper describes the in-service program and rehabilitation plan of the control, measuring instrumentation and radiation monitoring equipment as well as the computerized safety logic and signaling systems. the in-service program includes reactor core and pressure vessels. Spent fuel tank and primary cooling circuit have been inspected. Current problems and future plan for improving the safety systems are discussed. 10 figs., 1 tab

Design of a new wet storage rack for spent fuels from IEA-R1 reactor

International Nuclear Information System (INIS)

Rodrigues, Antonio C.I.; Madi Filho, Tufic; Siqueira, Paulo T.D.; Ricci Filho, Walter

2015-01-01

The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks of the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating conditions, the storage will have capacity for about six years. Since the estimated useful life of the IEA-R1 is about another 20 years, it will be necessary to increase the storage capacity of spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. After an extensive literature review of material options given for this type of application we got to Boral® manufactured by 3M due to numerous advantages. This paper presents studies on the analysis of criticality using the computer code MCNP 5, demonstrating the possibility of doubling the storage capacity of current racks to attend the demand of the IEA-R1 reactor while attending the safety requirements the International Atomic Energy Agency. (author)

Design of a new wet storage rack for spent fuels from IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, Antonio C.I.; Madi Filho, Tufic; Siqueira, Paulo T.D.; Ricci Filho, Walter, E-mail: acirodri@ipen.br, E-mail: tmfilho@ipen.br, E-mail: ptsiquei@ipen.br, E-mail: wricci@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks of the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating conditions, the storage will have capacity for about six years. Since the estimated useful life of the IEA-R1 is about another 20 years, it will be necessary to increase the storage capacity of spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. After an extensive literature review of material options given for this type of application we got to Boral® manufactured by 3M due to numerous advantages. This paper presents studies on the analysis of criticality using the computer code MCNP 5, demonstrating the possibility of doubling the storage capacity of current racks to attend the demand of the IEA-R1 reactor while attending the safety requirements the International Atomic Energy Agency. (author)

Aspects of the Iea-R1 research reactor seismic evaluation

International Nuclear Information System (INIS)

Mattar Neto, Miguel

1996-01-01

Codes and standards for the seismic evaluation of the research reactor IEA-R1 are presented. An approach to define the design basis earthquake based on the local seismic map and on simplified analysis methods is proposed. The site seismic evaluation indicates that the design earthquake intensity is IV MM. Therefore, according to the used codes and standards, no buildings, systems, and components seismic analysis are required. (author)

Commissioning of the new heat exchanger for the research nuclear reactor IEA-R1

Energy Technology Data Exchange (ETDEWEB)

Castro, Alfredo Jose Alvim de; Cassiano, Douglas Alves; Umbehaun, Pedro Ernesto; Carvalho, Marcos Rodrigues de; Frajndlich, Roberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mails: ajcastro@ipen.br; docass@gmail.com.br; umbehaun@ipen.br; carvalho@ipen.br; frajndli@ipen.br

2008-07-01

The Research Reactor IEA-R1 placed at IPEN/CNEN-SP is of the swimming pool type, light water moderated and with graphite reflectors, and was build and designed by Babcock and Wilcox Co. Start up operation was in September the 16{sup th}, 1957, being the first criticality for South Hemisphere. Although designed to operate at 5 MW, the IEA-R1 was operated until 2001 with 2 MW and was suitable for use in basic and applied research as well as the production of medical radioisotopes, industry and natural sciences applications. Due to a recent demand increase on radioisotopes in Brazil for medical diagnoses and therapies applications, IPEN /CNEN updated the IEA-R1 power to 5 MW and to work at continuous operation regime. Studies on the Ageing Management for the Research Reactor IEA-R1 were conducted according to IAEA procedures. As result of these studies critical components within the Ageing Management Program were identified. Also were made recommendations on the implementation of test scheduling and standardization procedures to organize data and documents. One of the main results was the need of monitoring the two heat exchangers, the two primary circuit pumps and the data acquisition system. During monitoring procedures, issues were observed on the IEA-R1 operation at 5 MW mainly due to the ageing of the Babcox and Wilcox TCA heat exchanger, and excessive vibrations at high flow rates on CBC's TCB heat exchanger. So, from 2005 on, it was decided to work with 3,5 MW and provide a new IESA heat exchanger with 5 MW capacity, to substitute the TCA heat exchanger. This work presents results on the commissioning of the new heat exchanger and compares against the values calculated in the IESA project. The results show that the IEA-R1 Reactor can be operated more safety and continuously at 5 MW with the new IESA heat exchanger. (author)

4D Art: corps réels et virtuels, une réalité augmentée

Directory of Open Access Journals (Sweden)

Michel Lemieux

2016-05-01

Full Text Available La compagnie canadienne 4D Art surprend le regard du public et interroge les sens de réalité et présence, par l’interaction scénique de corps réels et virtuels en mouvement. Pour comprendre le processus créateur des spectacles de 4D Art, on présente un entretien inédit réalisé avec les directeurs artistiques Michel Lemieux et Victor Pilon. Les motivations artistiques du jeu réel et virtuel, les procédés employés dans la création des figures virtuelles et les défis vécus par les acteurs sont exposés par les créateurs.

Modernization of the CDTN IPR-R1 TRIGA reactor instrumentation and control

International Nuclear Information System (INIS)

Mesquita, A.Z.; Costa, A.C.L.; Souza, R.M.G.P.

2009-01-01

The control system of the IPR-R1 was changed in 1995. Although since the year's 80 was generalized the use of microprocessor technology and video monitors for visual interface, in the IPR-R1 control room it was used analogical system by relay-based logic, and were maintained the mechanical strip chart recorders (ink-pen drive) to measure, monitor and store the operational parameters. It was maintained the measure and the control of, practically, the same variables of the original system, although the reactor power already have been upgraded to 100 kW and began the studies to increase it to 250 kW, which is the current core configuration. For 250 kW operations the fuel heat transfer becomes important and new parameters should be used as safety operational limits. A state-of-the-art instrumentation and control system using microprocessor technology is proposed to replace the present analogical systems. The new system can eliminates most manual data logging, provides automatic or manual reactor operation modes, provides complete real-time operator display, replays historical operating data on monitor or printer, eliminates spare parts replacement problems and meets all applicable international standards as NRC and IEE specifications. This paper describes the research project in process in CDTN that has as objective the modernization of the IPR-R1 TRIGA reactor instrumentation and control of the operational variables. The project also will improve the accomplishment of neutronic and thermal-hydraulic experiments, foreseen in the CDTN research program. (author)

Core calculations for the upgrading of the IEA-R1 research reactor

International Nuclear Information System (INIS)

Santos, Adimir dos; Perrotta, Jose A.; Bastos, Jose Luis F.; Yamaguchi, Mitsuo; Umbehaun, Pedro E.

1998-01-01

The IEA-R1 Research Reactor is a multipurpose reactor. It has been used for basic and applied research in the nuclear area, training and radioisotopes production since 1957. In 1995, the Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP) took the decision to modernize and upgrade the power from 2 to 5 MW and increase the operational cycle. This work presents the design requirements and the calculations effectuated to reach this goal. (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

Development of a training simulator to operators of the IEA-R1 research reactor

International Nuclear Information System (INIS)

Carvalho, Ricardo Pinto de

2006-01-01

This work reports the development of a Simulator for the IEA-R1 Research Reactor. The Simulator was developed with Visual C++ in two stages: construction of the mathematics models and development and configuration of graphics interfaces in a Windows XP executable. A simplified modeling was used for main physics phenomena, using a point kinetics model for the nuclear process and the energy and mass conservation laws in the average channel of the reactor for the thermal hydraulic process. The dynamics differential equations were solved by using finite differences through the 4th order Runge- Kutta method. The reactivity control, reactor cooling, and reactor protection systems were also modeled. The process variables are stored in ASCII files. The Simulator allows navigating by screens of the systems and monitoring tendencies of the operational transients, being an interactive tool for teaching and training of IEA-R1 operators. It also can be used by students, professors, and researchers in teaching activities in reactor and thermal hydraulics theory. The Simulator allows simulations of operations of start up, power maneuver, and shut down. (author)

Adam Smith et le “républicanisme”

Directory of Open Access Journals (Sweden)

Alexandra HYARD

2003-10-01

Full Text Available Je remercie Pierre Lurbe et Ann Thomson pour leurs remarques. Je tiens également à remercier Thierry Demals pour son aide précieuse. Néanmoins, je reste seule responsable des éventuelles erreurs contenues dans ce travail.Introduction Smith semble avoir toujours été en théorie un républicain, et il a sûrement eu le vrai esprit d’un républicain dans son amour de toute liberté rationnelle. (Rae 124 Par cette phrase, Rae nous livre son opinion sur une des questions relatives à Adam Smith (1723-1...

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)

Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor

International Nuclear Information System (INIS)

Reis, Patricia A.L.; Costa, Antonella L.; Pereira, Claubia; Veloso, Maria A.F.; Mesquita, Amir Z.; Soares, Humberto V.

2010-01-01

RELAP5 code was developed at the Idaho National Environmental and Engineering Laboratory and it is widely used for thermal hydraulic studies of commercial nuclear power plants and, currently, it has been also applied for thermal hydraulic analysis of nuclear research systems with good predictions. This work is a contribution to the assessment of RELAP5/3.3 code for research reactors analysis. It presents steady-state and transient calculation results performed using a RELAP5 model to simulate the IPR-R1 TRIGA research reactor conditions operating at 50 and 100 kW. The reactor is located at the Nuclear Technology Development Centre (CDTN), Brazil. The development and the assessment of a RELAP5 model for the IPR-R1 TRIGA are presented. Experimental data were considered in the process of code-to-data validation. The RELAP5 results were also compared with calculation performed using the STHIRP-1 (Research Reactors Thermal Hydraulic Simulation) code. The use of a cross flow model has been essential to improve results in the transient condition respect to preceding investigations.

Verification of the linearity of the IPR-R1 TRIGA reactor power channels

International Nuclear Information System (INIS)

Souza, Rose Mary Gomes do Prado; Campolina, Daniel de Almeida Magalhaes

2013-01-01

The aim of this paper is to verify the linearity of the three power channels of the IPR-R1 TRIGA reactor. Located at Nuclear Technology Development Center-CDTN in Belo Horizonte, the IPR-R1 reactor is a typical 100 kW Mark I light-water reactor cooled by natural convection. When the experiments were performed, the reactor core had 59 fuel elements, containing 8% by weight of uranium enriched to 20% in 235 U. The core has cylindrical configuration with an annular graphite reflector. The responses of the detectors of the Linear, Log N and Percent Power channels were compared with the responses of detectors which only depend on the overall neutron flux within the reactor. Gold and cobalt foils were activated at low and high powers, respectively, and the specific count results were compared with measurements performed, simultaneously, with a fission chamber, and with the power registered by the three channels. The results show that the Linear channel responds linearly up to 100 kW, and the Log N channel responses are linear at low powers. In the range of high power, the Log N and the Percent Power channels exhibit linearity only from 10 kW to 50 kW. (author)

Experiment on continuous operation of the Brazilian IEA-R1 research reactor

International Nuclear Information System (INIS)

Freitas Pintaud, M. de

1994-01-01

In order to increase the radioisotope production in the IEA-R1 research reactor at IPEN/CNEN-SP, it has been proposed a change in its operation regime from 8 hours per day and 5 days per week to continuous 48 hours per week. The necessary reactor parameters for this new operation regime were obtained through an experiment in which the reactor was for the first time operated in the new regime. This work presents the principal results from this experiment: xenon reactivity, new shutdown margins, and reactivity loss due to fuel burnup in the new operation regime. (author)

Auxiliary control system of the safety parameters for IPR-R1 reactor

International Nuclear Information System (INIS)

Coura, J.G.

1986-01-01

This paper deals with the description for the control of three cooling water parameters (conductivity, temperature and the maximum and minimum water levels) as well as the percent power fraction of the nuclear research reactor IPR-R1. In order to keep the reactor in good operation conditions, one permanent and accurate control of the cooling water is needed. The double monitoring of a fourth parameter, part of the original design, the percent power fraction, is obtained through the control of the uncompensated ion chamber current and aims to avoid the operation of the reactor without running the cooling system. (Author) [pt

Penser et activer les relations entre cartes et récits

Directory of Open Access Journals (Sweden)

SÉBASTIEN CAQUARD

2015-03-01

Full Text Available De prime abord, récit et carte semblent en opposition directe. Le récit offre un point de vue partiel et personnel, souvent chronologique et intimement associé à une trame narrative structurée autour d’évènements vécus, imaginés ou remémorés par un sujet concret engagé dans un cheminement. La carte s’ingénie à présenter de manière synthétique et abstraite des données quantifiables à partir d’un point distant, figé dans le temps, dépersonnalisé et aérien.

Measurements and calculation of reactivity in the IEA-R1 nuclear reactor

International Nuclear Information System (INIS)

Ferreira, P.S.B.

1988-01-01

Techniques and experimentals procedures utilized in the measurement of some nuclear parameters related to reactivity are presented. Measurements of reactivity coefficients, such as void, temperature and power, and control rod worth were made in the IEA-R1 Research Reactor. The techniques used to perform the measurements were: i) stable period (control rod calibration), ii) inverse kinetics (digital reactivity meter), iii) aluminium slab insertion in the fuel element coolant channels (void reactivity), iv) nuclear reactor core temperature changes by means of the changes in the coolant systems of reactor core (isothermal reactivity coefficient) and v) by making perturbation in the core through the control rod motions (power reactivity coefficient and control rod calibration). By using the computer codes HAMMER, HAMMER-TECHNION and CITATION, the experiments realized in the IEA-R1 reactor were simulated. From this simulation, the theoretical reactivity parameters were estimated and compared with the respective experimental results. Furthermore, in the second fuel load of Angra-1 Nuclear Power Station, the IPEN-CNEN/SP digital reactivity - meter were used in the lower power test with the aim to assess the equipment performance. Among several tests, the reacticity-meter were used in parallel with a Westinghouse analogic reativimeter-meter) to measure the heat additiona point, critical boron concentration, control rod calibration, isothermal and moderator reactivity coefficient. These tests, and the results obtained by the digital reactivity-meter are described. The results were compared with those obtained by Westinghouse analogic reactivity meter, showing excellent agreement. (author) [pt

Experimental study of the temperature distribution in the TRIGA IPR-R1 Brazilian research reactor

International Nuclear Information System (INIS)

Mesquita, Amir Zacarias

2005-01-01

The TRIGA-IPR-R1 Research Nuclear Reactor has completed 44 years in operation in November 2004. Its initial nominal thermal power was 30 kW. In 1979 its power was increased to 100 kW by adding new fuel elements to the reactor. Recently some more fuel elements were added to the core increasing the power to 250 kW. The TRIGA-IPR-R1 is a pool type reactor with a natural circulation core cooling system. Although the large number of experiments had been carried out with this reactor, mainly on neutron activation analysis, there is not many data on its thermal-hydraulics processes, whether experimental or theoretical. So a number of experiments were carried out with the measurement of the temperature inside the fuel element, in the reactor core and along the reactor pool. During these experiments the reactor was set in many different power levels. These experiments are part of the CDTN/CNEN research program, and have the main objective of commissioning the TRIGA-IPR-R1 reactor for routine operation at 250 kW. This work presents the experimental and theoretical analyses to determine the temperature distribution in the reactor. A methodology for the calibration and monitoring the reactor thermal power was also developed. This methodology allowed adding others power measuring channels to the reactor by using thermal processes. The fuel thermal conductivity and the heat transfer coefficient from the cladding to the coolant were also experimentally valued. lt was also presented a correlation for the gap conductance between the fuel and the cladding. The experimental results were compared with theoretical calculations and with data obtained from technical literature. A data acquisition and processing system and a software were developed to help the investigation. This system allows on line monitoring and registration of the main reactor operational parameters. The experiments have given better comprehension of the reactor thermal-fluid dynamics and helped to develop numerical

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)

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

Camps de réfugiés et environnement au Kenya : enjeux et contradictions

OpenAIRE

Cambrézy, Luc

2001-01-01

Dans les camps de réfugiés de Dadaab, au Kenya, un programme de protection environnementale et de réhabilitation du couvert végétal a été mis en place plusieurs années avant tout réel diagnostic sur l'ampleur et l'origine réelle des dégradations constatées. Des études ultérieures ont montré que les auréoles de dégradation autour des camps semblent essentiellement imputables aux besoins ligneux pour la construction et la maintenance des nombreuses infrastructures et non pas à la collecte de bo...

SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

Energy Technology Data Exchange (ETDEWEB)

Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

2009-12-03

The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

The Swedish Zero Power Reactor R0

Energy Technology Data Exchange (ETDEWEB)

Landergaard, Olof; Cavallin, Kaj; Jonsson, Georg

1961-05-15

The reactor R0 is a critical facility built for heavy water and natural uranium or fuel of low enrichment,, The first criticality was achieved September 25, 1959. During a first period of more than two years the R0 will be operated as a bare reactor in order to simplify interpretation of results. The reactor tank is 3. 2 m high and 2. 25 m in diameter. The fuel suspension system is quite flexible in order to facilitate fuel exchange and lattice variations. The temperature of the water can be varied between about 10 and 90 C by means of a heater and a cooler placed in the external circulating system. The instrumentation of the reactor has to meet the safety requirements not only during operation but also during rearrangements of the core in the shut-down state. Therefore, the shut-down state is always defined by a certain low 'safe' moderator level in the reactor tank. A number of safety rods are normally kept above the moderator ready for action. For manual or automatic control of the reactor power a specially designed piston pump is needed, by which the moderator level is varied. The pump speed is controlled from the reactor power error by means of a Ward-Leonard system. Moderator level measurement is made by means of a water gauge with an accuracy of {+-} 0. 1 mm.

The Swedish Zero Power Reactor R0

International Nuclear Information System (INIS)

Landergaard, Olof; Cavallin, Kaj; Jonsson, Georg

1961-05-01

The reactor R0 is a critical facility built for heavy water and natural uranium or fuel of low enrichment,, The first criticality was achieved September 25, 1959. During a first period of more than two years the R0 will be operated as a bare reactor in order to simplify interpretation of results. The reactor tank is 3. 2 m high and 2. 25 m in diameter. The fuel suspension system is quite flexible in order to facilitate fuel exchange and lattice variations. The temperature of the water can be varied between about 10 and 90 C by means of a heater and a cooler placed in the external circulating system. The instrumentation of the reactor has to meet the safety requirements not only during operation but also during rearrangements of the core in the shut-down state. Therefore, the shut-down state is always defined by a certain low 'safe' moderator level in the reactor tank. A number of safety rods are normally kept above the moderator ready for action. For manual or automatic control of the reactor power a specially designed piston pump is needed, by which the moderator level is varied. The pump speed is controlled from the reactor power error by means of a Ward-Leonard system. Moderator level measurement is made by means of a water gauge with an accuracy of ± 0. 1 mm

Use of self powered neutron detectors in the IEA-R1 reactor

International Nuclear Information System (INIS)

Galo Rocha, F. del.

1989-01-01

A survey of self-powered neutron detectors, SPND, which are used as part of the in-core instrumentation of nuclear reactors is presented. Measurements with Co and Er SPND's were made in the IEA-R1 reactor for determining the neutron flux distribution and the integral reactor power. Due to the size of the available detectors, the neutron flux distribution could not be obtained with accuracy. The results obtained in the reactor power measurements demonstrate that the SPND have the linearity and the quick response necessary for a reactor power channel. This work also presents a proposed design of a SPND using Pt as wire emissor. This proposed design is based in the experience gained in building two prototypes. The greatest difficulties encountered include materials and technology to perform the delicate weldings. (author)

Applications of neutron activation analysis technique in the IPR-R1 research reactor

International Nuclear Information System (INIS)

Sabino, C.V.S.; Mansur, N.

1986-01-01

A review is made of the neutron activation analysis technique used in the IPR-R1 reactor of the Centro de Desenvolvimento da Tecnologia Nuclear - NUCLEBRAS. Some characteristics of the method are described, types of samples and elements analyzed are also mentioned. (Author) [pt

Calculation of radiation heat generation on a graphite reflector side of IAN-R1 Reactor

International Nuclear Information System (INIS)

Duque O, J.; Velez A, L.H.

1987-01-01

Calculation methods for radiation heat generation in nuclear reactor, based on the point kernel approach are revisited and applied to the graphite reflector of IAN-R1 reactor. A Fortran computer program was written for the determination of total heat generation in the reflector, taking 1155 point in it

Current utilization and long term strategy of the Finnish TRIGA research reactor FiR 1

International Nuclear Information System (INIS)

Auterinen, Iiro; Salmenhaara, Seppo

2008-01-01

FiR 1 (TRIGA Mark II, 250 kW) has an important international role in the development of boron neutron capture therapy (BNCT) for cancer. The safety and efficacy of BNCT is studied for several different cancers: - primary glioblastoma, a highly malignant brain tumour (since 1999); - recurrent glioblastoma or anaplastic astrocytoma (since 2001); - recurrent inoperable head and neck carcinoma (since 2003). It is one of the few facilities in the world providing this kind of treatments. The successes in the BNCT development have now created a demand for these treatments, although they are given on an experimental basis. Well over 100 patients treated now since May 1999: - at least 1 patient irradiation / week, often 2 (Tuesday and Thursday) - patients are referred to BNCT-treatments from several hospitals, also outside research protocols; - the hospitals pay for the treatment. The FiR 1 reactor has proven to be a reliable neutron source for the BNCT treatments; no patient irradiations have been cancelled because of a failure of the reactor. The BNCT facility has become a center of extensive academic research especially in medical physics. Nuclear education and training continue to play also a role at FiR 1 in the form of university courses and training of nuclear industry personnel. FiR 1 is one of the two sources in Scandinavia for short lived radioisotopes used in tracer studies in industry. The main isotope produced is Br-82 in the form of either KBr or ethylene bromide. Other typical isotopes are Na-24, Ar-41, La-140. The isotopes are used mainly in tracer studies in industry (Indmeas Inc., Finland). Typical activity of one irradiated Br-sample is 20 - 80 GBq; total activity produced in one year is over 3 TBq; the reactor operating time needed for the isotope production is one or two days per week. Accelerator based neutron sources are developed for BNCT. The prospect is that when BNCT will achieve a status of a fully accepted and efficient treatment modality for

Le rêve deleuzien et le réveil analytique

OpenAIRE

Clémot, Hugo

2016-01-01

L’usage quasi-exclusif des concepts de Gilles Deleuze en études cinématographiques donne parfois l’impression que la philosophie du cinéma s’est endormie il y a une trentaine d’années en rêvant d’« images-mouvement » et de « cristaux de temps ». En vue de réveiller les chercheurs de leur sommeil dogmatique, le texte voudrait faire connaître certaines des raisons qui rendent les philosophes analytiques du cinéma sceptiques à l’encontre de la démarche du grand philosophe français. The excess...

Contrôle, régulation et sécurité en temps réel des ouvrages

Directory of Open Access Journals (Sweden)

ROYET, Paul

2016-09-01

Full Text Available La gestion patrimoniale des infrastructures, au plan opérationnel, inclut une surveillance des ouvrages en temps réel, en lien fort avec le contrôle et la régulation de leur fonctionnement, afin d'assurer la sécurité des usagers et de l'environnement. Cet article présente les principes et méthodes qui sous-tendent les actions au pas de temps fin pour des patrimoines tels que les digues, les barrages et les réseaux d'eau et d'assainissement et montre comment ces actions contribuent de manière déterminante à la connaissance de l'état du patrimoine.

Méthodologie de l'extrapolation des réacteurs chimiques Methodology for Scaling Up Chemical Reactors

Directory of Open Access Journals (Sweden)

Trambouze P.

2006-11-01

Full Text Available Après un exposé général relatif à la méthodologie du développement des procédés, applicable à l'extrapolation des réacteurs, est présenté un rapide examen critique des deux principales techniques mises en oeuvre, à savoir : - la théorie de la similitude ; - l'élaboration de modèles mathématiques. Deux exemples pratiques, relatifs aux réacteurs homogènes et aux réacteurs catalytiques à lit fixe et deux phases fluides, sont ensuite examinés à la lumière des considérations générales précédentes. After giving a general description of process-development methodology applicable to scaling up reactors, this article makes a quick critical examination of the two main techniques involved, i. e. : (a the theory of similarity, and (b the compiling of mathematical models. Two practical examples relating to homogeneous reactors and trickle-bed catalytic reactors are then examined in the light of the preceding general considerations.

25th birthday of the first criticality of IPR-R1 nuclear research reactor

International Nuclear Information System (INIS)

Tofani, P.C.; Stasiulevicius, R.; Roedel, G.

1988-01-01

The historical evolution of IPR-R1 research reactor of Instituto de Pesquisas Radioativas-Nuclebras, since the data of its first criticality, is presented. The modifications and the main activities carried out, are presented. (M.C.K.) [pt

Upgrading the electrical system of the IEA-R1 reactor to avoid triggering event of accidents

International Nuclear Information System (INIS)

Mello, Jose Roberto de; Madi Filho, Tufic

2015-01-01

The IEA-R1 research reactor at the Institute of Energy and Nuclear Research (IPEN) is a research reactor open pool type, built and designed by the American firm 'Babcox and Wilcox', having as coolant and moderator demineralized light water and Beryllium and graphite, as reflectors. The power supply system is designed to meet the electricity demand required by the loads of the reactor (Security systems and systems not related to security) in different situations the plant can meet, such as during startup, normal operation at power, shutdown, maintenance, exchange of fuel elements and accident situations. Studies have been done on possible accident initiating events and deterministic techniques were applied to assess the consequences of such incidents. Thus, the methods used to identify and select the accident initiating events, the methods of analysis of accidents, including sequence of events, transient analysis and radiological consequences, have been described. Finally, acceptance criteria of radiological doses are described. Only a brief summary of the item concerning loss of electrical power will be presented. The loss of normal electrical power at the IEA-R1 reactor is very common. In the case of Electric External Power Loss, at the IEA-R1 reactor building, there may be different sequences of events, as described below. When the supply of external energy in the IEA-R1 facility fails, the Electrical Distribution Vital System, consisting of 4 (four) generators type 'UPS', starts operation, immediately and it will continue supplying power to the reactor control table, core cooling system and other security systems. To contribute to security, in the electric power failure, starts to operate the Emergency Cooling System (SRE). SRE has the function of removing residual heat from the core to prevent the melting of fuel elements in the event of loss of refrigerant to the core. Adding to the generators with batteries group system, new auxiliary

Supervisory system to monitor the neutron flux of the IPR-R1 TRIGA research reactor at CDTN

International Nuclear Information System (INIS)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Tello, Cledola Cassia Oliveira

2009-01-01

The IPR-R1 TRIGA Mark I nuclear research reactor at the Nuclear Technology Development Center - CDTN (Belo Horizonte) is a pool type reactor. It was designed for research, training and radioisotope production. The International Atomic Energy Agency- IAEA - recommends the use of friendly interfaces for monitoring and controlling the operational parameters of nuclear reactors. This paper reports the activities for implementing a supervisory system, using LabVIEW software, with the purpose to provide the IPR-R1 TRIGA research reactor with a modern, safe and reliable system to monitor the time evolution of the power of its core. The use of the LabVIEW will introduce modern techniques, based on electronic processor and visual interface in video monitor, substituting the mechanical strip chart recorders (ink-pen drive and paper) that monitor the current neutrons flux, which is proportional to the thermal power supplied by reactor core. The main objective of the system will be to follow the evolution of the neutronic flux originated in the Linear and Logarithmic channels. A great advantage of the supervisory software nowadays, in relation to computer programs currently used in the facility, is the existence of new resources such as the data transmission and graphical interfaces by net, grid lines display in the graphs, and resources for real time reactor core video recordings. The considered system could also in the future be optimized, not only for data acquisition, but also for the total control of IPR-R1 TRIGA reactor(author)

Thermal hydraulic and neutron kinetic coupled simulation of the IPR-R1 Triga reactor

Energy Technology Data Exchange (ETDEWEB)

Reis, Patricia A.L.; Costa, Antonella L.; Pereira, Claubia; Silva, Clarysson A.M. da; Veloso, Maria Auxiliadora F.; Soares, Humbero V., E-mail: patricialire@yahoo.com.br, E-mail: antonella@nuclear.ufmg.br, E-mail: claubia@nuclear.ufmg.br, E-mail: clarysson@nuclear.ufmg.br, E-mail: dora@nuclear.ufmg.br, E-mail: betovitor@ig.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Instituto Nacional de Ciencias e Tecnologia de Reatores Nucleares Inovadores (INCT/CNPq Rede), Rio de Janeiro, RJ (Brazil)

2013-07-01

The nuclear industry and the scientific community have turned the attention for the development of coupled 3D neutron kinetics (NK) and thermal-hydraulic (TH) system codes to investigate specific nuclear reactor transients. Improving in theoretical investigations of complex phenomena in nuclear reactor technology have been increased thanks to numerical methods and computational resources incorporated in nuclear codes. This paper presents a model for the IPR-R1 TRIGA research reactor using the RELAP5-3D 3.0 code. The development and the assessment of the thermal-hydraulic RELAP5 code model for the IPR-R1 have been validated for steady state and transient situations and the results were published in preceding works. Results of RELAP5-3D steady state and a transient case presented in this paper show good agreement with experimental data, validating then this model for point kinetic calculations. To supply adequate cross sections to the NK code, the WIMSD5 is being used. First results of steady state calculation using the 3D neutron modeling are being presented in this paper. (author)

Experimental study of the temperature distribution in the TRIGA IPR-R1 Brazilian research reactor; Investigacao experimental da distribuicao de temperaturas no reator nuclear de pesquisa TRIGA IPR-R1

Energy Technology Data Exchange (ETDEWEB)

Mesquita, Amir Zacarias

2005-07-01

The TRIGA-IPR-R1 Research Nuclear Reactor has completed 44 years in operation in November 2004. Its initial nominal thermal power was 30 kW. In 1979 its power was increased to 100 kW by adding new fuel elements to the reactor. Recently some more fuel elements were added to the core increasing the power to 250 kW. The TRIGA-IPR-R1 is a pool type reactor with a natural circulation core cooling system. Although the large number of experiments had been carried out with this reactor, mainly on neutron activation analysis, there is not many data on its thermal-hydraulics processes, whether experimental or theoretical. So a number of experiments were carried out with the measurement of the temperature inside the fuel element, in the reactor core and along the reactor pool. During these experiments the reactor was set in many different power levels. These experiments are part of the CDTN/CNEN research program, and have the main objective of commissioning the TRIGA-IPR-R1 reactor for routine operation at 250 kW. This work presents the experimental and theoretical analyses to determine the temperature distribution in the reactor. A methodology for the calibration and monitoring the reactor thermal power was also developed. This methodology allowed adding others power measuring channels to the reactor by using thermal processes. The fuel thermal conductivity and the heat transfer coefficient from the cladding to the coolant were also experimentally valued. lt was also presented a correlation for the gap conductance between the fuel and the cladding. The experimental results were compared with theoretical calculations and with data obtained from technical literature. A data acquisition and processing system and a software were developed to help the investigation. This system allows on line monitoring and registration of the main reactor operational parameters. The experiments have given better comprehension of the reactor thermal-fluid dynamics and helped to develop numerical

Calculation of neutronic parameters of IEA-R1 reactor and purpose of a new configuration

International Nuclear Information System (INIS)

Kosaka, N.; Fanaro, L.C.C.B.; Yamaguchi, M.

1989-01-01

The program for reducing the fuel enrichment of the IEA-R1 reactor considers fuel plates containing U308-AL with 19,9% of U-235. The geometry of the new 18 fuel plate fuel elements has been kept the same. This work describes the calculation methods utilized at IPEN-CNEN/SP and some neutronic parameters of the present configuration of IEA-R1 as well as for a new configuration porposed with a new LEU fuel element are shown. (author) [pt

Modifications in the operational conditions of the IEA-R1 reactor under continuous 48 hours operation

International Nuclear Information System (INIS)

Moreira, Joao Manoel Losada; Frajndlich, Roberto

1995-01-01

This work shows the required changes in the IEA-R1 reactor for operation at 2 Mw, 48 hours continuously. The principal technical change regards the operating conditions of the reactor, namely, the required excess reactivity which now will amount to 4800 pcm in order to compensate the Xe poisoning at equilibrium at 2 Mw. (author). 6 refs, 1 fig, 1 tab

Insertion of reactivity (RIA) without scram in the reactor core IEA-R1 using code PARET

International Nuclear Information System (INIS)

Alves, Urias F.; Castrillo, Lazara S.; Lima, Fernando A.

2013-01-01

The modeling and analysis thermo hydraulics of a research reactor with MTR type fuel elements - Material Testing Reactor - was performed using the code PARET (Program for the Analysis of Reactor Transients) when in the system some external event is introduced that changed the reactivity in the reactor core. Transients of Reactivity Insertion of 0.5 , 1.5 and 2.0$/ 0.7s in the brazilian reactor IEA-R1 will be presented, and will be shown under what conditions it is possible to ensure the safe operation of its nucleus. (author)

Calculation of the main neutron parameters of the IEA-R1 research reactor

International Nuclear Information System (INIS)

Ojima, Mario Katsuhiko

1977-01-01

The main neutron parameters of the research reactor IEA-R1 were calculated using computer programs to generate cross sections and criticality calculations. A calculation procedure based on the programs available in the Processing Center Data of IEA was established and centered in the HAMMER and CITATION system. A study was done in order to verify the validity and accuracy of the calculation method comparing the results with experimental data. Some operating parameters of the reactor, namely the distribution of neutron flux, the critical mass, the variation of the reactivity with the burning of fuel, and the dead time of the reactor were determined

Hydroprocessing Catalysts. Utilization and Regeneration Schemes Catalyseurs d'hydrotraitement. Schémas d'utilisation et de régénération

Directory of Open Access Journals (Sweden)

Furimsky E.

2006-11-01

Full Text Available The catalyst reactor inventory represents an important part of the cost of hydroprocessing operation. The selection of a suitable catalyst and reactor is influenced by feedstock properties. Processes ensuring an uninterrupted operation during catalyst addition and withdrawal are preferred for processing high asphaltene and metal content feedstocks. The spent catalyst can be regenerated and returned to the operation if the extent of its deactivation is not high. The regeneration may be performed either in-situ or off-site. The former is suitable for fixed bed reactors whereas the catalyst from ebullated bed reactors must be regenerated off -site. The regeneration of spent catalysts heavily loaded with metals such as V, Ni and Fe may not be economic. Such catalysts may be suitable for metal reclamation. An environmentally safe method for catalyst disposal must be found if neither regeneration nor metal reclamation from spent catalysts can be performed. La quantité de catalyseurs utilisée représente une part importante du coût d'une opération d'hydrotraitement. Le choix d'un réacteur et d'un catalyseur approprié dépend des propriétés de la charge. On préfère utiliser les procédés permettant un fonctionnement continu pendant le chargement et le soutirage du catalyseur lorsqu'il s'agit de traiter des charges à haute teneur en asphaltène et en métaux. Le catalyseur usé peut être régénéré et remis en fonctionnement s'il n'est pas trop désactivé. La régénération peut être réalisée in situ ou hors du site. La première solution convient pour les réacteurs à lit fixe, tandis que le catalyseur de réacteurs à lit bouillonnant doit être régénéré hors du site. La régénération de catalyseurs usés fortement chargés en métaux tels que le vanadium, le nickel et le fer n'apparaît pas économique. De tels catalyseurs peuvent convenir pour la récupération des métaux. On doit trouver une méthode sans danger pour l

Gestion patrimoniale des réseaux d’assainissement : de l’état des réseaux à la planification de leur réhabilitation − Outils, méthodes et perspectives

Directory of Open Access Journals (Sweden)

WEREY, Cathy ; LE GAT, Yves ; LE GAUFFRE, Pascal ; ROZAN, Anne ; WITTNER, Christophe ; NIRSIMLOO, Kévin ; LECLERC, Cyril

2012-12-01

Full Text Available En France, la gestion patrimoniale des réseaux d’assainissement est une préoccupation croissante. Certains réseaux commencent en effet à dater et vont nécessiter des renouvellements importants et coûteux pour les décennies à venir. À travers leur mise en œuvre sur les réseaux de Caen et de Bordeaux, cet article présente deux modèles complémentaires, Indigau et GompitZ, permettant de décrire l’état du réseau et de prioriser les tronçons à réhabiliter.

SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

Energy Technology Data Exchange (ETDEWEB)

Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

2010-01-04

The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material

Ageing implementation and refurbishment development at the IEA-R1 nuclear research reactor: a 15 years experience

International Nuclear Information System (INIS)

Cardenas, Jose Patricio N.; Ricci Filho, Walter; Carvalho, Marcos R. de; Berretta, Jose Roberto; Marra Neto, Adolfo

2011-01-01

IPEN (Instituto de Pesquisas Energeticas e Nucleares) is a nuclear research center established into the Secretary of Science and Technology from the government of the state of Sao Paulo, and administered both technically and financially by Comissao Nacional de Energia Nuclear (CNEN), a federal government organization under the Ministry of Science and Technology. The institute is located inside the campus of the University of Sao Paulo, Sao Paulo city, Brazil. One of major nuclear facilities at IPEN is the IEA-R1 nuclear research reactor. It is the unique Brazilian research reactor with substantial power level suitable for application with research in physics, chemistry, biology and engineering, as well as radioisotope production for medical and other applications. Designed and built by Babcok-Wilcox, in accordance with technical specifications established by the Brazilian Nuclear Energy Commission, and financed by the US Atoms for Peace Program, it is a swimming pool type reactor, moderated and cooled by light water and uses graphite and beryllium as reflector elements. The first criticality was achieved on September 16, 1957 and the reactor is currently operating at 4.0 MW on a 64h per week cycle. Since 1996, an IEA-R1 reactor ageing study was established at the Research Reactor Center (CRPq) related with general deterioration of components belonging to some operational systems, as cooling towers from secondary cooling system, piping and pumps, sample irradiation devices, radiation monitoring system, fuel elements, rod drive mechanisms, nuclear and process instrumentation and safety operational system. Although basic structures are almost the same as the original design, several improvements and modifications in components, systems and structures had been made along reactor life. This work aims to show the development of the ageing program in the IEA-R1 reactor and the upgrading (modernization) that was carried out, concerning several equipment and system in the

Ageing implementation and refurbishment development at the IEA-R1 nuclear research reactor: a 15 years experience

Energy Technology Data Exchange (ETDEWEB)

Cardenas, Jose Patricio N.; Ricci Filho, Walter; Carvalho, Marcos R. de; Berretta, Jose Roberto; Marra Neto, Adolfo, E-mail: ahiru@ipen.b, E-mail: wricci@ipen.b, E-mail: carvalho@ipen.b, E-mail: jrretta@ipen.b, E-mail: amneto@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

IPEN (Instituto de Pesquisas Energeticas e Nucleares) is a nuclear research center established into the Secretary of Science and Technology from the government of the state of Sao Paulo, and administered both technically and financially by Comissao Nacional de Energia Nuclear (CNEN), a federal government organization under the Ministry of Science and Technology. The institute is located inside the campus of the University of Sao Paulo, Sao Paulo city, Brazil. One of major nuclear facilities at IPEN is the IEA-R1 nuclear research reactor. It is the unique Brazilian research reactor with substantial power level suitable for application with research in physics, chemistry, biology and engineering, as well as radioisotope production for medical and other applications. Designed and built by Babcok-Wilcox, in accordance with technical specifications established by the Brazilian Nuclear Energy Commission, and financed by the US Atoms for Peace Program, it is a swimming pool type reactor, moderated and cooled by light water and uses graphite and beryllium as reflector elements. The first criticality was achieved on September 16, 1957 and the reactor is currently operating at 4.0 MW on a 64h per week cycle. Since 1996, an IEA-R1 reactor ageing study was established at the Research Reactor Center (CRPq) related with general deterioration of components belonging to some operational systems, as cooling towers from secondary cooling system, piping and pumps, sample irradiation devices, radiation monitoring system, fuel elements, rod drive mechanisms, nuclear and process instrumentation and safety operational system. Although basic structures are almost the same as the original design, several improvements and modifications in components, systems and structures had been made along reactor life. This work aims to show the development of the ageing program in the IEA-R1 reactor and the upgrading (modernization) that was carried out, concerning several equipment and system in the

Le projet de recherche: définition, conduite et réalisation

OpenAIRE

Stockinger , Peter

2013-01-01

Master; Ce support de séminaire développe brièvement les quatre points suivants: 1) Définition d’un projet de recherche – présentation générale et recommandations. 2) La conduite d’un projet de recherche – présentation générale et recommandations. 3) La réalisation d’un projet de recherche sous forme d’un mémoire - présentation générale et recommandations. 4) Des ressources pour conduire un projet de recherche : ressources enligne et références bibliographiques.

Low enriched uranium UAl{sub X}-Al targets for the production of Molybdenum-99 in the IEA-R1 and RMB reactors

Energy Technology Data Exchange (ETDEWEB)

Domingos, Douglas B.; Silva, Antonio T. e; Joao, Thiago G.; Silva, Jose Eduardo R. da, E-mail: teixeira@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Nishiyama, Pedro J.B. de O., E-mail: pedro.julio@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

2011-07-01

The IEA-R1 reactor of IPEN/CNEN-SP in Brazil is a pool type research reactor cooled and moderated by demineralized water and having Beryllium and Graphite as reflectors. In 1997 the reactor received the operating licensing for 5 MW. A new research reactor is being planned in Brazil to replace the IEA-R1 reactor. This new reactor, the Brazilian Multipurpose Reactor (RMB), planned for 30 MW, is now in the conception design phase. Low enriched uranium (LEU) (<20% {sup 235}U) UAl{sub x} dispersed in Al targets are being considered for production of Molybdenum-99 ({sup 99}Mo) by fission. Neutronic and thermal-hydraulics calculations were performed, respectively, to compare the production of {sup 99}Mo for these targets in IEA-R1 reactor and RMB and to determine the temperatures achieved in the UAl{sub x}-Al targets during irradiation. For the neutronic calculations were utilized the computer codes HAMMER-TECHNION, CITATION and SCALE and for the thermal-hydraulics calculations was utilized the computer code MTRCR-IEAR1. (author)

Promouvoir des politiques et approches inclusives pour résoudre le ...

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

En se concentrant sur la violence criminelle et des gangs à Cape Town, l'étude fera la lumière sur l'ampleur de la participation des jeunes à ces réseaux de violence, selon les perspectives des jeunes hommes et des jeunes femmes. Le projet examinera comment les réseaux sociaux et économiques se forment et peuvent ...

Design of a digital system for operational parameters simulation of IPR-R1 TRIGA nuclear research reactor

International Nuclear Information System (INIS)

Lage, Aldo M.F.; Mesquita, Amir Z.; Felippe, Adriano de A.M.

2017-01-01

The instrumentation of nuclear reactors is designed based on the reliability, redundancy and diversification of control systems. The monitoring of the parameters is of crucial importance with regard to the operational efficiency and safety of the installation. Since the first criticality of a nuclear reactor, achieved by Fermi et al. in 1942, there has been concern about the reliable monitoring of the parameters involved in the chain reaction. This paper presents the current stage of the system of simulation, which is under development at the CDTN, which intends to simulate the operation of the TRIGA IPR-R1 nuclear reactor, involving the evolution of neutron flux and reactor power related events. The system will be developed using LabVIEW® software, using the modern concept of virtual instruments (VIs) that are visualized in a video monitor. For the implementation of this model, computational tools and systems analysis are necessary, which help and facilitate the implementation of the simulator. In this article we will show some of these techniques and the initial design of the model to be implemented. The design of a computational system is of great importance, since it guides in the implementation stages and generates the documentation for later maintenance and updating of the computational system. It is noteworthy that the innovations developed in research reactors are normally used in power reactors. The relatively low costs enable research reactors to be an excellent laboratory for developing techniques for future reactors. (author)

Design of a digital system for operational parameters simulation of IPR-R1 TRIGA nuclear research reactor

Energy Technology Data Exchange (ETDEWEB)

Lage, Aldo M.F.; Mesquita, Amir Z.; Felippe, Adriano de A.M., E-mail: aldo@cdtn.br, E-mail: amir@cdtn.br, E-mail: adrianoamfelippe@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN /CNEN-MG), Belo Horizonte, MG (Brazil); Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil)

2017-11-01

The instrumentation of nuclear reactors is designed based on the reliability, redundancy and diversification of control systems. The monitoring of the parameters is of crucial importance with regard to the operational efficiency and safety of the installation. Since the first criticality of a nuclear reactor, achieved by Fermi et al. in 1942, there has been concern about the reliable monitoring of the parameters involved in the chain reaction. This paper presents the current stage of the system of simulation, which is under development at the CDTN, which intends to simulate the operation of the TRIGA IPR-R1 nuclear reactor, involving the evolution of neutron flux and reactor power related events. The system will be developed using LabVIEW® software, using the modern concept of virtual instruments (VIs) that are visualized in a video monitor. For the implementation of this model, computational tools and systems analysis are necessary, which help and facilitate the implementation of the simulator. In this article we will show some of these techniques and the initial design of the model to be implemented. The design of a computational system is of great importance, since it guides in the implementation stages and generates the documentation for later maintenance and updating of the computational system. It is noteworthy that the innovations developed in research reactors are normally used in power reactors. The relatively low costs enable research reactors to be an excellent laboratory for developing techniques for future reactors. (author)

Modernization of Safety and Control Instrumentation of the IEA-R1 Research Reactor

Energy Technology Data Exchange (ETDEWEB)

De Carvalho, P.V., E-mail: paulov@ien.gov.br [Institute of Nuclear Engineering (IEN), National Nuclear Energy Commission (CNEN), Rio de Janeiro (Brazil)

2014-08-15

The research reactor IEA-R1 located in the Institute of Energy and Nuclear Research (IPEN), São Paulo, Brazil, obtained its first criticality on 16 September 1957 and since then has served the scientific and medical community in the performance of experiments in applied nuclear physics, as well as the provision of radioisotopes for production of radiopharmaceuticals. The reactor produces radioisotopes {sup 82}Br and {sup 41}Ar for special processes in industrial inspection and {sup 192}Ir and {sup 198}Au as sources of radiation used in brachytherapy, {sup 153}Sm for pain relief in patients with bone metastasis, and calibrated sources of {sup 133}Ba, {sup 137}Cs, {sup 57}Co, {sup 60}Co, {sup 241}Am and {sup 152}Eu used in medical clinics and hospitals practicing nuclear medicine and research laboratories. Services are offered in regular non-destructive testing by neutron radiography, neutron irradiation of silicon for phosphorous doping and other various irradiations with neutrons. The reactor is responsible for producing approximately 70% of radiopharmaceutical {sup 131}I used in Brazil, which saves about US$ 800 000 annually for the country. After more than 50 years of use, most of its equipment and systems have been modernized, and recently the reactor power was increased to 5 MW in order to enhance radioisotope production capability. However, the control room and nuclear instrumentation system used for reactor safety have operated more than 30 years and require constant maintenance. Many equipment and electronic components are obsolete, and replacements are not available in the market. The modernization of the nuclear safety and control instrumentation systems of IEA-R1 is being carried out with consideration for the internationally recognized criteria for safety and reliable reactor operations and the latest developments in nuclear electronic technology. The project for the new reactor instrumentation system specifies three wide range neutron monitoring

IEA-R1 Nuclear Research Reactor: 58 Years of Operating Experience and Utilization for Research, Teaching and Radioisotopes Production

Energy Technology Data Exchange (ETDEWEB)

Cardenas, Jose Patricio Nahuel; Filho, Tufic Madi; Saxena, Rajendra; Filho, Walter Ricci [Nuclear and Energy Research Institute, IPEN-CNEN/SP, Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242 Cid Universitaria CEP: 05508-000- Sao Paulo-SP (Brazil)

2015-07-01

IEA-R1 research reactor at the Instituto de Pesquisas Energeticas e Nucleares (Nuclear and Energy Research Institute) IPEN, Sao Paulo, Brazil is the largest power research reactor in Brazil, with a maximum power rating of 5 MWth. It is being used for basic and applied research in the nuclear and neutron related sciences, for the production of radioisotopes for medical and industrial applications, and for providing services of neutron activation analysis, real time neutron radiography, and neutron transmutation doping of silicon. IEA-R1 is a swimming pool reactor, with light water as the coolant and moderator, and graphite and beryllium as reflectors. The reactor was commissioned on September 16, 1957 and achieved its first criticality. It is currently operating at 4.5 MWth with a 60-hour cycle per week. In the early sixties, IPEN produced {sup 131}I, {sup 32}P, {sup 198}Au, {sup 24}Na, {sup 35}S, {sup 51}Cr and labeled compounds for medical use. During the past several years, a concerted effort has been made in order to upgrade the reactor power to 5 MWth through refurbishment and modernization programs. One of the reasons for this decision was to produce {sup 99}Mo at IPEN. The reactor cycle will be gradually increased to 120 hours per week continuous operation. It is anticipated that these programs will assure the safe and sustainable operation of the IEA-R1 reactor for several more years, to produce important primary radioisotopes {sup 99}Mo, {sup 125}I, {sup 131}I, {sup 153}Sm and {sup 192}Ir. Currently, all aspects of dealing with fuel element fabrication, fuel transportation, isotope processing, and spent fuel storage are handled by IPEN at the site. The reactor modernization program is slated for completion by 2015. This paper describes 58 years of operating experience and utilization of the IEA-R1 research reactor for research, teaching and radioisotopes production. (authors)

Thirty years experience in ET-RR-1 operation

International Nuclear Information System (INIS)

Khattab, M.

1993-01-01

Egypt research reactor (ET-R R-1) got critical in 27 Th. July 1961. Since that time many technical problems in system manipulation were raised. The present paper demonstrates the famous events that were initiated and the procedures that were taken for their recovery or mitigation. Maintenance problems are discussed. Reactor parameters measuring systems and control have been modernized. The reactor is investigated by in-service inspection program, (ISI). The results show that reactor vessels surface conditions are in good status. experience obtained from these activities and some proposals for future development are summarized. 6 figs., 1 tab

Spent fuel management - two alternatives at the FiR 1 reactor

International Nuclear Information System (INIS)

Salmenhaara, S.E.J.

2001-01-01

The FiR 1 -reactor, a 250 kW Triga reactor, has been in operation since 1962. The reactor with its subsystems has experienced a large renovation work in 1996-97. The main purpose of the upgrading was to install the new Boron Neutron Capture Therapy (BNCT) irradiation facility. The BNCT work dominates the current utilization of the reactor: four days per week for BNCT purposes and only one day per week for neutron activation analysis and isotope production. The Council of State (government) granted for the reactor a new operating license for twelve years starting from the beginning of the year 2000. There is however a special condition in the new license. We have to achieve a binding agreement between our Research Centre and the domestic Nuclear Power Plant Companies about the possibility to use the final disposal facility of the Nuclear Power Plants for our spent fuel, if we want to continue the reactor operation beyond the year 2006. In addition to the choosing of one of the spent fuel management alternatives the future of the reactor will also depend strongly on the development of the BNCT irradiations. If the number of patients per year increases fast enough and the irradiations of the patients will be economically justified, the operation of the reactor will continue independently of the closing of the USDOE alternative in 2006. Otherwise, if the number of patients will be low, the funding of the reactor will be probably stopped and the reactor will be shut down. (author)

Penny Lane et Strawberry Field(s : réel, identité et fantasmagorie

Directory of Open Access Journals (Sweden)

Bernard Gensane

2010-11-01

Full Text Available Les chansons « Penny Lane » et « Strawberry Fields Forever » permettent d’appréhender le thème de l’enfance chez les Beatles. De manière très différente, John Lennon et Paul McCartney s’appuient sur une visite de deux lieux réels liverpooliens pour mettre en résonance leurs visions fantasmagoriques du passé, et pour exploiter la langue (qu’ils travaillent et qui les travaille dans une perspective authentiquement artistique.

Neutrons characterization of the nuclear reactor Ian-R1 of Colombia; Caracterizacion de los neutrones del reactor nuclear IAN-R1 de Colombia

Energy Technology Data Exchange (ETDEWEB)

Gonzalez P, L. X.; Martinez O, S. A. [Universidad Pedagogica y Tecnologica de Colombia, Grupo de Fisica Nuclear Aplicada y Simulacion, Carretera Central del Norte Km. 1, Via Paipa, 150003 Tunja, Boyaca (Colombia); Vega C, H. R., E-mail: s.agustin.martinez@uptc.edu.co [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico)

2014-08-15

By means of Monte Carlo methods, with the code MCNPX, the neutron characteristics of the research nuclear reactor Ian-R1 of Colombia, in power off but with the neutrons source in their start position, have been valued. The neutrons spectra, the total flow and their average power were calculated in the irradiation spaces inside the graphite reflector, as well as in the cells with air. Also the spectra, the total flow and the absorbed dose were calculated in several places distributed along the radial shaft inside the water moderator. The neutrons total flow was also considered to the long of the axial shaft. The characteristics of the neutrons spectra vary depending on their position regarding the source and the material that surrounds to the cell where the calculation was made. (Author)

Calculations and selection of a TRIGA core for the Nuclear Reactor IAN-R1

International Nuclear Information System (INIS)

Castiblanco, L.A.; Sarta, J.A.

1997-01-01

The Reactor Group used the code WIMS reduced to five groups of energy, together with the code CITATION, and evaluated four configurations for a core, according to the grid actually installed. The four configurations were taken from the two proposals presented to the Instituto de Ciencias Nucleares y Energias Alternativas by General Atomics Company. In this paper, the Authors selected the best configuration according to the performance of flux distribution and excess reactivity, for a TRIGA core to be installed in the Nuclear Reactor IAN-R1

Clonage de l'IGF-I et de son récepteur chez le turbot (Psetta maxima

Directory of Open Access Journals (Sweden)

ELIES G.

1998-07-01

Full Text Available Les IGF, leurs récepteurs et leurs protéines de liaison constituent une famille moléculaire qui joue un rôle essentiel dans la régulation de la croissance et du développement. Nous nous sommes intéressés à la caractérisation moléculaire de l'IGF-l et de son récepteur (IGF-1R chez le turbot (Psetta maxima, un poisson plat téléostéen. Par RT-PCR, nous avons clone un ADNc codant pour les quatre domaines de l'IGF-l mature. La protéine présente 70 à 96 % d'identité avec les autres IGF-I de vertébrés. Le clonage de la séquence codante entière du récepteur a nécessité la construction d'une banque d'ADNc d'embryons de turbots. Le récepteur est organisé en domaines dont la taille et les caractéristiques sont semblables à celles des autres récepteurs aux IGF de type 1 décrits chez les mammifères et le poulet. La région catalytique est particulièrement conservée. Dans certains domaines, notamment dans la région C-terminale du précurseur, quelques différences qui pourraient avoir une importance fonctionnelle sont cependant observées. Enfin, par RT-PCR, nous avons mis en évidence une régulation ontogénique du statut de polyadénylation des ARNm IGF-1R.

Feasibility study of application of Prompt Gamma Neutron Activation Analysis (PGNAA) method in TRIGA IPR-R1 reactor; Estudo da viabilidade de aplicação do método Prompt Gamma Neutron Activation Analysis (PGNAA) no reator TRIGA IPR-R1

Energy Technology Data Exchange (ETDEWEB)

Guerra, Bruno Teixeira

2016-07-01

The TRIGA Mark I IPR-R1 research reactor is located at Nuclear Technology Development Centre (CDTN), Brazilian Commission for Nuclear Energy (CNEN), in Belo Horizonte, Brazil. The reactor operates at 100 kW but the core configuration allows the increasing of the power up to 250 kW. It has been applied research, training and radioisotopes production. The establishment of the Prompt Gamma Neutron Activation Analysis (PGNAA) method at the TRIGA IPR-R1 reactor will significantly increase the types of matrices analysed as well as the number of chemical elements. Additionally it will complement the neutron activation analysis. This work presents a proposed design of a PGNAA facility to be installed at the TRIGA IPR-R1. The proposed design is based on a tube as a neutron guide from the reactor core, inside the reactor pool, 6 m below the room’s level where shall be located the rack containing the set sample/detector/shielding. Thus, the aim of this study is to verify the feasibility to establish the PGNAA method in IPR-R1 through theoretical study applying the Monte Carlo code. The feasibility of establishing the PGAA method at the IPR-R1 installations was evaluated through of the calculations of neutron flux, radioactive capture reaction rates and detection limits for some isotopes. According to the obtained results, it can be concluded that is possible to establish the PGAA method at the IPR-R1 reactor, even with some restrictions in its theoretical design calculated by MCNP. (author)

Les réseaux dans le temps et dans l’espace

Directory of Open Access Journals (Sweden)

Marion Maisonobe

2014-03-01

Full Text Available Le groupe fmr vient d’avoir 3 ans. Fondé par Laurent Beauguitte et César Ducruet en Octobre 2010, le groupe fmr regroupe des chercheurs et étudiants intéressés par l’analyse de réseaux et son caractère trans-disciplinaire. Chaque réunion du groupe, ouverte au public, donne lieu à une synthèse consacrée à une méthode, un outil ou un concept. La prochaine réunion publique aura lieu le mardi 12 Novembre au 13 Rue du Four de 10h30 à 12h30. Elle portera sur le thème « Réseaux et Simulation » et s...

Encadrement des produits et des procédés : réglementation et normalisation du commerce international

Directory of Open Access Journals (Sweden)

Morin Odile

2003-07-01

Full Text Available Produits et procédés sont encadrés à la fois par des réglementations et, à un autre niveau, par des normes du commerce international. Cette présentation traite des textes réglementaires au niveau communautaire et national. On rappellera que l’entrée en vigueur d’un règlement européen est suivie d’une transposition dans le droit de chaque pays membre et que la réglementation nationale s’applique en l’absence de dispositions communautaires. En matière de commerce international, seront évoquées les actions de normalisation du Conseil Oléicole International (COI pour les huiles d’olive et de grignons d’olive et celles du Codex Alimentarius pour les huiles et graisses comestibles. L’ensemble des dispositions réglementaires constitue un cadre englobant les productions de l’amont vers l’aval, à la fois sur un plan vertical (oléagineux, huiles et corps gras, huiles d’olive, margarines, procédés de raffinage et transversalement (composés organiques volatils, OGM, solvants d’extraction, additifs, contaminants…. Le cas de l’huile d’olive est particulier en ce qu’il bénéficie d’un encadrement au niveau international (normes commerciales COI et Codex Alimentarius, européen et national (réglementation. Le Codex Alimentarius, quant à lui, établit des normes à caractère vertical (huiles végétales, graisses animales, huiles d’olive, matières grasses tartinables… et horizontal (additifs, résidus de pesticides…. L’essentiel de cet encadrement est résumé dans les tableaux qui illustrent cette contribution.

Circuits design of action logics of the protection system of nuclear reactor IAN-R1 of Colombia; Diseno de los circuitos de la logica de actuacion del sistema de proteccion del reactor nuclear IAN-R1 de Colombia

Energy Technology Data Exchange (ETDEWEB)

Gonzalez M, J. L.; Rivero G, T.; Sainz M, E., E-mail: joseluis.gonzalez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2014-10-15

Due to the obsolescence of the instrumentation and control system of the nuclear research reactor IAN-R1, the Institute of Geology and Mining of Colombia, IngeoMinas, launched an international convoking for renewal it which was won by the Instituto Nacional de Investigaciones Nucleares (ININ). Within systems to design, the reactor protection system is described as important for safety, because this carried out, among others two primary functions: 1) ensuring the reactor shutdown safely, and 2) controlling the interlocks to protect against operational errors if defined conditions have not been met. To fulfill these functions, the various subsystems related to the safety report the state in which they are using binary signals and are connected to the inputs of two redundant logic wiring circuits called action logics (Al) that are part of the reactor protection system. These Al also serve as logical interface to indicate at all times the status of subsystems, both the operator and other systems. In the event that any of the subsystems indicates a state of insecurity in the reactor, the Al generate signals off (or scram) of the reactor, maintaining the interlock until the operator sends a reset signal. In this paper the design, implementation, verification and testing of circuits that make up the Al 1 and 2 of IAN-R1 reactor is described, considering the fulfillment of the requirements that the different international standards imposed on this type of design. (Author)

R and D directions for the development of CANDU reactors

International Nuclear Information System (INIS)

Torgerson, D.F.

1998-01-01

Full text: AECL is carrying out a comprehensive R and D programme to advance all aspects of CANDU reactor technology. These programs are focusing on three main strategic directions: improved economics, enhanced safety, and fuel cycle flexibility. R and D areas include fuel cycle development, heavy water technology, fuel channel development, safety technology, control and instrumentation, reactor chemistry, systems and components, and health and environment. In each case, the R and D programs have short, medium, and long-term goals to achieve the overall strategic directions. Most of the programs seek to further develop and exploit some of the unique characteristics of pressurized heavy water reactors. Examples of this include high neutron economy and on-power fueling which allow several different fuel cycles, the presence of large water heat sinks for enhanced safety, and modular components that can be easily replaced for plant life extension. This presentation reviews AECL's product development directions and the R and D programs that have been begun for their development

Scale Effects in Laboratory and Pilot-Plant Reactors for Trickle-Flow Processes Les conséquences de l'extrapolation appliquée aux procédés à écoulement ruisselant réalisés en laboratoire et dans les réacteurs des unités-pilotes

Directory of Open Access Journals (Sweden)

Sie S. T.

2006-11-01

carry out meaningful process research on hydrotreating processes on the scale of micro-reactors. Les études et mises au point effectuées en laboratoire sont nécessairement effectuées à plus petite échelle que les réalisations commerciales. Dans le cas de la mise au point et de la commercialisation de la technologie d'un procédé nouveau, il faudra traduire les résultats obtenus en laboratoire pour la technologie envisagée à l'échelle commerciale; le problème est donc l'extrapolation vers le haut. Cependant, bien souvent, la technologie commerciale, pour ce qui touche au type de réacteur, est plus ou moins bien définie et les études de laboratoire s'attachent à produire des données permettant de prévoir le comportement qu'auront dans ce réacteur des catalyseurs nouveaux, de matières premières de substitution, etc. Dans bien des cas, étant donné la complexité de la composition de la matière première et la cinétique de réaction, il est impossible de mener la prévision en s'appuyant sur les données cinétiques et les modèles informatiques, de sorte qu'il n'y a pas d'autre solution que la simulation du réacteur commercial à l'échelle du laboratoire; le problème est donc l'extrapolation vers le bas. Du point de vue de l'efficacité des études de recherche et développement, pour les expériences en laboratoire, l'échelle devra être aussi petite que possible sans nuire à la signification des résultats. Le présent article examine certains problèmes liés à l'extrapolation vers le bas d'un réacteur à écoulement ruisselant telle qu'elle est appliquée dans les procédés d'hydrotraitement à des réacteurs de laboratoire de tailles différentes cinétiquement équivalents. Deux aspects principaux relatifs à des inégalités de dynamique des fluides résultant de différences d'échelle sont décrits plus en détail, i. e. les écarts par rapport à un écoulement idéal donnant lieu à un effet bouchon et au mouillage ou à l

Spent fuel management plans for the FiR 1 Reactor

International Nuclear Information System (INIS)

Salmenhaara, S. E. J.

2002-01-01

The FiR 1-reactor, a 250 kW TRIGA reactor, has been in operation since 1962. The main purpose to run the reactor is now the Boron Neutron Capture Therapy (BNCT). The BNCT work dominates the current utilization of the reactor: three days per week for BNCT purposes and only two days per week for other purposes such as the neutron activation analysis and isotope production. The final disposal site is situated in Olkiluoto, on the western coast of Finland. Olkiluoto is also one of the two nuclear power plant sites in Finland. In the new operating license of our reactor there is a special condition. We have to achieve a binding agreement between our Research Centre and either the domestic Nuclear Power Companies about the possibility to use the Olkiluoto final disposal facility for our spent fuel or US DOE about the return of our spent fuel back to USA. If we want to continue the reactor operation beyond the year 2006. the domestic final disposal is the only possibility. At the moment it seems to be reasonable to prepare to both possibilities: the domestic final disposal and the return to the USA offered by US DOE. Because the cost estimates of the both possibilities are on the same order of magnitude, the future of the reactor itself will decide, which of the spent fuel policies will be obeyed. In a couple of years' time it will be seen, if the funding of the reactor and the incomes from the BNCT treatments will cover the costs. If the BNCT and other irradiations develop satisfactorily, the reactor can be kept in operation beyond the year 2006 and the domestic final disposal will be implemented. If, however, there is still lack of money, there is no reason to continue the operation of the reactor and the choice of US DOE alternative is natural. (author)

Application of nondestructive methods for qualification of high density fuels in the IEA-R1 reactor

International Nuclear Information System (INIS)

Silva, Jose E.R.; Silva, Antonio T.; Domingos, Douglas B.; Terremoto, Luis A.A.

2011-01-01

IPEN/CNEN-SP manufactures fuels to be used in its research reactor - the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil still does not have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP has conducted a fuel qualification program based on the use of uranium compounds (U 3 O 8 and U 3 Si 2 dispersed in Al matrix) internationally tested and qualified to be used in research reactors, and has attained experience in the technological development stages for the manufacturing of fuel plates, irradiation and non-destructive post-irradiation testing. Fuel elements containing low volume fractions of fuel in the dispersion were manufactured and irradiated successfully directly in the core of the IEA-R1. However, there are plans at IPEN/CNEN-SP to increase the uranium density of the fuels. Ten fuel miniplates (five containing U 3 O 8 -Al and five containing U 3 Si 2 -Al), with densities of 3.2 gU/cm 3 and 4.8 gU/cm 3 respectively, are being irradiated inside an irradiation device placed in a peripheral position of the IEA-R1 core. Non-destructive methods will be used to evaluate irradiation performance of the fuel miniplates after successive cycles of irradiation, by means: monitoring the reactor parameters during operation; periodic underwater visual inspection of fuel miniplates, eventual sipping test for fuel miniplates suspected of leakage and underwater measuring of the miniplate thickness for assessment of the fuel miniplate swelling. (author)

Initial mass function in R-associations CMaR1, Mon R1 and Mon R2 from radiodata

International Nuclear Information System (INIS)

Pyatunina, T.B.

1985-01-01

Results of search for compact radiosources in R-associations CMa R1 and Mon R1 carried out with the radiotelescope RATAN-600 at the 7.6-cm wavelength are given. The number of sources found in the association Mon R1 is approximately equal to the expected number of background extragalactic radiosources. In the association CMa R1 seven radiosources of small angular diameter with the flux greater than 30 mJy are found, two of which probably are background sources. A comparison of optical and radiodata on the association CMa R1 and previously published data on the association Mon R2 make it possible to estimate the initial mass function for associations under study: xi(M) infinity Msup(-2.7+-0.7) for stars with M approximately 10Msub(Sun)

Circuits design of action logics of the protection system of nuclear reactor IAN-R1 of Colombia

International Nuclear Information System (INIS)

Gonzalez M, J. L.; Rivero G, T.; Sainz M, E.

2014-10-01

Due to the obsolescence of the instrumentation and control system of the nuclear research reactor IAN-R1, the Institute of Geology and Mining of Colombia, IngeoMinas, launched an international convoking for renewal it which was won by the Instituto Nacional de Investigaciones Nucleares (ININ). Within systems to design, the reactor protection system is described as important for safety, because this carried out, among others two primary functions: 1) ensuring the reactor shutdown safely, and 2) controlling the interlocks to protect against operational errors if defined conditions have not been met. To fulfill these functions, the various subsystems related to the safety report the state in which they are using binary signals and are connected to the inputs of two redundant logic wiring circuits called action logics (Al) that are part of the reactor protection system. These Al also serve as logical interface to indicate at all times the status of subsystems, both the operator and other systems. In the event that any of the subsystems indicates a state of insecurity in the reactor, the Al generate signals off (or scram) of the reactor, maintaining the interlock until the operator sends a reset signal. In this paper the design, implementation, verification and testing of circuits that make up the Al 1 and 2 of IAN-R1 reactor is described, considering the fulfillment of the requirements that the different international standards imposed on this type of design. (Author)

Information et réseaux en Asie et en Afrique subsaharienne ...

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

Le programme diffuse également des connaissances utiles au renforcement du dialogue et des pratiques en matière de politiques dans ces domaines. Le CRDI et le Department for International Development du Royaume-Uni ont établi le programme IRAAS grâce à un financement conjoint de 18,5 millions CAD réparti sur ...

Nye vilkår for ledelse - Strategisk ledelse set i et praksisperspektiv

DEFF Research Database (Denmark)

Larsen, Mette Vinther; Rasmussen, Jørgen Gulddahl

2012-01-01

Nye vilkår for ledelse er et bidrag til den aktive debat om, hvordan strategi og strategisk ledelse kan forstås. En debat, der er aktiv både inden for forskning, men i særdeleshed også inden for praksis, hvor især den finansielle krise har aktualiseret behovet for at forstå strategisk ledelse und...... andre vilkår. Artiklen behandler dette både på et teoretisk og et empirisk niveau for at kaste lys over, hvordan disse nye vilkår for strategisk ledelse kan forstås, og hvordan de konkret håndteres....

Nuclear research reactor IEA-R1 heat exchanger inlet nozzle flow - a preliminary study

International Nuclear Information System (INIS)

Angelo, Gabriel; Andrade, Delvonei Alves de; Fainer, Gerson; Angelo, Edvaldo

2009-01-01

As a computational fluid mechanics training task, a preliminary model was developed. ANSYS-CFX R code was used in order to study the flow at the inlet nozzle of the heat exchanger of the primary circuit of the nuclear research reactor IEA-R1. The geometry of the inlet nozzle is basically compounded by a cylinder and two radial rings which are welded on the shell. When doing so there is an offset between the holes through the shell and the inlet nozzle. Since it is not standardized by TEMA, the inlet nozzle was chosen for a preliminary study of the flow. Results for the proposed model are presented and discussed. (author)

SYNTHESIS AND CHARACTERIZATION OF (MU-5-C5ME5)2TI(R)CL (R = ME, ET, NORMAL-PR, CH=CH2, PH, O-NORMAL-PR) AND THEIR SALT METATHESIS REACTIONS - THERMAL-DECOMPOSITION PATHWAYS OF (MU-5-C5ME5)2TI(ME)R' (R' = ET, CH=CH2, PH, CH2PH)

NARCIS (Netherlands)

LUINSTRA, GA; TEUBEN, JH

Complexes Cp*2Ti(R)Cl (Cp* = eta-5-C5Me5; R = Me (1), Et (2), n-Pr (3), CH=CH2 (4), Ph (5), O-n-Pr (6)) have been prepared by oxidation Of CP*2TiR with lead dichloride. Not every compound Cp*2Ti(R)Cl was accessible and for R = CH2CMe3 and CH2Ph reduction to Cp*2TiCl and R. was observed. Homolysis of

Summary of IEA-R1 research a reactor licensing related to its power increase from 2 to 10 MW

International Nuclear Information System (INIS)

1989-04-01

This work is a summary of IEA-R1 research reactor licensing related to its power increase from 2 to 10 MW. It reports also safety requirements, fuel elements, and reactor control modifications inherent to power increase. (A.C.A.S.)

La liberté républicaine et la démocratisation du régime international

Directory of Open Access Journals (Sweden)

Dave Anctil

2009-06-01

Full Text Available L’idéal républicain de la liberté comme non-domination promu par P. Pettit possède un potentiel intéressant pour penser l’évolution de l’internationalisme. Cet article examine l’enjeu éthique et politique de l’application institutionnelle de la liberté comme non-domination à l’échelle supranationale. Il discute en particulier la thèse de J. Bohman, qui a récemment proposé une interprétation délibérative et cosmopolitique de la conception de la liberté républicaine. Mais le passage de la citoyenneté démocratique nationale à la citoyenneté cosmopolitique, tel que défendu par Bohman, nous semble reposer sur des conceptions trop exigeantes et compréhensives de l’impartialité et de la démocratie. En nous appuyant sur les travaux socio-historiques de S. Sassen et de C. Tilly, nous soutenons que des idéaux normatifs moins exigeants de l’impartialité et de la démocratie gagneraient en réalisme sociologique et en correspondance avec les mécanismes actuellement impliqués dans l’évolution de la coopération internationale et dans la démocratisation des sociétés. The republican ideal of freedom as non-domination, as promoted by P. Pettit, offers good grounds for thinking about the evolution of internationalism. This paper evaluates the ethical and political dimensions of freedom as non-domination at the supranational level. I discuss the argument of J. Bohman, who has recently proposed a deliberative and cosmopolitan interpretation of freedom as non-domination. I argue that the move from national democratic citizenship to a cosmopolitan conception of citizenship, as championed by Bohman, is justified by overtly comprehensive and taxing conceptions of impartiality and democracy. I then refer to recent sociological-historical works by S. Sassen and C. Tilly, and argue that less demanding normative conceptions of impartiality and democracy could gain sociological realism and correspondence with the actual

Application of safety checklist to the analysis of the IEA-R1 reactor water retreatment system

International Nuclear Information System (INIS)

Sauer, Maria Eugenia Lago Jacques; Sara Neto, Antonio Jorge; Lima, Toni Carlos Caboclo de; Ribeiro, Maria Alice Morato

2005-01-01

In 1999, the management of the IEA-R1 Research Reactor (pool type - 5 MWth), located at IPEN/CNEN-SP, started the evaluation of the Reactor Pool Water Retreatment System to identify operational aspects, which could compromise the operators safety. The purpose was to identify and propose enhancements to the system which would be installed to substitute for the existing one. This process was conducted through a qualitative study of the system in operation. This study was carried out by a team composed of specialists in reactor operation, systems maintenance and radiological protection, and one safety analyst. The study consisted, basically, in local inspections to verify the physical and operational conditions of each equipment / component as well as aspects related to maintenance activities of the system. The process control and the operator procedures associated with the retreatment of the reactor pool water were also reviewed. The methodology adopted to develop the study was based in process hazard analysis technique named Safety Checklist. This paper presents a summary of this study and the main results obtained. Some operational and safety problems identified, the prevention and/or correction means to avoid them, and the recommendations and suggestions that have been implemented to the new design of the IEA-R1 Reactor Water Retreatment System, whose installation was concluded in 2003, are also presented. (author)

Application of nondestructive methods for qualification of high density fuels in the IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Silva, Jose E.R.; Silva, Antonio T.; Domingos, Douglas B.; Terremoto, Luis A.A., E-mail: jersilva@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

IPEN/CNEN-SP manufactures fuels to be used in its research reactor - the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil still does not have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP has conducted a fuel qualification program based on the use of uranium compounds (U{sub 3}O{sub 8} and U{sub 3}Si{sub 2} dispersed in Al matrix) internationally tested and qualified to be used in research reactors, and has attained experience in the technological development stages for the manufacturing of fuel plates, irradiation and non-destructive post-irradiation testing. Fuel elements containing low volume fractions of fuel in the dispersion were manufactured and irradiated successfully directly in the core of the IEA-R1. However, there are plans at IPEN/CNEN-SP to increase the uranium density of the fuels. Ten fuel miniplates (five containing U{sub 3}O{sub 8}-Al and five containing U{sub 3}Si{sub 2}-Al), with densities of 3.2 gU/cm{sup 3} and 4.8 gU/cm{sup 3} respectively, are being irradiated inside an irradiation device placed in a peripheral position of the IEA-R1 core. Non-destructive methods will be used to evaluate irradiation performance of the fuel miniplates after successive cycles of irradiation, by means: monitoring the reactor parameters during operation; periodic underwater visual inspection of fuel miniplates, eventual sipping test for fuel miniplates suspected of leakage and underwater measuring of the miniplate thickness for assessment of the fuel miniplate swelling. (author)

Lead-based Fast Reactor Development Plan and R&D Status in China

International Nuclear Information System (INIS)

Wu Yican

2013-01-01

• Lead-based fast reactors have good potential for waste transmutation, fuel breeding and energy production, which has been selected by CAS as the advanced reactor development emphasis with the support of ADS program and MFE program. Sharing of technologies R&D is possible among GIF/ADS/Fusion. • The concepts and test strategy of series China lead-based fast reactors (CLEAR) have been developed. The preliminary engineering design and safety analysis of CLEAR-I are underway. • Technology R&D on CLEAR with series lead alloy loops and accelerator-based neutron generator have been constructed or under construction. • CLEAR series reactor design and construction have big challenges, widely international cooperation on reactor design and technology R&D is welcome

Device for neutron flux monitoring in IEA-R1 reactor using rhodium self powered neutron detector; Dispositivo de mapeamento de fluxo de neutron atraves do SPN/Rodio no IEA-R1

Energy Technology Data Exchange (ETDEWEB)

Ricci Filho, Walter; Fernando, Alberto de Jesus; Jerez, Rogerio; Tondin, Julio B.M.; Pasqualetto, Hertz [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

2000-07-01

The IEA-R1 reactor has undergone a modernization tio increase its operating power to 5 MW, in order to allow a more efficient production of radioisotopes. The objective of this work is to provide the reactor with flux monitoring device using a rhodium self powered neutron detector. Self powered detectors are rugged miniature devices with are increasingly being used for fixed in core reactor monitoring both for safety purposes and flux mapping. The work presents the results obtained with Rhodium-SPND in several irradiation position inside the reactor core. (author)

Current activities at the FiR 1 TRIGA reactor

International Nuclear Information System (INIS)

Salmenhaara, Seppo

2002-01-01

The FiR 1 -reactor, a 250 kW Triga reactor, has been in operation since 1962. The main purpose to run the reactor is now the Boron Neutron Capture Therapy (BNCT). The epithermal neutrons needed for the irradiation of brain tumor patients are produced from the fast fission neutrons by a moderator block consisting of Al+AlF 3 (FLUENTAL), which showed to be the optimum material for this purpose. Twenty-one patients have been treated since May 1999, when the license for patient treatment was granted to the responsible BNCT treatment organization. The treatment organization has a close connection to the Helsinki University Central Hospital. The BNCT work dominates the current utilization of the reactor: three days per week for BNCT purposes and only two days per week for other purposes such as the neutron activation analysis and isotope production. In the near future the back end solutions of the spent fuel management will have a very important role in our activities. The Finnish Parliament ratified in May 2001 the Decision in Principle on the final disposal facility for spent fuel in Olkiluoto, on the western coast of Finland. There is a special condition in our operating license. We have now about two years' time to achieve a binding agreement between VTT and the Nuclear Power Plant Companies about the possibility to use the final disposal facility of the Nuclear Power Plants for our spent fuel. If this will not happen, we have to make the agreement with the USDOE with the well-known time limits. At the moment it seems to be reasonable to prepare for both spent fuel management possibilities: the domestic final disposal and the return to the USA offered by USDOE. Because the cost estimates of the both possibilities are on the same order of magnitude, the future of the reactor itself will determine, which of the spent fuel policies will be obeyed. In a couple of years' time it will be seen, if the funding of the reactor and the incomes from the BNC treatments will cover

Les marbriers des Bâtiments du roi : organisation et réalisations

Directory of Open Access Journals (Sweden)

Sophie Mouquin

2012-09-01

Full Text Available Matériau noble, symbole de beauté, de pouvoir et d’éternité, le marbre est sous l’Ancien Régime, et particulièrement sous le règne de Louis XIV et la Régence, un matériau royal. Toutes les maisons royales reçoivent pavements, lambris et cheminées réalisés dans des marbres aux couleurs vives, provenant pour la plupart de carrières du royaume. Leur origine répond ainsi à la politique royale du marbre français que les directeurs des Bâtiments du roi s’efforcent de mettre en place et de consolider. Tous ces travaux ont leurs artisans : Derbais, Dezègre, Pasquier, Ménard, Mathaut, Lisquy, Tarlé, Trouard, etc., autant de noms indissociables des réalisations marbrières dans les maisons royales, mais si souvent oubliés. Ils jouent pourtant, dans ce domaine, un rôle de premier plan à tous niveaux, de la carrière au chantier. L’exposé présente l’organisation de ce corps de métier, sa place au sein des Bâtiments du roi et son rôle dans la politique marbrière. Il s’appuie sur les principales réalisations versaillaises, comme l’appartement des bains, l’escalier des Ambassadeurs, l’escalier de la Reine, la galerie des Glaces, le salon d’Hercule, les cheminées et les lambris des appartements du Roi et de la Reine. Il évoquera le chantier des jardins avec le bosquet de la Colonnade et d’autres bosquets.

Experimental distribution of coolant in the IPR-R1 Triga nuclear reactor core

Energy Technology Data Exchange (ETDEWEB)

Mesquita, Amir Z., E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Servico de Tecnologia de Reatores; Palma, Daniel A.P., E-mail: dapalma@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN/RJ), Rio de Janeiro, RJ (Brazil); Costa, Antonella L.; Pereira, Claubia; Veloso, Maria A.F.; Reis, Patricia A.L., E-mail: claubia@nuclear.ufmg.b, E-mail: dora@nuclear.ufmg.b [Universidade Federal de Minas Gerais (DEN/UFMG), Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

2011-07-01

The IPR-R1 is a typical TRIGA Mark I light-water and open pool type reactor. The core has an annular configuration of six rings and is cooled by natural circulation. The core coolant channels extend from the bottom grid plate to the top grid plate. The cooling water flows through the holes in the bottom grid plate, passes through the lower unheated region of the element, flows upwards through the active region, passes through the upper unheated region, and finally leaves the channel through the differential area between a triangular spacer block on the top of the fuel element and a round hole in the grid. Direct measurement of the flow rate in a coolant channel is difficult because of the bulky size and low accuracy of flow meters. The flow rate through the channel may be determined indirectly from the heat balance across the channel using measurements of the water inlet and outlet temperatures. This paper presents the experiments performed in the IPR-R1 reactor to monitoring some thermo-hydraulic parameters in the core coolant channels, such as: the radial and axial temperature profile, temperature, velocity, mass flow rate, mass flux and Reynolds's number. Some results were compared with theoretical predictions, as it was expected the variables follow the power distribution (or neutron flux) in the core. (author)

Experimental distribution of coolant in the IPR-R1 Triga nuclear reactor core

International Nuclear Information System (INIS)

Mesquita, Amir Z.; Costa, Antonella L.; Pereira, Claubia; Veloso, Maria A.F.; Reis, Patricia A.L.

2011-01-01

The IPR-R1 is a typical TRIGA Mark I light-water and open pool type reactor. The core has an annular configuration of six rings and is cooled by natural circulation. The core coolant channels extend from the bottom grid plate to the top grid plate. The cooling water flows through the holes in the bottom grid plate, passes through the lower unheated region of the element, flows upwards through the active region, passes through the upper unheated region, and finally leaves the channel through the differential area between a triangular spacer block on the top of the fuel element and a round hole in the grid. Direct measurement of the flow rate in a coolant channel is difficult because of the bulky size and low accuracy of flow meters. The flow rate through the channel may be determined indirectly from the heat balance across the channel using measurements of the water inlet and outlet temperatures. This paper presents the experiments performed in the IPR-R1 reactor to monitoring some thermo-hydraulic parameters in the core coolant channels, such as: the radial and axial temperature profile, temperature, velocity, mass flow rate, mass flux and Reynolds's number. Some results were compared with theoretical predictions, as it was expected the variables follow the power distribution (or neutron flux) in the core. (author)

Synthesis and Characterization of (η5-C5Me5)2Ti(R)Cl (R = Me, Et, n-Pr, CH=CH2, Ph, O-n-Pr) and Their Salt Metathesis Reactions. Thermal Decomposition Pathways of (η5-C5Me5)2Ti(Me)R' (R' = Et, CH=CH2, Ph, CH2Ph)

NARCIS (Netherlands)

Luinstra, Gerrit A.; Teuben, Jan H.

1992-01-01

Complexes Cp*2Ti(R)Cl (Cp* = η5-C5Me5; R = Me (1), Et (2), n-Pr (3), CH=CH2 (41, Ph (5), O-n-Pr (6)) have been prepared by oxidation of Cp*2TiR with lead dichloride. Not every compound Cp*2Ti(R)Cl was accessible and for R = CH2CMe3 and CH2Ph reduction to Cp*2TiCl and R· was observed. Homolysis of

Study of neutronic flux in IPR-R1 reactor with MCNPX; Estudo do fluxo neutronico no reator IPR-R1 com o MCNPX

Energy Technology Data Exchange (ETDEWEB)

Melo, J.A.S.; Castrillo, L.S., E-mail: julio.angelo@poli.br, E-mail: lazara@poli.br [Universidade de Pernambuco (UPE), Recife, PE (Brazil). Escola Politecnica; Oliveira, R.M.B.M., E-mail: romero.matias@educacao.pe.gov.br [Secretaria Executiva de Educacao do Estado de Pernambuco (SEE), Recife, PE (Brazil)

2016-11-01

MCNPX computer code, one of the latest versions of code MCNP transport were used to study the flux distribution and its neutronic fluence as a function of energy in two research reactor irradiation IPR-R1. The model developed was validated with research conducted by Dalle (2005). Initially, in the simulation is considered fresh fuel whose core configuration contained three neutron rods control, being two of them 100% ejected while the other inserted 3,1 x 10{sup -1} m deep, as adopted in the literature situation. The neutron source used was the critical type, through KSRC card. The results of the neutron flow and neutronic fluence were obtained in the central tube and the turntable on a range of energy spectrum that ranged from 1.0 x 10{sup -9} MeV to 10 MeV, showing good correlations with the model used in validation. Finally, a hypothetical situation wherein the three reactor control rods are ejected simultaneously was simulated. The simulation results showed an increase in the neutron flux of 7% in the central tube and 5% on the turntable.

Measurement and calculation of spatial and energetic neutron flux in the IEA-R1 reactor core

International Nuclear Information System (INIS)

Bittelli, U.D.

1988-01-01

This work presents spatial and energetic flux distribution measured in the IEA-R1 reactor core. The thermal neutron flux was measured by gold activation foils (bare and covered with cadmium) in the fuel element number 108 (reaction: 197 Au(n,γ) 198 Au) at 451W overall reactor power. The fast neutron flux was measured by indium activation foils (reaction: 115 In(n,n') 115m In) in the fuel elements number 94 at 4510W overall reactor power. The neutron energy spectrum was adjusted by SAND II code with the data produced by the irradiation of seven activation detectors in the fuel element number 94 at 4510 W overall reactor power. The following reactions were used: 58 Fe(n,γ) 59 Fe, 232 Th(n,γ) 233 Th, 197 Au(n,γ) 198 Au, 59 Co(n,γ) 60 Co, 54 Fe(n,p) 54 Mn, 24 Mg(n,p) 24 Na, 47 Ti(n,p) 47 Sc, 48 Ti(n,p) 48 Sc and 115 In(n,n') 115m In. The experimental results compared to those obtained by CITATION (spatial distribution flux) and HAMMER (energetic distribution flux) code, showed good agreement. The results presented in this work are a good contribution for a better knowledge of spatial and energetic neutron flux distribution in the IEA-R1 reactor core, besides that the experimental procedure is easily applicable to another situations. (autor) [pt

Automates programmables et réseaux de terrain conception des systèmes de régulation

CERN Document Server

Blanc, D

1998-01-01

Depuis le début des années 80, nous intégrons des automates programmables pour le contrôle des différents processus industriels. A l'origine, l'automate programmable était considéré comme une machine séquentielle, capable de suppléer des automatismes réalisés en logique traditionnelle, en apportant toutefois de profonds bouleversements dans la manière de concevoir et d'organiser le contrôle d'un processus. L'intégration de l'automate programmable renforce le degré de fiabilité de l'équipement et offre une très grande adaptabilité face aux évolutions de l'environnement. Aujourd'hui, l'automate programmable n'est plus seulement une machine séquentielle mais il est beaucoup plus considéré comme un calculateur de processus grâce aux énormes progrès quant à la structure de base, la qualité et la diversité des outils proposés. Son intégration sur Fieldbus (Profibus, WorldFip), sur Ethernet (Standard TCP-IP), accroît ses possibilités et constitue un passage obligé pour augmenter la...

Tassements référentiels sur la décharge réhabilitée d’Agadir et suivi des biogaz

Directory of Open Access Journals (Sweden)

Ahmed Elkadi

2014-04-01

Full Text Available La recirculation et réinjection des lixiviats dans le corps des anciens déchets, après leurs couverture finale, est mise en œuvre à titre d’essai sur une partie de la décharge réhabilité pour accélérer la biodégradation de la matière organique, augmenter la production des biogaz et par conséquent favoriser d’avantage la stabilité du massif des déchets. Afin d’assurer une valorisation et une exploitation rationnelle, au niveau environnemental et économique, les biogaz produits sur la première phase de l’ancienne décharge dont la réhabilitation est achevée, ont fait l’objet d’un suivit qualitatif et quantitatif continu et permanent de leurs production, toute en extrapolant les résultats pour la gestion future des biogaz du centre d’enfouissement des déchets de Tamellast. Pour une meilleure représentativité spatio-temporelle de la base de données, les fonctions avancées des Systèmes d’Information Géographiques ont été utilisées, dans le but d’analyser, gérer, structurer et communiquer l’information spatiale relative aux biogaz. En parallèle à ce suivi qualitatif et quantitatif, un suivi topographique annuel du massif des déchets enfouis au niveau de la zone dégazée a été réalisé – Topométrie classique-, les mêmes levés sont traités ultérieurement à partir d’un Modèle Numérique de Terrain (MNT, les résultats obtenu peuvent être extrapoler, dans un travail futur, pour la conception d’un modèle de prédiction des tassements des déchets ménagers dans les pays en voie de développement dans une démarche économique et sécuritaire. Le contrôle des tassements référentiels qui peuvent apparaitre avec le temps sur un massif des déchets réhabilité, permettra certainement de mieux contrôler les fuites des biogaz, et conserver les biens conçus avec la réhabilitation de l’ancienne décharge de la ville d’Agadir tel que les pistes de circulation, plantations etc.

Questions et réponses sur la GDE | IDRC - International ...

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

accentuent elles ? La région du Moyen-Orient et de l'Afrique du Nord (MOAN) est la région la plus pauvre en eau dans le monde. Les ressources d'eau renouvelables per capita sont actuellement de 1100 m3 par personne par ...

Le fictif et le réel dans L’Empereur et l’assassin de Chen Kaige

Directory of Open Access Journals (Sweden)

Xiaomin Giafferri

2008-12-01

Full Text Available Comme tout texte historique littéraire refait l’Histoire en la manipulant, le récit filmique est doublement mensongère du fait de sa double représentation : le décor et les acteurs représentent une situation qui est la fiction, et le film lui-même représente sous forme d’images juxtaposées cette première représentation. Sans vouloir faire la part du réel et de l’imaginaire, le présent travail tente de montrer comment, dans le film L’empereur et l’assassin de Chen Kaige, l’illusion de l’authenticité s’établit à travers les mécanismes de la fictionnalisation de l’Histoire. L’observation de leur manifestation est amenée à considérer deux axes principaux : l’organisation du récit et la mise en scène des personnages.

Dynamiques et rôle économique et social du secteur informel des ...

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

L'économie des pays en développement, africain notamment, est caractérisée par la coexistence d'un secteur formel et d'un autre dit informel. ... Ce projet vise à mieux comprendre le dynamique actuelle du secteur informel des TIC et le rôle économique et social qu'il joue au Burkina Faso, au Cameroun et au Sénégal, ...

Radio evidence for the initial stellar mass function in the R associations CMa R1, Mon R1, Mon R2

International Nuclear Information System (INIS)

Pyatunina, T.B.

1985-01-01

The R associations CMa R1 and Mon R1 have been searched for compact 7.6-cm sources with the RATAN-600 radio telescope. The Mon R1 region shows only about the expected number of background radio galaxies; in CMa R1 seven sources of small angular size with S> or =30 mJy have been found, two of them probably background objects. Comparison with optical data for CMa R1, together with previous RATAN-600 data for Mon R2, yields an initial mass function xi(M)proportionalM/sup -2.7plus-or-minus0.7/ for the rather massive (Mroughly-equal10 M/sub sun/) stars in these associations

Shadow corrosion evaluation in the Studsvik R2 reactor

International Nuclear Information System (INIS)

Sanders, Ch.; Lysell, G.

2000-01-01

Post-irradiation examination has shown that increased corrosion occurs when zirconium alloys are in contact with or in proximity to other metallic objects. The observations indicate an influence of irradiation from the adjacent component as the enhanced corrosion occurs as a 'shadow' of the metallic object on the zirconium surface. This phenomenon could ultimately limit the lifetime of certain zirconium alloy components in the reactor. The Studsvik R2 materials test reactor has an In-Core Autoclave (INCA) test facility especially designed for water chemistry and materials research. The INCA facility has been evaluated and found suitable for shadow corrosion studies. The R2 reactor core containing the INCA facility was modeled with the Monte Carlo N-Particle (MCNP) code in order to evaluate the electron deposition in various materials and to develop a hypothesis of the shadow corrosion mechanism. (authors)

The molten salt reactor: R and D status and perspectives in Europe

International Nuclear Information System (INIS)

Renault, Claude; Delpech, Sylvie; Merle-Lucotte, Elsa; Konings, Rudy; Hron, Miloslav; Ignatiev, Victor

2010-01-01

The paper concentrates on molten salt fast reactor (MSFR) concepts which are receiving most attention in the EU context. It shows the main R and D achievements and some remaining issues to be addressed in such essential areas as (a) reactor conceptual design, (b) molten salt properties, (c) fuel salt clean-up scheme and (d) high temperature materials. The status and perspectives of molten salt reactor R and D efforts in Europe are then discussed

Ageing Management Programme for the IEA-R1 Reactor in São Paulo, Brazil

Energy Technology Data Exchange (ETDEWEB)

Ramanathan, L. V. [Institute of Energy and Nuclear Research (IPEN), National Nuclear Energy Commission (CNEN), São Paulo (Brazil)

2014-08-15

IEA-R1 is a swimming pool type reactor. It is moderated and cooled by light water and uses graphite and beryllium as reflector elements. First criticality was achieved on 16 September 1957, and the reactor is currently operating at 4.0 MW on a 64 h per week cycle. In 1996, a reactor ageing study was established to determine general deterioration of systems and components such as cooling towers, secondary cooling system, piping, pumps, specimen irradiation devices, radiation monitoring system, fuel elements, rod drive mechanisms, nuclear and process instrumentation, and safety system. The basic structure of the reactor from the original design has been maintained, but several improvements and modifications have been made over the years to various components, systems and structures. During the period 1996–2005 the reactor power was increased from 2 MW to 5 MW and the operational cycle from 8 h per day for 5 days a week to 120 h continuous per week, mainly to increase production of {sup 99}Mo. Prior to increasing reactor power, several modifications were made to the reactor system and its components. Simultaneously, a vigorous ageing management, inspection and modernization programme was put in place.

IEA-R1 renewed primary coolant piping system stress analysis

International Nuclear Information System (INIS)

Fainer, Gerson; Faloppa, Altair A.; Oliveira, Carlos A. de; Mattar Neto, Miguel

2015-01-01

A partial replacement of the IEA-R1 piping system was conducted in 2014. The aim of this work is to perform the stress analysis of the renewed primary piping system of the IEA-R1, taking into account the as built conditions and the pipe modifications. The nuclear research reactor IEA-R1 is a pool type reactor designed by Babcox-Willcox, which is operated by IPEN since 1957. The primary coolant system is responsible for removing the residual heat of the Reactor core. As a part of the life management, a regular inspection detected some degradation in the primary piping system. In consequence, part of the piping system was replaced. The partial renewing of the primary piping system did not imply in major piping layout modifications. However, the stress condition of the piping systems had to be reanalyzed. The structural stress analysis of the primary piping systems is now presented and the final results are discussed. (author)

In-service inspection of ET-RR-1 reactor vessels and spent fuel storage tank

International Nuclear Information System (INIS)

Khattab, M.; Shafy, M.; Konoplev, K.; Samodurve, YU.; Orlov, S.; Didenko, V.; Jackorev, O.

1993-01-01

Technical survey included in-service inspection are needed in order to investigate the structural integrity and to insure safe operation of the ET-R R-1 reactor after thirty years aging. An intensive work for the inspection of the inspection of the central tank, shield tank, horizontal channels, primary coolant circuit and spent fuel storage tank have been carried out. The inspection procedures were visual method using video camera and magnification optical as well as thickness measurements using ultrasonic gauge meter and replica for determining defect depth. Water chemical analysis of the primary cooling circuit and spent fuel storage were helpful in results explanation. The results showed that the reactor vessels have good surface conditions. The observed pitting did not affect the structural integrity. The majority of the defects were pits having maximum surface area of about 50 mm. Their depth does not exceed 2 mm. The pits depth rate penetration is of the order of 0.5% per year. Thickness measurements showed insignificant variation. Water status and its chemical properties are very important in controlling corrosion rate. 18 figs., 14 tabs

Reactivity-worth estimates of the OSMOSE samples in the MINERVE reactor R1-UO2 configuration.

Energy Technology Data Exchange (ETDEWEB)

Klann, R. T.; Perret, G.; Nuclear Engineering Division

2007-10-03

An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R1-UO2 core configuration were completed. The reactor model was generated using the REBUS code developed at Argonne National Laboratory. The calculations are based on the specifications for fabrication, so they are considered preliminary until sampling and analysis have been completed on the fabricated samples. The estimates indicate a range of reactivity effect from -22 pcm to +25 pcm compared to the natural U sample.

Evaluation of the physical protection system of the IEA-R1 research reactor

International Nuclear Information System (INIS)

Vaz, Antonio C.A.; Conti, Thadeu das N.

2013-01-01

The '09/11' in New York and the accident at the Fukushima power plant are two events that served as worldwide reference to review some aspects of the Physical Protection System (PPS) in nuclear areas. The nuclear research reactor IEA-R1 has followed this new world order and improved the protection systems that are directly related to detection (CCTV, sensors, alarms, etc), delay (turnstile, gates, barriers, etc) and response (communication systems, response force, etc), for operation against malicious act, seeking always to avoid or minimize any possibility of threat, theft and sabotage. These actions were performed to prevent and to mitigate the consequence on the environment, economy and society from damages caused by natural hazard, as well. This study evaluates the PPS of the IEA-R1 regarding the weaknesses, strengths,and impacts of the changes resulting from the system implanted. The analyses were based on methodology developed by security experts from SANDIA National Laboratories in Texas - U.S.A, allowing the evaluation of the system through probabilistic and hypothetical analysis. (author)

Evaluation of the physical protection system of the IEA-R1 research reactor

Energy Technology Data Exchange (ETDEWEB)

Vaz, Antonio C.A.; Conti, Thadeu das N., E-mail: acavaz@ipen.br, E-mail: tnconti@yahoo.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

The '09/11' in New York and the accident at the Fukushima power plant are two events that served as worldwide reference to review some aspects of the Physical Protection System (PPS) in nuclear areas. The nuclear research reactor IEA-R1 has followed this new world order and improved the protection systems that are directly related to detection (CCTV, sensors, alarms, etc), delay (turnstile, gates, barriers, etc) and response (communication systems, response force, etc), for operation against malicious act, seeking always to avoid or minimize any possibility of threat, theft and sabotage. These actions were performed to prevent and to mitigate the consequence on the environment, economy and society from damages caused by natural hazard, as well. This study evaluates the PPS of the IEA-R1 regarding the weaknesses, strengths,and impacts of the changes resulting from the system implanted. The analyses were based on methodology developed by security experts from SANDIA National Laboratories in Texas - U.S.A, allowing the evaluation of the system through probabilistic and hypothetical analysis. (author)

Environmental issues associated with R Reactor renovation and startup

International Nuclear Information System (INIS)

Marter, W.L.

1982-01-01

This memorandum identifies the more significant environmental issues that would be associated with renovation and startup of R Reactor to meet future demands for nuclear weapon materials. Some key environmental issues identified are: potential occupational radiation exposures associated with repairing the leaks in the reactor nozzles and thermal shield tanks and with renovating the disassembly basin facilities; the impacts of constructing additional cooling water pumping capacity; the effect of increased pumping on impingement and entrainment at the pump houses; thermal effects on the R Canal-precooler pond-Par Pond ecosystem from increased discharge of cooling water; and effects of increased water flow in Lower Three Runs Creek on biota and on cesium-137 remobilization

Real time monitoring system of the operation variables of the TRIGA IPR-R1 nuclear research reactor

International Nuclear Information System (INIS)

Ricardo, Carla Pereira; Mesquita, Amir Zacarias

2007-01-01

During the last two years all the operation parameters of the TRIGA IPR-R1 were monitored and real time indicated bu the data acquisition system developed for the reactor. All the information were stored on a rigid disk, at the collection system computer, leaving the information on the reactor performance and behaviour available for consultation in a chronological order. The data acquisition program has been updated and new reactor operation parameters were included for increasing the investigation and experiments possibilities. The register of reactor operation variables are important for the immediate or subsequent safety analyses for reporting the reactor operations to the external organizations. This data acquisition satisfy the IAEA recommendations. (author)

Design of first reactor protection system prototype for C A R E M reactor

International Nuclear Information System (INIS)

Azcona, A; Lorenzo, G.; Maciel, F.; Fittipaldi, A

2006-01-01

In this paper we present the design of a prototype of the C A R E M Reactor Protection System, which is implemented on a basis of the digital platform T E L E P E R M X S.The proposed architecture for the Reactor Protection System (R P S) has 4 redundant trains composed by a complete set of sensors, a data acquisition computer and a processing computer.The information from the 4 processing computers goes into to a two voting units with a two out of four (2004) logic and its outputs are combined by a final actuation logic with a voting scheme of one out of two (1002).The prototype is implemented with a unique train.The train inputs are simulated by an Automatic Testing Unit.The pre-established test case or procedure results are fed back into the A T U.The choice of the digital platform T E L E P E R M X S for the R P S implementation allows versatility in the design stage and permits the prototype expansion due to its modular characteristic and the software tools flexibility [es

Final report on the IAEA research contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB

International Nuclear Information System (INIS)

Zobor, E.; Janosy, J.S.; Szentgali, A.

1980-09-01

The final report summarizes the research activities made in the framework of the IAEA Research Contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB. A multilevel hierarchical control system is treated which uses weakly-coupled low dimensional subsystems under the supervision of a dynamic coordinator program. This self-organizing adaptive control system was checked by a 5 MW research reactor. As an example the paper describes the experimental computer control system of the 5 MW WWR-SM research reactor, where the reactor power and outlet temperature have been controlled on the basis of the treated control concept since 1978. (author)

Thermal power calibrations of the IPR-R1 TRIGA reactor by the calorimetric and the heat balance methods

International Nuclear Information System (INIS)

Mesquita, Amir Zacarias; Rezende, Hugo Cesar; Souza, Rose Mary Gomes do Prado

2009-01-01

Since the first nuclear reactor was built, a number of methodological variations have been evolved for the calibration of the reactor thermal power. Power monitoring of reactors is done by means of neutronic instruments, but its calibration is always done by thermal procedures. The purpose of this paper is to present the results of the thermal power calibration carried out on March 5th, 2009 in the IPR-R1 TRIGA reactor. It was used two procedures: the calorimetric and heat balance methods. The calorimetric procedure was done with the reactor operating at a constant power, with primary cooling system switched off. The rate of temperature rise of the water was recorded. The reactor power is calculate as a function of the temperature-rise rate and the system heat capacity constant. The heat balance procedure consists in the steady-state energy balance of the primary cooling loop of the reactor. For this balance, the inlet and outlet temperatures and the water flow in the primary cooling loop were measured. The heat transferred through the primary loop was added to the heat leakage from the reactor pool. The calorimetric method calibration presented a large uncertainty. The main source of error was the determination of the heat content of the system, due to a large uncertainty in the volume of the water in the system and a lack of homogenization of the water temperature. The heat balance calibration in the primary loop is the standard procedure for calibrating the power of the IPR-R1 TRIGA nuclear reactor. (author))

Ponction biopsies rénales dans le Service de Néphrologie de Fès: indications et résultats: à propos de 522 cas

Science.gov (United States)

Mbarki, Houda; Belghiti, Khadija Alaoui; Harmouch, Taoufiq; Najdi, Adil; Arrayhani, Mohamed; Sqalli, Tarik

2016-01-01

L'apport de la ponction biopsie rénale (PBR) dans le diagnostic, le choix thérapeutique et l’évaluation pronostique des néphropathies est considérable. Aucune étude marocaine n'a évalué la pratique et l'apport de la PBR. Notre objectif est d’étudier les indications de la PBR, déterminer la fréquence des maladies rénales identifiées par PBR dans notre région et de faire une confrontation entre les données clinico-biologiques et le diagnostic historique. Notre étude menée entre Janvier 2009 et Décembre 2012, est rétrospective. Nous avons inclus tous les patients du service de Néphrologie du CHU Hassan II de Fès ayant bénéficié d'une biopsie de reins natifs. 522 PBR ont été réalisées. Nous avons exclu 8 biopsies devant le manque de renseignements et avons donc retenu 514. L’âge moyen des patients au moment de la PBR est de 39 ±17 ans (3-82 ans). Le sex ratio est de 0,9. Le syndrome néphrotique est le diagnostic clinique le plus fréquent à tous les âges (58,2%). Les néphropathies glomérulaires représentent 94,2% des maladies rénales diagnostiquées, leur distribution varie selon l’âge des patients. La PBR a confirmé le premier diagnostic suspecté cliniquement dans 40,65% des cas, alors qu'elle a révélé un diagnostic inattendu chez 22,5% d'entre eux. Le diagnostic syndromique permet d'orienter vers la maladie rénale la plus probable et de guider les thérapeutiques urgentes en attendant les résultats de la PBR. Mais il ne peut en aucun remplacer la PBR qui reste le gold standard. PMID:27583085

Electromagnétisme fondements et applications : avec 300 exercices et problèmes résolus

CERN Document Server

Pérez, José-Philippe; Fleckinger, Robert

1997-01-01

Cet ouvrage fait partie de ceux qui l'on acquiert dès le début de ses études et que l'on conserve comme ouvrage de référence. Il rassemble en un seul volume les notions fondamentales de l'électromagnétisme et des diverses applications en physique. Il est construit en 30 chapîtres très structurés et illustrés de nombreux exercices et problèmes résolus. Le public Etudiants des DEUG Sciences (SM, MIAS, ST et SV) Etudiants des classes préparatoires (MP, PC, PSI) Etudiants des licences de physique Candidats aux concours d'enseignement.

Experiment of IEA-R1 reactor core cooling by air convection after pool water loss accident

International Nuclear Information System (INIS)

Torres, Walmir Maximo; Baptista Filho, Benedito Dias

2000-01-01

This paper presents a study of a Emergency Core Cooling to be applied to the IEA-R1 reactor. This system must have the characteristics of passive action, with water spraying over the core, and feeding by gravity from elevated reservoirs. In the evaluation, this system must demonstrate that when the reservoirs are emptied, the core cooling must assure to be fulfilled by air natural convection. This work presents the results of temperature distribution in a test section with plates electrically heated simulation the heat generation conditions on the most heated reactor element

Populations, espace et infrastructures : réduire la violence urbaine ...

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

Populations, espace et infrastructures : réduire la violence urbaine et favoriser la justice à Mumbai, Rio et Durban. Dans notre monde en ... Despite constitutional guarantees, violence both within and outside the home is an ever-present threat and an everyday reality for a large majority of women and girls across India.

International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor

Energy Technology Data Exchange (ETDEWEB)

Hainoun, A., E-mail: pscientific2@aec.org.sy [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Doval, A. [Nuclear Engineering Department, Av. Cmdt. Luis Piedrabuena 4950, C.P. 8400 S.C de Bariloche, Rio Negro (Argentina); Umbehaun, P. [Centro de Engenharia Nuclear – CEN, IPEN-CNEN/SP, Av. Lineu Prestes 2242-Cidade Universitaria, CEP-05508-000 São Paulo, SP (Brazil); Chatzidakis, S. [School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States); Ghazi, N. [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Park, S. [Research Reactor Design and Engineering Division, Basic Science Project Operation Dept., Korea Atomic Energy Research Institute (Korea, Republic of); Mladin, M. [Institute for Nuclear Research, Campului Street No. 1, P.O. Box 78, 115400 Mioveni, Arges (Romania); Shokr, A. [Division of Nuclear Installation Safety, Research Reactor Safety Section, International Atomic Energy Agency, A-1400 Vienna (Austria)

2014-12-15

Highlights: • A set of advanced system thermal hydraulic codes are benchmarked against IFA of IEA-R1. • Comparative safety analysis of IEA-R1 reactor during LOFA by 7 working teams. • This work covers both experimental and calculation effort and presents new out findings on TH of RR that have not been reported before. • LOFA results discrepancies from 7% to 20% for coolant and peak clad temperatures are predicted conservatively. - Abstract: In the framework of the IAEA Coordination Research Project on “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal hydraulic computational methods and tools for operation and safety analysis of research reactors” the Brazilian research reactor IEA-R1 has been selected as reference facility to perform benchmark calculations for a set of thermal hydraulic codes being widely used by international teams in the field of research reactor (RR) deterministic safety analysis. The goal of the conducted benchmark is to demonstrate the application of innovative reactor analysis tools in the research reactor community, validation of the applied codes and application of the validated codes to perform comprehensive safety analysis of RR. The IEA-R1 is equipped with an Instrumented Fuel Assembly (IFA) which provided measurements for normal operation and loss of flow transient. The measurements comprised coolant and cladding temperatures, reactor power and flow rate. Temperatures are measured at three different radial and axial positions of IFA summing up to 12 measuring points in addition to the coolant inlet and outlet temperatures. The considered benchmark deals with the loss of reactor flow and the subsequent flow reversal from downward forced to upward natural circulation and presents therefore relevant phenomena for the RR safety analysis. The benchmark calculations were performed independently by the participating teams using different thermal hydraulic and safety

Anticoking Coatings for High Temperature Petrochemical Reactors Revêtements pour réacteurs pétrochimiques à cokage réduit

Directory of Open Access Journals (Sweden)

Ropital F.

2006-12-01

Full Text Available Coke deposition is a major problem for several refinery and petrochemical processes, among which steam cracking for ethylene production. Decreasing coking rates will reduce decoking frequency and will also decrease heat transfer degradation. For these processes, a means of reducing coking phenomena is the application of anticoking coatings on the reactor walls. For this purpose a methodology was developed under a CEC Brite-Euram project with steam cracking as the main application. A first selection of the coatings and their techniques of deposition was performed according to their composition (non catalytic compounds, their resistance to carburization and oxidation and also according to the nature of the substrate. The feasibility of coating deposition was studied for small diameter furnace tubes and the techniques were perfected in particular with respect to the physicochemical characterization of the coatings and their resistance during thermal cycling and coking-decoking cycles. For the thermal cycling and the coking evaluation, industrial conditions were reproduced as closely as possible. For coking tests, a microreactor with complete mixing of the gas phase was developed for temperatures up to 950°C. The coking behavior of the coated samples was compared with conventional refractory alloys: reduction of the coking rate by a factor of 3 was measured with the most promising coating. This work was completed by the kinetic modelling of coking on uncoated materials. La formation de coke est un problème crucial pour de nombreux procédés pétrochimiques. Ralentir le cokage permet de réduire la fréquence des décokages et de limiter la dégradation du transfert thermique. Un des moyens envisageables pour réduire le cokage est le dépôt d'un revêtement à la paroi de ces réacteurs. La mise au point de tels revêtements a fait l'objet d'un projet de recherche européen Brite-Euram, pour lequel le vapocraquage a été la principale

Le fictif et le réel dans L’Empereur et l’assassin de Chen Kaige

OpenAIRE

Giafferri, Xiaomin

2008-01-01

Comme tout texte historique littéraire refait l’Histoire en la manipulant, le récit filmique est doublement mensongère du fait de sa double représentation : le décor et les acteurs représentent une situation qui est la fiction, et le film lui-même représente sous forme d’images juxtaposées cette première représentation. Sans vouloir faire la part du réel et de l’imaginaire, le présent travail tente de montrer comment, dans le film L’empereur et l’assassin de Chen Kaige, l’illusion de l’authen...

Characterization of cartridge filters from the IEA-R1 Nuclear Reactor

International Nuclear Information System (INIS)

2015-01-01

The management of radioactive waste ensures safety to human health and the environment nowadays and for the future, without overwhelming the upcoming generations. The primary characterization of radioactive waste is one of the main steps in the management of radioactive waste. This step permits to choose the best treatment for the radioactive waste before forwarding it to its final disposal. The aim of the present work is the primary characterization of cartridge filters from the IEA-R1 nuclear reactor utilizing gamma-ray spectrometry, and the method of Monte Carlo for calibration. The IEA-R1 is located in the Nuclear and Energy Research Institute (IPEN - CNEN) in the city of Sao Paulo, Brazil. Cartridge filters are used for purification of the cooling water that is pumped through the core of the pool type nuclear research reactors. Once worn out, these filters are replaced and then become radioactive waste. Determination of the radioactive inventory is of paramount importance in the management of such radioactive waste, and one of the main methods for doing so is the gamma-ray spectrometry, which can identify and quantify high energy photon emitters. The technique chosen for the characterization of radioactive waste in the present work is the gamma-ray spectrometry with High purity Germanium (HPGe) detectors. From the energy identified in the experimental spectrum, three radioisotopes were identified in the cartridge filter: 108m Ag, 110m Ag, 60 Co. For the estimated activity of the filter, the calibration in efficiency was made utilizing the MCNP4C code of the Monte Carlo method. Such method was chosen because there is no standard source available in the same geometry of the cartridge filter, therefore a simulation had to be developed in order to reach a calibration equation, necessary to estimate the activity of the radioactive waste. The results presented an activity value in the order of MBq for all radioisotopes. (authors)

Characterization of cartridge filters from the IEA-R1 Nuclear Reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-07-01

The management of radioactive waste ensures safety to human health and the environment nowadays and for the future, without overwhelming the upcoming generations. The primary characterization of radioactive waste is one of the main steps in the management of radioactive waste. This step permits to choose the best treatment for the radioactive waste before forwarding it to its final disposal. The aim of the present work is the primary characterization of cartridge filters from the IEA-R1 nuclear reactor utilizing gamma-ray spectrometry, and the method of Monte Carlo for calibration. The IEA-R1 is located in the Nuclear and Energy Research Institute (IPEN - CNEN) in the city of Sao Paulo, Brazil. Cartridge filters are used for purification of the cooling water that is pumped through the core of the pool type nuclear research reactors. Once worn out, these filters are replaced and then become radioactive waste. Determination of the radioactive inventory is of paramount importance in the management of such radioactive waste, and one of the main methods for doing so is the gamma-ray spectrometry, which can identify and quantify high energy photon emitters. The technique chosen for the characterization of radioactive waste in the present work is the gamma-ray spectrometry with High purity Germanium (HPGe) detectors. From the energy identified in the experimental spectrum, three radioisotopes were identified in the cartridge filter: {sup 108m}Ag, {sup 110m}Ag, {sup 60}Co. For the estimated activity of the filter, the calibration in efficiency was made utilizing the MCNP4C code of the Monte Carlo method. Such method was chosen because there is no standard source available in the same geometry of the cartridge filter, therefore a simulation had to be developed in order to reach a calibration equation, necessary to estimate the activity of the radioactive waste. The results presented an activity value in the order of MBq for all radioisotopes. (authors)

Studsvik's R2 reactor - Review of activities

Energy Technology Data Exchange (ETDEWEB)

Grounes, Mikael; Tomani, Hans; Graeslund, Christian; Rundquist, Hans; Skoeld, Kurt [Studsvik Nuclear AB, Nykoeping (Sweden)

1993-07-01

A general description of the R2 reactor, its associated facilities and its history is given. The facilities and range of work are described for the following types of activities: fuel testing, materials testing, neutron transmutation doping of silicon, activation analysis, radioisotope production and basic research including thermal neutron scattering, nuclear chemistry and neutron capture radiography. (author)

Neutrons characterization of the nuclear reactor Ian-R1 of Colombia

International Nuclear Information System (INIS)

Gonzalez P, L. X.; Martinez O, S. A.; Vega C, H. R.

2014-08-01

By means of Monte Carlo methods, with the code MCNPX, the neutron characteristics of the research nuclear reactor Ian-R1 of Colombia, in power off but with the neutrons source in their start position, have been valued. The neutrons spectra, the total flow and their average power were calculated in the irradiation spaces inside the graphite reflector, as well as in the cells with air. Also the spectra, the total flow and the absorbed dose were calculated in several places distributed along the radial shaft inside the water moderator. The neutrons total flow was also considered to the long of the axial shaft. The characteristics of the neutrons spectra vary depending on their position regarding the source and the material that surrounds to the cell where the calculation was made. (Author)

Analysis of the IEA-R1 reactor start-up procedures - an application of the HazOp method

International Nuclear Information System (INIS)

Sauer, Maria Eugenia Lago Jacques

2000-01-01

An analysis of technological catastrophic events that took place in this century shows that human failure and vulnerability of risk management programs are the main causes for the occurrence of accidents. As an example, plants and complex systems where the interface man-machine is close, the frequency of failures tends to be higher. Thus, a comprehensive knowledge of how a specific process can be potentially hazardous is a sine qua non condition to the operators training, as well as to define and implement more efficient plans for loss prevention and risk management. A study of the IEA-R1 research reactor start-up procedures was carried out, based upon the methodology Hazard and Operability Study (HazOp). The analytical and qualitative multidisciplinary HazOp approach provided means to a comprehensive review of the reactor start-up procedures, contributing to improve the understanding of the potential hazards associated to deviations on performing this routine. The present work includes a historical summary and a detailed description of the HazOp technique, as well as case studies in the process industries and the use of expert systems in the application of the method. An analysis of 53 activities of the IEA-R1 reactor start-up procedures was made, resulting in 25 recommendations of changes covering aspects of the project, operation and safety of the reactor. Eleven recommendations have been implemented. (author)

Intérêts de la description des variantes vasculaires avant chirurgie hépatique pancréatique et rénale

OpenAIRE

Leloup , Sarah Smahel

2015-01-01

Non disponible / Not available; Une imagerie complète associant au moins un scanner multi-phasique et une IRM doit être réalisée avant toute chirurgie hépatique (pour carcinome hépato-cellulaire ou métastasectomie hépatique), transplantation hépatique, duodéno-pancréatectomie céphalique, et avant toute greffe rénale. Elle n’a plus seulement pour but de fournir des éléments de caractérisation lésionnelle, elle devient à la base du bilan de résécabilité des lésions et d’opérabilité des patients...

The IPR-R1 TRIGA Mark I Reactor in 39 years: Operations and general improvements

International Nuclear Information System (INIS)

Maretti Junior, Fausto; Prado Fernandes, Marcio; Oliveira, Paulo Fernando; Alves de Amorim, Valter

1999-01-01

The nuclear IPR-R1 TRIGA Mark I Reactor operating in the Nuclear Technology Development Center, originally Institute for Radioactive Research in Minas Gerais, Brazil, was dedicated in November 11, 1960. Initially operating for the production of radioisotopes for different uses, it started later to be used in large scale for neutron activation analysis and training of operators for nuclear power plants. Many improvements have been made throughout these years to provide a better performance in its operation and safety conditions. A new cooling system to operate until 300 kW, a new control rod mechanism, an aluminum tank for the reactor pool, an optimization in the pneumatic system, a new reactor control console and a general remodeling of the reactor laboratory were some of the improvements added. To prevent and mitigate the ageing effects, the reactor operation personnel is starting a program to minimize future operation problems. This paper describes the improvements made, the results obtained during the past 39 years, and the precautions taken to ensure future safe operation of the reactor to give operators better conditions of safe work. (author)

Trajets quotidiens et récits délinquants

Directory of Open Access Journals (Sweden)

Michael Sheringham

2007-08-01

Full Text Available Dossier/Issue: 1 - Raconter le quotidien aujourd'hui - Si l’expérience de la quotidienneté, qui préoccupe un philosophe comme Henri Lefebvre ou un écrivain comme Georges Perec, semble résister à l’emprise du roman, Michel de Certeau a pu mettre une réflexion sur le récit au cœur de son essai fondamental, L’invention du quotidien. En effet, les notions de « récits délinquants » ou d’« énonciations piétonnières », chez Certeau, fournissent des outils précieux pour l’élucidation du rôle du récit dans des textes qui interrogent le monde quotidien à partir de pérégrinations et de méditations urbaines, dont certains exemples majeurs sont traités ici : Un ethnologue dans le métro (Marc Augé, Journal du dehors (Annie Ernaux, Les passagers du Roissy-Express (François Maspero, La liberté des rues (Jacques Réda.If the experience of everydayness, which preoccupied a philosopher like Henri Lefebvre and a writer like Georges Perec, seem to resist the sway of the novel, Michel de Certeau nonetheless placed a consideration of narrative at the heart of his seminal essay Practices of Everyday Life. And indeed such notions as "delinquent narratives" and "pedestrian speech acts", elaborated by Certeau, provide precious tools for identifying the role of narrative in texts which interrogate the everyday world on the basis of urban peregrinations and meditations, of which some major examples are examined here : An Ethnologist in the Metro (Marc Augé, Exteriors (Annie Ernaux, Roissy-Express : A Journey Through the Paris Suburbs (François Maspero, The Freedom of the Streets (Jacques Réda.

Feasibility studies of producing 99 Mo by capture in the IEA-R1 research reactor

International Nuclear Information System (INIS)

Concilio, Roberta; Mendonca, Arlindo Gilson; Maiorino, Jose Rubens

1998-01-01

Everyday the production of 99 Mo for 99m Tc generators, becomes more necessary, whose properties are ideal for medical diagnosis. This works presents a description and an analysis of the production of 99 Mo by radioactive capture at 98 Mo using the research reactor IEA-R1 in 5 MW and operating 5 days a week, referring to the use of targets, separation methods, total and specific activity attained and its limitations. (author)

Trouver l'équilibre entre les soins non rémunérés et le travail ...

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

limiter leurs choix et leurs options en matière d'emploi. ... L'équipe de recherche utilisera les résultats obtenus pour donner des conseils stratégiques sur la façon dont les politiques et programmes étatiques et non étatiques d'autonomisation économique des femmes peuvent cadrer avec la prestation de soins non ...

Isothermal (vapour + liquid) equilibrium for the binary {l_brace}1,1,2,2-tetrafluoroethane (R134) + propane (R290){r_brace} and {l_brace}1,1,2,2-tetrafluoroethane (R134) + isobutane (R600a){r_brace} systems

Energy Technology Data Exchange (ETDEWEB)

Dong Xueqiang [Key Laboratory of Cryogenics, Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, P.O. Box 2711, Beijing 100190 (China); Graduate University of Chinese Academy of Sciences, Beijing 100039 (China); Gong Maoqiong, E-mail: gongmq@mail.ipc.ac.c [Key Laboratory of Cryogenics, Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, P.O. Box 2711, Beijing 100190 (China); Liu Junsheng [Key Laboratory of Cryogenics, Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, P.O. Box 2711, Beijing 100190 (China); Graduate University of Chinese Academy of Sciences, Beijing 100039 (China); Wu Jianfeng, E-mail: jfwu@mail.ipc.ac.c [Key Laboratory of Cryogenics, Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, P.O. Box 2711, Beijing 100190 (China)

2010-09-15

(Vapour + liquid) equilibrium (VLE) data for the binary systems of {l_brace}1,1,2,2-tetrafluoroethane (R134) + propane (R290){r_brace} and {l_brace}1,1,2,2-tetrafluoroethane (R134) + isobutane (R600a){r_brace} were measured with a recirculation method at the temperatures ranging from (263.15 to 278.15) K and (268.15 to 288.15) K, respectively. All of the data were correlated by the Peng-Robinson (PR) equation of state (EoS) with the Huron-Vidal (HV) mixing rules utilizing the non-random two-liquid (NRTL) activity coefficient model. Good agreement can be found between the experimental data and the correlated results. Azeotropic behaviour can be found at the measured temperature ranges for these two mixtures.

Progrès de l'intégration régionale, rôle et stratégie du Groupe de la

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

mgv3643

8 déc. 2009 ... 1. Progrès de l‟Intégration Régionale,. Rôle et Stratégie du Groupe de la Banque Africaine de Développement dans la promotion de l‟intégration régionale en Afrique. Gabriel Mougani. Département NEPAD, Intégration Régionale et Commerce ...

Renforcement des droits fonciers communautaires et réactions aux ...

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

De telles menaces qui planent sur les droits fonciers et environnementaux des collectivités sont un indice de tensions plus grandes au sein de l'appareil d'État et du système de justice. Dans ce ... Des droits internationaux aux pratiques locales : la réforme constitutionnelle et la participation en Amérique latine. Ce projet ...

Application of safety checklist to the analysis of the IEA-R1 reactor water retreatment system; Utilizacao do checklist de seguranca na analise do sistema de retratamento de agua do reator IEA-R1

Energy Technology Data Exchange (ETDEWEB)

Sauer, Maria Eugenia Lago Jacques; Sara Neto, Antonio Jorge; Lima, Toni Carlos Caboclo de; Ribeiro, Maria Alice Morato [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: melsauer@ipen.br

2005-07-01

In 1999, the management of the IEA-R1 Research Reactor (pool type - 5 MWth), located at IPEN/CNEN-SP, started the evaluation of the Reactor Pool Water Retreatment System to identify operational aspects, which could compromise the operators safety. The purpose was to identify and propose enhancements to the system which would be installed to substitute for the existing one. This process was conducted through a qualitative study of the system in operation. This study was carried out by a team composed of specialists in reactor operation, systems maintenance and radiological protection, and one safety analyst. The study consisted, basically, in local inspections to verify the physical and operational conditions of each equipment / component as well as aspects related to maintenance activities of the system. The process control and the operator procedures associated with the retreatment of the reactor pool water were also reviewed. The methodology adopted to develop the study was based in process hazard analysis technique named Safety Checklist. This paper presents a summary of this study and the main results obtained. Some operational and safety problems identified, the prevention and/or correction means to avoid them, and the recommendations and suggestions that have been implemented to the new design of the IEA-R1 Reactor Water Retreatment System, whose installation was concluded in 2003, are also presented. (author)

Thermal neutron flux measurements in the rotary specimen rack of the IPR-R1 TRIGA reactor

Energy Technology Data Exchange (ETDEWEB)

Souza, Rose Mary G. do Prado; Rodrigues, Rogério R.; Souza, Luiz Claudio A., E-mail: souzarm@cdtn.br, E-mail: rrr@cdtn.br, E-mail: lcas@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The thermal neutron flux in the rotary specimen rack of the IPR-R1 TRIGA reactor at the Nuclear Technology Development Center (CDTN), Belo Horizonte, Brazil, has been measured by the neutron activation method, using bare and cadmium covered gold foils. Those foils were irradiated in the rotary specimen rack with the reactor at 100 kW. The reactor core configuration has 63 fuel elements, composed of 59 original aluminum-clad elements and 4 stainless steel-clad fuel elements. The gamma activities of the foils were measured using Ge spectrometer. The perturbations of the thermal neutron flux caused by the introduction of an absorbing foil into the medium were considered in order to obtain accurate determination of the flux. The thermal neutron flux obtained was 7.4 x 10{sup 11} n.cm{sup -2}.s{sup -1}. (author)

Relativité fondements et applications : avec 150 exercices et problèmes résolus

CERN Document Server

Pérez, José-Philippe

1999-01-01

Cet ouvrage rassemble, en un seul volume, les fondements de la relativité auxquels ont été ajoutés quelques compléments, de nombreux exemples d'illustration et 150 exercices et problèmes résolus. Il est structuré en dix chapitres, dont les trois derniers (physique nucléaire, électromagnétisme et relativité, gravitation et relativité) peuvent être considérés comme des prolongements culturels. Il s'adresse aux étudiants des trois premières années d'études supérieures : DEUG, ENSI-DEUG et licences. En effet leurs connaissances, que ce soit en mathématiques, en mécanique, en électromagnétisme ou en optique, suffisent largement pour comprendre les fondements et les applications physiques de cette théorie du XXe siècle. En raison de son découpage en leçons structurées, quasi autonomes, et de l'accent mis sur le développement des idées, ce livre devrait également intéresser les candidats aux concours d'enseignement (CAPES et agrégation).

R and D on fast reactor fuel reprocessing

International Nuclear Information System (INIS)

Subba Rao, R.V.; Vijaya Kumar, V.; Natarajan, R.

2012-01-01

Development of Fast Reactor Fuel Reprocessing technology, with low out of pile inventory, is carried out at the Indira Gandhi Centre for Atomic Research (IGCAR). Based on the successful R and D programme which addressed specific issues of fast reactor fuels, a pilot plant called CORAL was set up. This plant is operational since 2003 and several reprocessing campaigns with spent FBTR fuels of varying burnups have been carried out. Based on the valuable operating experience of CORAL, the design of demonstration fast reactor fuel reprocessing plant (DFRP) and the commercial reprocessing plant, FRP have been taken up. Concurrently R and D efforts are continuing for improving the process and equipment performance apart from reducing the waste volumes and the radiation exposures to the operating personnel. Some important R and D efforts are highlighted in the paper. Reducing the dissolution time is one of the vital area of investigation especially for the high plutonium bearing MOX fuels which are known to dissolve slowly. To address this as well as criticality issues, continuous dissolvers are being developed. Solvent extraction based process is employed for getting highly pure nuclear grade uranium and plutonium. In view of the lower cooling time the fission product activity in the spent fuel is higher, formulation of process flowsheet with reduced number of solvent extraction cycles to improve the decontamination of ruthenium and zirconium without the formation of second organic phase due to plutonium loading, is under investigation. Retention of plutonium in lean organic is another issue to be addressed as otherwise it would lead to further deterioration of the solvent on storage. Several reagents to effectively wash the lean solvent have been investigated and flowsheets have been formulated to recover the retained plutonium with minimum secondary wastes. Partitioning of uranium and plutonium is an important step and methods reported in the literature have inherent

Multiphase Reactors: Models and Experimental Verification Les réacteurs polyphasés : modèles et vérification expérimentale

Directory of Open Access Journals (Sweden)

Dudukovic M. P.

2006-11-01

implementation of a convection dispersion model. The planned implementation of fan-beam tomography would quantify the two-dimensional holdup distribution and together with CARPT provide all the data necessary for verification of fundamental two phase flow models. Pressure drop, holdup, flow regime transition and phase distribution in trickle-beds has received considerable attention but no generally accepted theory for prediction of these quantities exists. Here we describe a phenomenological model for the low interaction regime which views the bed as an array of slits with liquid film flow. Universal velocity profile is used to describe the flow in both liquid films and the gas core and a large data bank for pressure drop and holdup was used to confirm that in the low interaction regime each of the two phases ignores the presence of the other one. The final model contains only two parameters, which are determined from single phase flow experiments, and contains no constants fitted to two phase flow data. The model predicts pressure drop and holdup in the uniform low interaction regime better than any of the existing models. Furthermore, introducing the Kapitza's criterion for laminar liquid film instability into the model the flow regime transition to pulsing is predicted well for all the data that satisfy the conditions for the theory to apply. Other pore level transition mechanisms are suspected for other data. The above phenomenological model is also used as a basis for predicting liquid distribution in a cell model of a trickle-bed. Experimental confirmation awaits the application of PET technology. L'identification et la quantification des régimes, des distributions des rétentions de phase, des schémas de flux et du mélange en retour sont d'une importance primordiale pour extrapoler à l'échelle et concevoir correctement les réacteurs polyphasés. Les modèles existants sont, malheureusement, bien souvent étayés par des résultats expérimentaux inadéquats. Nous d

Equipment for thermal neutron flux measurements in reactor R2

Energy Technology Data Exchange (ETDEWEB)

Johansson, E; Nilsson, T; Claeson, S

1960-04-15

For most of the thermal neutron flux measurements in reactor R2 cobalt wires will be used. The loading and removal of these wires from the reactor core will be performed by means of a long aluminium tube and electromagnets. After irradiation the wires will be scanned in a semi-automatic device.

Management of European fast reactor R and D

International Nuclear Information System (INIS)

Judd, A.M.; Sheriff, N.

1993-01-01

Since 1984 government-funded fast reactor R and D in France, Germany and the UK has been run as a collaborative activity, and since 1988 as a unified programme in support of the design and construction of the advanced European Fast Reactor. This paper describes the international management structure which has been set up, and the means used to control the work. It is written from the point of view of those engaged in the project, and makes no attempt at a formal analysis of the structure. The main difficulty is that control of funding remains with the three governments. The R and D programme has to be managed so that it meets the needs of each government separately as well as the designers' requirements. To start with the management structure was excessively bureaucratic, but it has become more flexible and efficient. This has happened as the initial nationalistic suspicions have broken down, and the staff engaged in the work have learnt more about each others' ways of working so that an atmosphere of trust and inter-dependence has grown up. (This paper was written before the changes in UK policy on fast reactor development were announced in November 1992). (Author)

Water chemical control of the TRIGA IPR-R1 reactor primary cooling system

International Nuclear Information System (INIS)

Auler, Lucia M.L.A; Chaves, Renata D.A.; Palmieri, Helena E.L.; Menezes, Maria Angela de B.C.; Oliveira, Paulo F.; Kastner, Geraldo F.; Damazio, Ilza; Fagundes, Oliene dos R.; Cintra, Maria Olivia C.; Andrade, Geraldo V. de; Amaral, Angela M.; Franco, Milton B.; Fortes, Flavio; Gomes, Nilton Carlos; Vidal, Andrea; Maretti Junior, Fausto; Knupp, Eliana A.N.; Souza, Wagner de; Guedes, Joao B.; Furtado, Renato C.S.

2013-01-01

The TRIGA Mark I IPR-R1 reactor located at CDTN/CNEN has been in operation and contributed to research and with services to society since 1960. Is has been used in several activities such as nuclear power plant operation, graduate and post-graduate training courses, isotope production, and as an analytical irradiation tool of different types of samples. Among the several structural and operational safety requirements is the chemical quality control of the primary circuit cooling water. The aim of this work was to check the cooling water quality from the pool reactor. A water sampling plan was proposed (May, 2011 - June, 2012) and presents the results obtained in this period. The natural radioactivity level as gross alpha and gross beta activity and other chemical parameters (pH and electric conductivity) of the samples were analyzed. Some instrumental techniques were used: potentiometric methods (pH), conductometric methods (electrical conductivity, EC) and gross α and gross β proportional counting system). (author)

Adaptation, eau et résilience dans l'Himalaya | IDRC - International ...

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

Comment ce projet appuiera-t-il l'adaptation? Les changements socioéconomiques, combinés aux répercussions des changements climatiques, pourraient porter gravement atteinte aux moyens de subsistance de toute la population de la région. Pour aider les populations du Pakistan, de l'Inde, du Bangladesh et du Népal ...

MiR-223 suppresses cell proliferation by targeting IGF-1R.

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Cheng You Jia

Full Text Available To study the roles of microRNA-223 (miR-223 in regulation of cell growth, we established a miR-223 over-expression model in HeLa cells infected with miR-223 by Lentivirus pLL3.7 system. We observed in this model that miR-223 significantly suppressed the proliferation, growth rate, colony formation of HeLa cells in vitro, and in vivo tumorigenicity or tumor formation in nude mice. To investigate the mechanisms involved, we scanned and examined the potential and putative target molecules of miR-223 by informatics, quantitative PCR and Western blot, and found that insulin-like growth factor-1 receptor (IGF-1R was the functional target of miR-223 inhibition of cell proliferation. Targeting IGF-1R by miR-223 was not only seen in HeLa cells, but also in leukemia and hepatoma cells. The downstream pathway, Akt/mTOR/p70S6K, to which the signal was mediated by IGF-1R, was inhibited as well. The relative luciferase activity of the reporter containing wild-type 3'UTR(3'untranslated region of IGF-1R was significantly suppressed, but the mutant not. Silence of IGF-1R expression by vector-based short hairpin RNA resulted in the similar inhibition with miR-223. Contrarily, rescued IGF-1R expression in the cells that over-expressed miR-223, reversed the inhibition caused by miR-223 via introducing IGF-1R cDNA that didn't contain the 3'UTR. Meanwhile, we also noted that miR-223 targeted Rasa1, but the downstream molecules mediated by Rasa1 was neither targeted nor regulated. Therefore we believed that IGF-1R was the functional target for miR-223 suppression of cell proliferation and its downstream PI3K/Akt/mTOR/p70S6K pathway suppressed by miR-223 was by targeting IGF-1R.

Valeur économique totale des récifs coralliens, mangroves et herbiers de la Martinique

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Pierre Failler

2012-04-01

Full Text Available La Martinique possède 55 km2 de récifs coralliens, 50 d’herbiers et 20 de mangroves. Ces trois écosystèmes produisent des biens et services dont la valeur est estimée à quelque 250 millions d’euros par an. Près de 60% de cette valeur est issue des usages directs liés aux activités récréatives (plongée, excursion, récréation balnéaire induites pour l’essentiel par le tourisme et celles liées à la pêche (professionnelle et de plaisancière. Les services écosystémiques (assimilés aux usages indirects tels que la protection des côtes, l’absorption/séquestration de carbone, la production de biomasse de poissons et l’épuration de l’eau sont conséquents puisque leur valeur annuelle s’élève à 94 millions € soit 38% de la valeur totale. La valeur de ce qui a trait au non-usage des récifs, herbiers et mangroves (lié à la volonté de transmettre un patrimoine écologique pour l’essentiel ou encore à la satisfaction de savoir que les récifs sont en bon état se traduit par une création de valeur de l‘ordre de 10 million €/an. Les herbiers et les mangroves  contribuent le plus (par km2 à la création de valeur (respectivement 2,16 millions €/km2, 1,87 million €/km2 contre 1,78 million €/km2 pour les récifs. Ils doivent donc bénéficier de mesures de protection et surtout de valorisation au même titre que les récifs coralliens qui font déjà l’objet d’une attention particulière.Martinique possesses 55 km2 of coral reefs, 50 of sea grass and 20 of mangroves. These three ecosystems produce services for a value estimated at 250 millions € per year. About 60% of this value originates from directs uses such as recreational activities (diving, excursions, beach activities, etc. induce by tourism and fishery. Ecosystem services (indirect uses such as coastal protection, carbon sequestration, biomass production and water purification are significant since their sum value reaches annually

Measured and calculated effective delayed neutron fraction of the IPR-R1 Triga reactor

Energy Technology Data Exchange (ETDEWEB)

Souza, Rose Mary G.P.; Dalle, Hugo M.; Campolina, Daniel A.M., E-mail: souzarm@cdtn.b, E-mail: dallehm@cdtn.b, E-mail: campolina@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The effective delayed neutron fraction, {beta}{sub eff}, one of the most important parameter in reactor kinetics, was measured for the 100 kW IPR-R1 TRIGA Mark I research reactor, located at the Nuclear Technology Development Center - CDTN, Belo Horizonte, Brazil. The current reactor core has 63 fuel elements, containing about 8.5% and 8% by weight of uranium enriched to 20% in U{sup 235}. The core has cylindrical configuration with an annular graphite reflector. Since the first criticality of the reactor in November 1960, the core configuration and the number of fuel elements have been changed several times. At that time, the reactor power was 30 kW, there were 56 fuel elements in the core, and the {beta}{sub eff} value for the reactor recommended by General Atomic (manufacturer of TRIGA) was 790 pcm. The current {beta}{sub eff} parameter was determined from experimental methods based on inhour equation and on the control rod drops. The estimated values obtained were (774 {+-} 38) pcm and (744 {+-} 20) pcm, respectively. The {beta}{sub eff} was calculated by Monte Carlo transport code MCNP5 and it was obtained 747 pcm. The calculated and measured values are in good agreement, and the relative percentage error is -3.6% for the first case, and 0.4% for the second one. (author)

R-matrix parameters in reactor applications

International Nuclear Information System (INIS)

Hwang, R.N.

1992-01-01

The key role of the resonance phenomena in reactor applications manifests through the self-shielding effect. The basic issue involves the application of the microscopic cross sections in the macroscopic reactor lattices consisting of many nuclides that exhibit resonance behavior. To preserve the fidelity of such a effect requires the accurate calculations of the cross sections and the neutron flux in great detail. This clearly not possible without viable resonance data. Recently released ENDF/B VI resonance data in the resolved range especially reflect the dramatic improvement in two important areas; namely, the significant extension of the resolved resonance ranges accompanied by the availability of the R-matrix parameters of the Reich-Moore type. Aside from the obvious increase in computing time required for the significantly greater number of resonances, the main concern is the compatibility of the Riech-Moore representation to the existing reactor processing codes which, until now, are based on the traditional cross section formalisms. This purpose of this paper is to summarize our recent efforts to facilitate implementation of the proposed methods into the production codes at ANL

Concepteur de matériel pédagogique et rédacteur technique (h/f ...

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

Le titulaire veille à ce que ce contenu fasse mieux connaître les services et les outils de GI-TI, y compris les changements récents. Il se tient au courant des changements survenus dans le domaine et entretient des relations avec la communauté locale et virtuelle de l'apprentissage et de la rédaction technique afin de ...

Et Ürünlerinde Bitkisel Yağların Kullanımı

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Gülen Yıldız Turp

2015-02-01

Full Text Available Yağ tüketimi ile çeşitli hastalıklar arasındaki ilişki, tüketicileri diyetlerindeki yağın miktarı ve özellikleriyle daha fazla ilgili olmaya yöneltmektedir. İşlenmiş et ürünlerinin yağ oranları daha az yağlı etlerin kullanımını içeren formülasyonlarla azaltılabilmekte, ancak bu girişim ekonomik olmadığı gibi ürün kalitesinde de istenmeyen değişikliklere yol açabilmektedir. Kolesterol içermeyen ve doymamış yağ asitlerini yüksek oranlarda içeren bitkisel yağların et ürünlerinde kullanımı ile daha sağlıklı et ürünleri üretimi mümkün görünmektedir. Bu çalışmada çeşitli et ürünlerinde bitkisel yağların kullanımının, ürün özellikleri üzerine etkileri literatüre dayanılarak incelenmiştir.

Substitution of the CFCs R-11, R-13, R-503, R-13B1, R-113, R-114 and R-12B1 in existing refrigerating, air-conditioning and heat pump systems with refrigerants of low ozone depletion potential in the Federal Republic of Germany. Status report; Ersatz der FCKW R11, R13, R503, R13B1, R113, R114, und R12B1 in bestehenden Kaelte-, Klima- und Waermepumpenanlagen in der Bundesrepublik Deutschland durch Kaeltemittel mit geringem Ozonabbaupotential. Statusbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

The technical basics and the state of the art for the substitution of the CFC refrigerants R-11, R-13, R-503, R-13B1, R-113, R-114 and R-12B1 in existing refrigeration systems are described and explained. The report contains an overview of the current applications of these refrigerants in the FRG, a review and discussion of existing substitutes, the presentation and evaluation of research and experiences with the conversion to alternative refrigerants, the presentation of the required infrastructure and a discussion of the technical feasibility. The conversion of existing systems to refrigerants of lower ozone depletion potential is in conclusion evaluated with regard to its technical feasibility, environmental relevance and economic efficiency. (orig.) [Deutsch] Es werden die technischen Grundlagen und der Stand der Technik zum Ersatz der FCKW-Kaeltemittel R11, R13, R503, R13B1, R113, R114 und R12B1 in bestehenden Kaelteanlagen dargestellt und erlaeutert. Der Bericht beinhaltet einen Ueberblick ueber die derzeitige Anwendung dieser Kaeltemittel in der BRD, die Vorstellung und Diskussion existierender Ersatzstoffe, die Darstellung und Bewertung der Forschung und Erfahrungen zu Umruestungen auf Ersatzstoffe, die Vorstellung der erforderlichen Infrastruktur und die Diskussion der technischen Durchfuehrbarkeit. Die Umstellung bestehender Anlagen auf Kaeltemittel mit geringerem Ozonabbaupotential wird abschliessend hinsichtlich der technischen Durchfuehrbarkeit, der Umweltrelevanz und der Wirtschaftlichkeit bewertet. (orig.)

Do cosmological data rule out f (R ) with w ≠-1 ?

Science.gov (United States)

Battye, Richard A.; Bolliet, Boris; Pace, Francesco

2018-05-01

We review the equation of state (EoS) approach to dark sector perturbations and apply it to f (R ) gravity models of dark energy. We show that the EoS approach is numerically stable and use it to set observational constraints on designer models. Within the EoS approach we build an analytical understanding of the dynamics of cosmological perturbations for the designer class of f (R ) gravity models, characterized by the parameter B0 and the background equation of state of dark energy w . When we use the Planck cosmic microwave background temperature anisotropy, polarization, and lensing data as well as the baryonic acoustic oscillation data from SDSS and WiggleZ, we find B0<0.006 (95% C.L.) for the designer models with w =-1 . Furthermore, we find B0<0.0045 and |w +1 |<0.002 (95% C.L.) for the designer models with w ≠-1 . Previous analyses found similar results for designer and Hu-Sawicki f (R ) gravity models using the effective field theory approach [Raveri et al., Phys. Rev. D 90, 043513 (2014), 10.1103/PhysRevD.90.043513; Hu et al., Mon. Not. R. Astron. Soc. 459, 3880 (2016), 10.1093/mnras/stw775]; therefore this hints for the fact that generic f (R ) models with w ≠-1 can be tightly constrained by current cosmological data, complementary to solar system tests [Brax et al., Phys. Rev. D 78, 104021 (2008), 10.1103/PhysRevD.78.104021; Faulkner et al., Phys. Rev. D 76, 063505 (2007), 10.1103/PhysRevD.76.063505]. When compared to a w CDM fluid with the same sound speed, we find that the equation of state for f (R ) models is better constrained to be close to -1 by about an order of magnitude, due to the strong dependence of the perturbations on w .

Angiomyolipome rénal agressif avec extension à la veine rénale: à propos d'un cas et une revue de la littérature

Science.gov (United States)

Majdoub, Aziz El; Khallouk, Abdelhak; Farih, Moulay Hassan

2017-01-01

L'angiomyolipome rénal est une tumeur qui est reconnue bénigne. Elle présente trois composantes différentes: musculaire, vasculaire et graisseuse, dont la distribution est variable. Le diagnostic repose sur la mise en évidence de la composante graisseuse intra-tumorale en TDM ou IRM. Exceptionnellement la tumeur peut avoir un caractère agressive avec extension locorégionale et veineuse (la veine rénale et la veine cave inferieure). Nous présentons une observation d'une patiente âgée de 37 ans présentant un Angiomyolipome rénal volumineux avec extension à la veine rénale. PMID:29599888

Elections régionales 2004 : jeux d'échelles entre local, régional et national. L'enseignement des cartes de France par canton

Directory of Open Access Journals (Sweden)

Michel Bussi

2004-03-01

Full Text Available Les élections de mars 2004 relèvent-elles principalement d'un enjeu national ou d'un enjeu régional ? Selon le modèle de "l'élection intermédiaire" de Jean-Luc Parodi, elles dépendraient avant tout d'un enjeu national. Mais depuis l'élaboration de ce modèle, les régions ont gagné en puissance et le débat sur la régionalisation gagné en consistance. Les échelles nationales et régionales ne sont pas les seules à l’oeuvre. Les cartes de ce dossier mettent également en évidence l'importance des e...

Justify of implementation of a hot water layer system in swimming pool research reactor IEA-R1m

International Nuclear Information System (INIS)

Toyoda, Eduardo Yoshio; Gordon, Ana Maria Pinho Leite; Sordi, Gian-Maria A.A.

2001-01-01

The IPEN/CNEN-SP has a swimming pool research reactor (IEA-R1m) in operation since 1957 at 2 MW. In 1998, after some modifications, its nominal power increased to 5 MW. Among these modifications some adaptations had to be accomplished in the radiological protection and operational procedure. The present work aim to study the need of implementation of a hot water layer in order to reduce the dose in the workers in the vicinity of the reactor swimming pool. Applying the principles of radioprotection optimization, it was concluded that the decision of the construction of one hot water layer system in the reactor swimming pool, is not necessary. (author)

Diagnostic moléculaire du complexe Mycobacterium tuberculosis résistant à l'isoniazide et à la rifampicine au Burkina Faso

Science.gov (United States)

Désire, Ilboudo; Cyrille, Bisseye; Florencia, Djigma; Souba, Diande; Albert, Yonli; Valerie, Bazie Jean Telesphore; Rebecca, Compaore; Charlemagne, Gnoula; Tamboura, Djibril; Rémy, Moret; Virginio, Pietra; Simplice, Karou Damintoti; Martial, Ouedraogo; Jacques, Simpore

2015-01-01

Introduction Cette étude a eu pour objectifs de diagnostiquer la tuberculose pulmonaire par l'examen microscopique et par la PCR des crachats et de déterminer les bases moléculaires de la résistance à la rifampicine et à l'isoniazide. Méthodes Le diagnostic du Complexe Mycobacterium Tuberculosis (CMTB) a été effectué par microscopie après coloration au Ziehl Nielsen et par PCR en temps réel en utilisant le kit d'identification du complexe MTB (Sacace Biotechnologie, Italie). Les résistances à la Rifampicine et à l'Isoniazide ont été étudiées par la technique de la PCR en utilisant le kit MTB résistance 8 (Sacace, Biotechnologie). Résultats Sur les 59 patients diagnostiqués pour la tuberculose pulmonaire, 59,3% étaient positifs en microscopie optique et 44,1% étaient positifs par PCR en Temps réel. Les résistances à la rifampicine (rpoB) et à l'isoniazide (katG et inhA) ont été observées chez 9 patients. La résistance à la rifampicine était due aux mutations (Asp516Val, Ser531Trp, Leu533Pro) et celle à l'isoniazide par les substitutions Ser315Thr du gène katG et C209T du gène inhA. Les multi résistances à la rifampicine et à l'isoniazide ont été observées dans 55,5% des échantillons et concernaient les associations: ropBAsp513Val + inhAC209T et rpoBLeu533Pro + katGSer315Thr. Conclusion La PCR en temps réel qui permet l'identification des allèles mutants rpoB, katG et inhA de M. tuberculosis est un outil de diagnostic épidémiologique de grande importance car elle permet de déterminer le niveau de résistance à la rifampicine et à l'isoniazide. PMID:26491516

La périurbanisation résidentielle en Belgique à la lumière des contextes suisse et danois: enracinement, dynamiques centrifuges et régulations collectives

OpenAIRE

Halleux, Jean-Marie; Bruck, L.; Mairy, N.

2002-01-01

Par rapport à ses voisins européens, la Belgique apparaît marquée par une périurbanisation à la fois plus importante et plus éclatée, ce dont résultent sans conteste de nombreux accrochages par rapport aux principes stratégiques du développement durable. Le présent article se propose d’étudier les causes de l’éclatement urbain qui affecte le territoire belge à la lumière d’une comparaison avec la Suisse et le Danemark, deux pays réputés pour avoir mis sur pied des politiques relativement effi...

Automates programmables et réseaux de terrain: conception des systèmes de régulation

OpenAIRE

Blanc, D

1998-01-01

Depuis le début des années 80, nous intégrons des automates programmables pour le contrôle des différents processus industriels. A l'origine, l'automate programmable était considéré comme une machine séquentielle, capable de suppléer des automatismes réalisés en logique traditionnelle, en apportant toutefois de profonds bouleversements dans la manière de concevoir et d'organiser le contrôle d'un processus. L'intégration de l'automate programmable renforce le degré de fiabilité de l'équipement...

L'essentiel de la RT 2012 obligations et mise en oeuvre de la réglementation thermique

CERN Document Server

Leblond, Philippe

2004-01-01

Issue du Grenelle de l’environnement, la réglementation thermique 2012 (RT 2012) a pour objectif de limiter les consommations énergétiques des bâtiments et leurs émissions de gaz à effet de serre. Depuis le 1er janvier 2013, tous les dossiers de permis de construire doivent être conformes aux exigences de résultats et de moyens imposées par la RT 2012. Ils devront indiquer notamment : • la valeur de deux coefficients : Bbiomax, le besoin bioclimatique maximal admissible, et Cepmax, la consommation conventionnelle maximale des bâtiments pour les usages en chauffage, ventilation et refroidissement ; • la valeur de la Ticréf, la température conventionnelle intérieure de référence ; • un certain nombre d’exigences de moyens, comme le respect de la surface et l’ouverture minimales des baies, ou l’obligation d’utiliser les énergies renouvelables. Cet ouvrage didactique et complet décrypte les textes de la RT 2012 et fournit sous forme de guide pratique une méthode simple adaptable ...

Thermal-hydraulic R and D infrastructure for water cooled reactors of the Indian nuclear power program

International Nuclear Information System (INIS)

Vijayan, P.K.; Jain, V.; Saha, D.; Sinha, R.K.

2009-01-01

R and D has been the critical ingredient of Indian Nuclear Power Program from the very inception. Approach to R and D infrastructure has been closely associated with the three-stage nuclear power program that was crafted on the basis of available resources and technology in the short-term and energy security in the long-term. Early R and D efforts were directed at technologies relevant to Pressurized Heavy Water Reactors (PHWRs) which are currently the mainstay of Indian nuclear power program. Lately, the R and D program has been steered towards the design and development of advanced and innovative reactors with the twin objective of utilization of abundant thorium and to meet the future challenges to nuclear power such as enhanced safety and reliability, better economy, proliferation resistance etc. Advanced Heavy Water Reactor (AHWR) is an Indian innovative reactor currently being developed to realize the above objectives. Extensive R and D infrastructure has been created to validate the system design and various passive concepts being incorporated in the AHWR. This paper provides a brief review of R and D infrastructure that has been developed at Bhabha Atomic Research Centre for thermal-hydraulic investigations for water-cooled reactors of Indian nuclear power program. (author)

Infiltrationsanæstesi som postoperativ smertebehandling ved hoftenær femurfraktur - et igangværende studie

DEFF Research Database (Denmark)

Bech, Rune Dueholm

2008-01-01

pertrochantær femurfraktur og collum femoris fraktur inkluderes. 50 patienter indgår i hver af de to diagnose-grupper (to delstudier). Ved randomisering tildeles patienterne hhv. Ropivacain eller placebo (NaCl), der gives som 1 peroperativ og 6 postoperative bolusinstillationer via et kateter, som fjernes efter...

Oméga 3 et neurotransmission cérébrale

Directory of Open Access Journals (Sweden)

Vancassel Sylvie

2004-01-01

Full Text Available Les acides gras polyinsaturés (AGPI sont des constituants structuraux fondamentaux du système nerveux central (SNC dont la teneur conditionne le fonctionnement des cellules neuronales. Ils sont des acteurs de la communication intercellulaire, notamment à travers les processus de neurotransmission. De nombreuses études ont montré chez l’animal que le déficit des membranes cérébrales en oméga 3, et plus particulièrement en acide docosahexaénoïque (22 : 6ω-3 ou DHA induit par une carence alimentaire spécifique en cette famille d’AGPI, s’accompagne de troubles de l’apprentissage. Un support neurochimique a été avancé, impliquant les processus de libération de neurotransmetteurs, notamment les monoamines et l’acétylcholine. Cette relation entre AGPI ω3 et neurotransmission est d’autant plus intéressante qu’elle pourrait être également impliquée chez l’Homme dans l’apparition et\\\\ou la sévérité de certains troubles neuropsychiatriques dans lesquels des dysfonctionnements de la neurotransmission sont constatés (schizophrénie, dépression, hyperactivité chez l’enfant. En effet, de nombreuses études révèlent un déficit du statut corporel en AGPI oméga 3 (20 : 5 et 22 : 6 mais aussi en oméga 6, qui peut être corrigé par voie nutritionnelle, permettant alors de réduire significativement certains des symptômes pathologiques. Dans ce contexte, nous développons au laboratoire des recherches visant à comprendre les mécanismes d’action des oméga 3, et en particulier du DHA, dans les membranes nerveuses et l’incidence sur le fonctionnement de ces cellules.

Acoplamiento molecular y actividad antibacteriana de las tioureas (R,R-N,N´-bis(1-ciclohexiletiltiourea y (R,R-N,N´-bis(1-feniletiltiourea

Directory of Open Access Journals (Sweden)

Fabían Martínez Flores

2013-05-01

Full Text Available Las tioureas, son compuestos resultantes de sustituir el átomo de oxígeno de la urea (NH2CONH2 por un átomo de azufre (NH2CSNH2. Actualmente se ha visto que las tioureas presentan diversas actividades biológicas, dentro de las que se encuentra la antimicrobiana. En el presente estudio se evaluó la actividad antibacteriana mediante acoplamiento molecular entre la enzima DNA girasa (receptor y las tioureas (R, R-N,N´-bis(1 ciclohexiletiltiourea (CYTU1 y (R,R-N,N´-bis(1-feniletiltiourea (CYTU2 como ligando en busca del posible mecanismo de acción de estos compuestos, los resultados muestran que existe interacción entre la enzima y ambas tioureas en el sitio activo. Por otro lado, también se evaluó la actividad antibacteriana frente a cepas de Sthapylococcus aureus, Escherichia coli y Pseudomonas fluorescens, mediante el método de microdilución en caldo con la adición de bromuro de 3-(4,5-dimetil-2-tiazolil-2,5-difeniltetrazolium (MTT, como parte del ensayo de viabilidad, mostrando una disminución de la misma sólo contra las bacterias gram negativas, siendo la tiourea CYTU2 la que mostró mejor actividad antibacteriana. Molecular docking and antibacterial activity thioureas (R,R-N,N´-bis(1-cyclohexyethylthiourea and (R,R-N,N´-bis(1-phenylethylthiourea Abstract Thioureas are resultant compounds of substitute the oxygen atom from urea (NH2CONH2 for a sulfur atom (NH2CSNH2. There are evidential that show the biological activity of thioureas, within which are antibacterial activity. We studied the antibacterial activity of two thioureas (R,R-N,N´-bis(1 cyclohexylethylthiourea (CYTU1 y (R,R-N,N´-bis(1 phenylethylthiourea (CYTU2 in silico using Molecular Docking between the DNA gyrase enzyme (receptor and the two thioureas (ligand. The results showed interaction between DNA girase and both thioureas on the pocket of the enzyme. By other hand, the biological activity was evaluated against the following bacterial strains: Sthapylococcus

L'université en transition : L'évolution de son rôle et des défis à ...

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

1 janv. 2012 ... En réunissant des textes rendant compte d'initiatives et d'innovations dans diverses régions du monde, notamment en Afrique subsaharienne, en Amérique latine, en Asie du Sud-Est, en Chine, en Europe de l'Est, en Europe de l'Ouest et en Scandinavie, l'ouvrage brosse un tableau qui est d'actualité et ...

Numerical Simulation of Fixed-Bed Catalytic Reforming Reactors: Hydrodynamics / Chemical Kinetics Coupling Simulation numérique des réacteurs de reformage catalytique en lit fixe : couplage hydrodynamique-cinétique chimique

Directory of Open Access Journals (Sweden)

Ferschneider G.

2006-11-01

Full Text Available Fixed bed reactors with a single fluid phase are widely used in the refining or petrochemical industries for reaction processes catalysed by a solid phase. The design criteria for industrial reactors are relatively well known. However, they rely on a one-dimensional writing and on the separate resolution of the equation of conservation of mass and energy, and of momentum. Thus, with complex geometries, the influence of hydrodynamics on the effectiveness of the catalyst bed cannot be taken into account. The calculation method proposed is based on the multi-dimensional writing and the simultaneous resolution of the local conservation equations. The example discussed concerns fixed-bed catalytic reactors. These reactors are distinguished by their annular geometry and the radial circulation of the feedstock. The flow is assumed to be axisymmetric. The reaction process is reflected by a simplified kinetic mechanism involving ten chemical species. Calculation of the hydrodynamic (mean velocities, pressure, thermal and mass fields (concentration of each species serves to identify the influence of internal components in two industrial reactor geometries. The map of the quantity of coke formed and deposited on the catalyst, calculated by the model, reveals potential areas of poor operation. Les réacteurs à lit fixe avec une seule phase fluide sont largement utilisés dans l'industrie du raffinage et de la pétrochimie, pour mettre en oeuvre un processus réactionnel catalysé par une phase solide. Les règles de conception des réacteurs industriels sont relativement bien connues. Cependant, elles reposent sur l'écriture monodimensionnelle et la résolution séparée, d'une part, des équations de conservation de la masse et de l'énergie et d'autre part, de la quantité de mouvement. Ainsi dans le cas de géométries complexes, l'influence de l'hydrodynamique sur l'efficacité du lit catalytique ne peut être prise en compte. La méthode de calcul

Le choix du périurbain à Québec : nature et biographie résidentielle

OpenAIRE

Andrée Fortin; Andrée Fortin; Carole Després; Carole Després

2009-01-01

À l’heure des changements climatiques et du vieillissement de la population québécoise, nous nous sommes interrogées sur ce qui attire et/ou retient des résidents dans le périurbain, souvent au prix de longs déplacements quotidiens pour le travail ou les emplettes. Comme dans certains secteurs périurbains le prix des résidences est très élevé, le choix résidentiel ne se réduit pas à des considérations d’ordre économique. Nous analysons ici une des composantes essentielles du milieu et qui en ...

Le choix du périurbain à Québec. Nature et biographie résidentielle

OpenAIRE

Fortin, Andrée; Després, Carole

2011-01-01

À l’heure des changements climatiques et du vieillissement de la population québécoise, nous nous sommes interrogées sur ce qui attire et/ou retient des résidents dans le périurbain, souvent au prix de longs déplacements quotidiens pour le travail ou les emplettes. Comme dans certains secteurs périurbains le prix des résidences est très élevé, le choix résidentiel ne se réduit pas à des considérations d’ordre économique. Nous analysons ici une des composantes essentielles du milieu et qui en ...

Les dynamiques de partager un récit: Auteur, autorité et auto-récit ...

African Journals Online (AJOL)

chez Maryse Condé et Tituba, dans Moi, Tituba, Sorcière…noire de Salem. Ceci est un récit fictif de la vie de Tituba, Indienne, une esclave accusée de la sorcellerie en 1692. L'article adopte l' idée de la poétique de la relation par Édouard ...

Operational parameters study of IPR-R1 TRIGA research reactor using virtual instruments

International Nuclear Information System (INIS)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares

2013-01-01

The instrumentation of nuclear reactors is designed with the principle of reliability, redundancy and diversification of control systems. Reliable monitoring of the parameters involved in the chain reaction is of great importance regarding efficiency and operational safety of the installation. The main goal of the simulation system in this proposed paper is to provide the study and improvement in understanding how these operational variables are interrelated and their behavior especially those related to neutronic and thermohydraulics. The work will be developed using the software LabVIEW ® (Laboratory Virtual Instruments Engineering Workbench). The program will enable the study of the variables involved in the operation of the installation throughout its operating range, for instance, a few mW up to 250 kW. The IPR-R1 TRIGA is a research nuclear reactor placed in open pool and cooled by light water with natural circulation. It is located at the Nuclear Technology Development Center (CDTN), in Belo Horizonte Brazil. The developing system employs the modern concept of virtual instruments (VIs), using microprocessors and visual interface on video monitors. LabVIEW ® breaks the paradigm of text-based programming language, for programming based on icons. The system will enable the use of this reactor in training and personnel training in the nuclear field. The work follows the recommendations of the International Atomic Energy Agency (IAEA), which has encouraged its members to develop strategic plans in order to use their research reactors. (author)

Operational parameters study of IPR-R1 TRIGA research reactor using virtual instruments

Energy Technology Data Exchange (ETDEWEB)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares, E-mail: ajp@cdtn.br, E-mail: amir@cdtn.br, E-mail: fsl@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

The instrumentation of nuclear reactors is designed with the principle of reliability, redundancy and diversification of control systems. Reliable monitoring of the parameters involved in the chain reaction is of great importance regarding efficiency and operational safety of the installation. The main goal of the simulation system in this proposed paper is to provide the study and improvement in understanding how these operational variables are interrelated and their behavior especially those related to neutronic and thermohydraulics. The work will be developed using the software LabVIEW ® (Laboratory Virtual Instruments Engineering Workbench). The program will enable the study of the variables involved in the operation of the installation throughout its operating range, for instance, a few mW up to 250 kW. The IPR-R1 TRIGA is a research nuclear reactor placed in open pool and cooled by light water with natural circulation. It is located at the Nuclear Technology Development Center (CDTN), in Belo Horizonte Brazil. The developing system employs the modern concept of virtual instruments (VIs), using microprocessors and visual interface on video monitors. LabVIEW ® breaks the paradigm of text-based programming language, for programming based on icons. The system will enable the use of this reactor in training and personnel training in the nuclear field. The work follows the recommendations of the International Atomic Energy Agency (IAEA), which has encouraged its members to develop strategic plans in order to use their research reactors. (author)

Sensibilité et évolution de la résistance aux antibiotiques des ...

African Journals Online (AJOL)

La collecte des donnée a été faite par extraction des résultats de tous les antibiogrammes de E coli, réalisés de 2005 à 2012 enregistrés dans la mémoire de l'automate d'identification et lecture d'antibiogramme mini API™ et par les registres du laboratoire. Résultats : –Escherichia coli était l'espèce la plus fréquente avec ...

Écrire vrai: la posture d’authenticité chez Agota Kristof et Katalin Molnár

Directory of Open Access Journals (Sweden)

Julia Ori

2018-04-01

Full Text Available Agota Kristof and Katalin Molnár, two Franco-Hungarian authors of the twentieth century, share the concern to use a language that can express a certain reality and truth. For that, they distance themselves from the normative French language and write in an incorrect language, more apt to represent their difference. However, while Kristof wants to reach maximum objectivity, Molnár writes in an exaggeratedly subjective way. This article examines the textual and extratextual position of these authors regarding the possibility of writing the truth, through the analysis of language in Kristof's trilogy and in La¬mour Dieu of Molnár. Agota Kristof et Katalin Molnár, deux auteures franco-hongroises du XXe siècle, partagent la même préoccupation d’utiliser un langage pouvant exprimer une certaine réalité et vérité. Pour cela, elles s’éloignent de la langue française normative et écrivent dans un langage incorrect, plus apte à représenter leur différence. Néanmoins, tandis que le but de Kristof est d’arriver à une objectivité totale, Molnár écrit d’une manière exagérément subjective. Dans cet article, nous examinons la posture textuelle et extratextuelle de ces auteures concernant la possibilité d’écrire la vérité, à travers l’analyse du langage dans la trilogie de Kristof et dans Lamour Dieu de Molnár.

Stabilité et pertes des conducteurs pour régime alternatif

Science.gov (United States)

Estop, P.; Lacaze, A.

1994-04-01

Recent progresses obtained on low-T_c superconductors usable at industrial frequencies allow to envisage a new and innovating application as the current limiter. The device conception determines a cryogenic cost due to the dissipated energy in superconducting wires. In order to reduce the losses sufficiently, fine wires with submicromic filaments must be used. In relation to the need to obtain an infaillible protection during the quench, a new type of conductor, has been worked out, tested and validated. The main technical aspects concerning the losses of low-T_c superconductors have been developed on this paper. Les récents progrès obtenus sur les conducteurs supraconducteurs basse température critique utilisables aux fréquences industrielles permettent d'entrevoir une application nouvelle et innovante comme le limiteur de courant. De la conception d'un tel système résulte un coût cryogénique lié à l'énergie dissipée dans les brins supraconducteurs. La réduction des pertes nécessite l'utilisation de brins suffisamment fins et disposant de filaments submicromiques. Concernant le besoin d'obtenir une protection infaillible au moment de la transition, un conducteur d'un concept nouveau a été élaboré, testé et validé. L'article passe en revue les principaux aspects techniques liés à la stabilité et aux pertes dans les conducteurs supraconducteurs basse température critique.

Rat organic solute carrier protein 1 (rOscp1) mediated the transport of organic solutes in Xenopus laevis oocytes: isolation and pharmacological characterization of rOscp1.

Science.gov (United States)

Izuno, Hisanori; Kobayashi, Yasuna; Sanada, Yutaka; Nihei, Daisuke; Suzuki, Masako; Kohyama, Noriko; Ohbayashi, Masayuki; Yamamoto, Toshinori

2007-09-22

Rat organic solute carrier protein 1 (rOscp1) was isolated from a rat testis cDNA library. Isolated rOscp1 cDNA consisted of 1089 base pairs that encoded a 363-amino acid protein, and the amino acid sequence was 88% and 93% identical to that of human OSCP1 (hOSCP1) and mouse Oscp1 (mOscp1), respectively. The message for rOscp1 is highly detected in rat testis. When expressed in X. oocytes, rOscp1 mediated the high affinity transport of p-aminohippurate (PAH) with a Km value of 15.7+/-1.9 microM, and rOscp1-mediated organic solutes were exhibited in time- and Na+-independent manners. rOscp1 also transported various structurally heterogenous compounds such as testosterone, dehydroepiandrosterone sulfate (DHEA-S), and taurocholate with some differences in substrate specificity compared with hOSCP1. Immunohistochemical analysis revealed that the rOscp1 protein is localized in the basal membrane side of Sertoli cells as observed in mouse testis [Kobayashi et al., 2007; Kobayashi, Y., Tsuchiya, A., Hayashi, T., Kohyama, N., Ohbayashi, M., Yamamoto, T., 2007. Isolation and characterization of polyspecific mouse organic solute carrier protein 1 (mOscp1). Drug Metabolism and Disposition 35 (7), 1239-1245]. Thus, the present results indicate that a newly isolated cDNA clone, rOscp1, is a polyspecific organic solute carrier protein with some differences in substrate specificity compared with human and mouse OSCP1.

The future of the IPR-R1 TRIGA MARK I reactor after 48 years operation

International Nuclear Information System (INIS)

Maretti, Fausto Junior; Sette Camara, Luiz Otavio I.; Oliveira, Paulo Fernando

2008-01-01

The TRIGA Mark I IPR-R1 Reactor operates in the Nuclear Technology Development Center/ Brazilian Committion for Nuclear Energy (CDTN/CNEN), originally Institute of Radioactive Researches, in Belo Horizonte, Minas Gerais, since November 6, 1960. Initially it operated for isotope production for different uses, being later used in wide scale for another purposes as analyses for activation with neutrons and training of nuclear power plants operators. Dozens of degree theses were also developed with the use of the reactor. Along the years, several improvements were introduced in the reactor and its auxiliary systems, with the purpose to provide better use of the facilities and with the objective to increase the safety in the operation. The reactor is ready right now to operate at 250 kW, and for sure the nuclear applications programmed will be improved. The Operation Manual and the Safety Analysis report were already modified, as well as the Emergency Plan and the relative procedures to the same. After the tests at the end of 2008, the reactor will already be operating in the new power. This work presents a description of the several accomplishments of the last years and comments about the possibility of new uses for the reactor in the several areas of nuclear applications and some of the experiments and tests results during the upgrading program. (authors)

Exploration d’un système interfacique et de ses dynamiques : application au tourisme de réunions et de congrès

Directory of Open Access Journals (Sweden)

Christofle S.

2012-10-01

Full Text Available Le tourisme de réunions et de congrès fait se rassembler en un lieu nodal, durant au moins deux jours, des personnes issues d’horizons géographiques variés mais aux intérêts communs. Le système interfacique congressuel se structure autour de la réunion, interface immatérielle, qui prend place dans le palais des congrès, interface matérielle, et met en contact différents acteurs : congressistes, organisateurs, prestataires de services, collectivités territoriales. Ce système ouvert, localisé, s’articule autour de trois grands types d’interfaces, intra-réticulaires, inter-réseaux et réseaux-territoires dans le cadre de stratégies économiques, de destination et de développement territorial. Quatre grands effets sont induits : la diffusion et l’appropriation d’une information neuve, l’accélération de l’innovation et de l’expérimentation, la création d‘une expérience communautaire, le développement de la valeur.

Isıl İşlem Uygulanmış Et ve Et Ürünlerinde Heterosiklik Aromatik Aminler

Directory of Open Access Journals (Sweden)

Fatih Öz

2015-02-01

Full Text Available 1977 yılında Japon bilim adamları, kızartılmış et ve balık ürünlerinden Heterosiklik Aromatik Amin (HAA olarak sınıflandırdıkları yüksek oranda toksik yeni bir grup bilesikler belirlemişlerdir. HAA’ler balık ve et gibi protein bakımından zengin gıdaların 150 °C’nin üzerindeki sıcaklıklarda pişirilmesi esnasında oluşan mutajenik ve/veya kanserojenik bileşiklerdir. Bu bileşikler aminoasitler ve karbonhidratlar ile kreatin veya kreatininin reaksiyon ürünleridir. Bu çalışmada HAA’lerin oluşumu, prekürsörleri, oluşum seviyelerinin azaltılması ve analiz metotları ile ilgili araştırmalar derlenmiştir. Gıda mutajenleri ile karşılaştırıldığında HAA’lerin aflatoksin B1 den 100 kat, benzo[a]pyrene den ise 2000 kat daha fazla mutajenik oldukları belirtilmiştir. Güçlü mutajen olan bu bileşikleri içeren gıdaların birçok ülkede yaygın olarak tüketilmesi ve epidemiyolojik çalışmaların bu tür gıdaları fazlaca tüketen ülkelerde kanser oranının çok daha yüksek olduğunu belirtmesinden dolayı konu dünya çapında büyük öneme sahiptir. Günümüze kadar, gıdalardan ve model sistemlerden 25’i aşkın HAA izole edilmiştir. HAA’ler genelde ısıl işlem uygulanmış et ve et ürünlerinde bulunurlar. HAA’lerin konsantrasyonları ısıl işlem gören ürünün tipi, pişirme sıcaklığı ve süresi,  pişirme ekipman ve metodu, pH ve su aktivitesi gibi fiziksel faktörler ile karbonhidratlar, serbest aminoasitler ve kreatin gibi kimyasal faktörlere bağlıdır. Ayrıca, ısı ve kütle transferi, yağlar, yağ oksidasyonu ve antioksidanların HAA’lerin konsantrasyonuna etki ettiği saptanmıştır.

Neutron flux determination at the IPR-R1 Triga Mark I neutron beam extractor

International Nuclear Information System (INIS)

Zangirolami, Dante Marco; Maretti Junior, Fausto; Ferreira, Andrea Vidal

2009-01-01

The IPR-R1 Triga Mark I Reactor located at the CDTN/CNEN, Belo Horizonte, Brazil, has been operating since November of 1960. In this work, measurements of thermal and epithermal neutron flux along the IPR-R1 neutron beam extractor were performed by neutron activation of reference materials using the two foils method. The obtained results were compared with results from two previous works: an experimental measurement done in a previous reactor core configuration and a numerical work made by Monte Carlo simulation using the actual reactor core configuration. The main purpose of this work is to update the measured data to the actual reactor core configuration. (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

Révolution tunisienne et Internet : le rôle des médias sociaux

OpenAIRE

Lecomte, Romain

2013-01-01

Suite au mouvement de contestation populaire qui a conduit à la chute du régime de Ben Ali, médias et experts des NTIC ont beaucoup insisté sur le rôle révolutionnaire joué par Internet en Tunisie, et plus particulièrement par les « réseaux sociaux ». Dans cet article, tout en cherchant à analyser comment, concrètement, les usages d’Internet ont pu servir de catalyseur au mouvement de contestation né à Sidi Bouzid, nous mettons en garde contre certaines analyses en vogue véhiculant le mythe d...

Doping of monocrystalline silicon with phosphorus by means of neutron irradiation at the IEA-R1 research reactor

International Nuclear Information System (INIS)

Carbonari, A.W.; Puget, M.A.C.

1990-11-01

The first neutron irradiation experiments with monocrystal silicon in the IEA-R1 research reactor of IPEN are related. The silicon is irradiated with phosphorus producing a N type semiconductor with a very small resistivity variation throughout the crystal volume. The neutrons induce nuclear reactions in Si-30 isotope and these atoms are then transformed in to phosphorous atoms. This process is known as Neutron Transmutation Doping. In order to irradiate the silicon crystals in the reactor, a specific device has been constructed, and it permits the irradiation of up to 2.5'' diameter monocrystals. (author)

Intégration régionale et politique des outre-mers

Directory of Open Access Journals (Sweden)

Didier Benjamin

1999-06-01

Full Text Available Grâce à ses outre-mers, qui lui apportent 96% de sa zone économique exclusive, la France dispose du troisième domaine maritime du monde et assure une présence sur tous les océans. Cependant, les outre-mers ne jouent plus qu'un rôle mineur dans la politique des océans. Ce paradoxe s'explique en partie par les difficultés qu'ils rencontrent à s'insérer dans les échanges internationaux et à s'intégrer aux organisations régionales. Les différences de niveaux de développement socioéconomique avec les pays voisins contribuent à isoler les outre-mers dans leur environnement immédiat.

Et brand er en samtale, men hvem råber højest?

DEFF Research Database (Denmark)

Hansen, Heidi

2015-01-01

I samtalen om brandet kan der være mange stakeholdere på banen. Spørgsmålet er, hvem der formår at sætte dagsordenen? Det skorter ikke på gode råd og how-to-do-it bøger i marketing branchen, og mange af disse råd er kloge og indsigtsfulde, men ligegyldigt hvilken opskrift man følger, kan man aldr...... kontrollere et brands betydning. Man kan blot forsøge at påvirke det i en bestemt retning. Et brand er nemlig ikke en fast størrelse, det er en social konstruktion, og virksomheden styrer ikke selv, hvilken brandværdi de tillægges af forbrugerne....

Le choix du périurbain à Québec : nature et biographie résidentielle

Directory of Open Access Journals (Sweden)

Andrée Fortin

2009-01-01

Full Text Available À l’heure des changements climatiques et du vieillissement de la population québécoise, nous nous sommes interrogées sur ce qui attire et/ou retient des résidents dans le périurbain, souvent au prix de longs déplacements quotidiens pour le travail ou les emplettes. Comme dans certains secteurs périurbains le prix des résidences est très élevé, le choix résidentiel ne se réduit pas à des considérations d’ordre économique. Nous analysons ici une des composantes essentielles du milieu et qui en fait aux yeux de plusieurs un « milieu sain » : la proximité de la nature. En quoi cela constitue-t-il un attrait pour les résidents ? Est-ce parce qu’il permet un mode de vie associé à des activités de plein air, ou plutôt un milieu « naturel » associé aux grands espaces ? Quel rapport les résidents du périurbain ont-il avec la nature qui les entoure ? Dans le cadre d’une recherche qualitative sur l’étalement urbain, nous avons interrogé 132 résidents de six secteurs périurbains de l’agglomération de Québec (Canada, associés autrefois à la villégiature ou à l’agriculture. Les entretiens semi-dirigés portaient sur le choix résidentiel, les représentations de la ville, de la banlieue, de la campagne et du village, les lieux fréquentés dans l’agglomération et le rapport à l’automobile. Il apparaît que les éléments recherchés dans le milieu de vie par plusieurs répondants sont ceux qu’ils ont connus dans leur enfance, dans des banlieues pavillonnaires de première couronne (c’est-à-dire édifiées dans les années 1950 et 1960 ou des régions rurales, dont ils sont majoritairement issus. C’est ainsi que la biographie personnelle semble influencer le choix résidentiel. Pour vivre près de la nature, ils seraient prêts à s’éloigner davantage de la ville qu’ils caractérisent essentiellement par la pollution et le béton. La dépendance à l’automobile que ce mode de vie entra

Characterization of the water filters cartridges from the iea-r1 reactor using the Monte Carlo method

International Nuclear Information System (INIS)

Costa, Priscila; Potiens Junior, Ademar J.

2015-01-01

Filter cartridges are part of the primary water treatment system of the IEA-R1 Research Reactor and, when saturated, they are replaced and become radioactive waste. The IEA-R1 is located at the Nuclear and Energy Research Institute (IPEN), in Sao Paulo, Brazil. The primary characterization is the main step of the radioactive waste management in which the physical, chemical and radiological properties are determined. It is a very important step because the information obtained in this moment enables the choice of the appropriate management process and the definition of final disposal options. In this paper, it is presented a non-destructive method for primary characterization, using the Monte Carlo method associated with the gamma spectrometry. Gamma spectrometry allows the identification of radionuclides and their activity values. The detection efficiency is an important parameter, which is related to the photon energy, detector geometry and the matrix of the sample to be analyzed. Due to the difficult to obtain a standard source with the same geometry of the filter cartridge, another technique is necessary to calibrate the detector. The technique described in this paper uses the Monte Carlo method for primary characterization of the IEA-R1 filter cartridges. (author)

How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

International Nuclear Information System (INIS)

Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N.

2015-01-01

This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N., E-mail: acavaz@ipen.br, E-mail: dgsilva@ipen.br, E-mail: eytoyoda@ipen.br, E-mail: psantia@ipen.br, E-mail: tnconti@ipen.br, E-mail: rsemmler@ipen.b, E-mail: rncarval@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

Study and project of the new rack with boron for storage of fuel elements burned in the IEA-R1 research reactor

International Nuclear Information System (INIS)

Rodrigues, Antonio Carlos Iglesias; Madi Filho, Tufic; Silva, Davilson Gomes da

2017-01-01

The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor's pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3TMhis) was chosen due to its properties. This work presents studies: (a) for the construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Library were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission - CNEN and the International Atomic Energy Agency (IAEA). To calculate the k eff were considered new fuel elements (maximum possible reactivity) used in full charge of the storage rack. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff < 0.95). (author)

Study and project of the new rack with boron for storage of fuel elements burned in the IEA-R1 research reactor

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, Antonio Carlos Iglesias; Madi Filho, Tufic; Silva, Davilson Gomes da, E-mail: acirodri@ipen.br, E-mail: tmfilho@usp.br, E-mail: dgsilva@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor's pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3TMhis) was chosen due to its properties. This work presents studies: (a) for the construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Library were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission - CNEN and the International Atomic Energy Agency (IAEA). To calculate the k{sub eff} were considered new fuel elements (maximum possible reactivity) used in full charge of the storage rack. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff < 0.95). (author)

Safety approach and R and D program for future french sodium-cooled fast reactors

International Nuclear Information System (INIS)

Beils, Stephane; Carluec, Bernard; Devictor, Nicolas; Fiorini, Gian Luigi; Sauvage, Jean Francois

2011-01-01

This paper presents briefly the safety approach as well as the R and D program that is underway to support the deployment of future French Sodium-Cooled fast Reactors (SFRs): A) Safety objectives and principles for future reactors. The content of the first section reflects the works of AREVA, CEA, and EDF concerning the safety orientations for the future reactors. The availability of such orientations and requirements for the SFRs has to allow introducing and managing the process that will lead to the detailed definition of the safety approach, to the selection of the corresponding safety options, and to the identification and motivation of the supporting R and D. B) Strategy and roadmap in support of the R and D for future SFRs. This section describes the R and D program led jointly by CEA, EDF, and AREVA, which has been developed with the objectives to be able to preliminarily define, by 2012, the safety orientations for the future SFRs, and to deduce from them the characteristics of the ASTRID prototype. (author)

Measurement of thermal, epithermal and fast neutrons fluxes by the activation foil method at IEA-R1 reactor

International Nuclear Information System (INIS)

Dias, M.S.; Koskinas, M.F.; Berretta, J.R.; Fratin, L.; Botelho, S.

1990-01-01

The thermal, epithermal and fast neutron fluxes have been determined experimentally by the activation foil method at position GI, located near the IEA-R1 reactor core. The reactions used were 197 Au (n,gamma) 198 Au, for thermal and epithermal neutrons and 27 Na (n,alpha) 24 Na, for fast neutrons. The activities were measured by the 4π(PC)β-γ coincidence method. (author)

Rôle et responsabilités du réviseur d'entreprises en situation de fraude.

OpenAIRE

Veri, Raphaël

2016-01-01

Rôle et responsabilités du réviseur d'entreprises en situation de fraude. Mémoire réalisé par VERI Raphaël, encadré par le professeur PEIRCE Robert. NOMA : 8843-12-00 Année académique: 2015-2016 Programme d'étude: GEST2 Ce mémoire a été réalisé afin d’étudier le rôle et les responsabilités du réviseur d'entreprises qui détecte une fraude dont il n'est ni l'auteur ni un complice direct. Le premier chapitre est consacré à la définition de la profession de réviseur d’entreprises ainsi que des mi...

Structural evaluation of IEA-R1 primary system pump nozzles

Energy Technology Data Exchange (ETDEWEB)

Fainer, Gerson; Faloppa, Altair A.; Oliveira, Carlos A. de; Mattar Neto, Miguel, E-mail: gfainer@ipen.br, E-mail: afaloppa@ipen.br, E-mail: calberto@ipen.br, E-mail: mmattar@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2017-11-01

The IEA-R1 pumps of the primary coolant system may be required to withstand design and operational conditions. IEA-R1 nuclear research reactor is an open pool type reactor operated by IPEN since 1957. The reactor can be operated up to 5MW heating power since it was upgraded in a modernization program conducted by IPEN. The primary coolant system is composed by the piping system, decay tank, two heat pumps and two heat exchangers. In the latest arrangement upgrade of the primary system, conducted in 2014 as part of an aging management program, a partial replacement of the coolant piping and total replacement of piping and pump supports were done. As consequence, reviewed loads in the pump nozzles were obtained demanding a new evaluation of them. The aim of this report is to present the structural evaluation of the pump nozzles, considering the new loads coming from the new piping layout, according to: API 610 code verification, Supplier loads and structural analysis applying finite element method, by using the ANSYS computer program, regarding ASME VIII Div 1 & 2 recommendations. (author)

Structural evaluation of IEA-R1 primary system pump nozzles

International Nuclear Information System (INIS)

Fainer, Gerson; Faloppa, Altair A.; Oliveira, Carlos A. de; Mattar Neto, Miguel

2017-01-01

The IEA-R1 pumps of the primary coolant system may be required to withstand design and operational conditions. IEA-R1 nuclear research reactor is an open pool type reactor operated by IPEN since 1957. The reactor can be operated up to 5MW heating power since it was upgraded in a modernization program conducted by IPEN. The primary coolant system is composed by the piping system, decay tank, two heat pumps and two heat exchangers. In the latest arrangement upgrade of the primary system, conducted in 2014 as part of an aging management program, a partial replacement of the coolant piping and total replacement of piping and pump supports were done. As consequence, reviewed loads in the pump nozzles were obtained demanding a new evaluation of them. The aim of this report is to present the structural evaluation of the pump nozzles, considering the new loads coming from the new piping layout, according to: API 610 code verification, Supplier loads and structural analysis applying finite element method, by using the ANSYS computer program, regarding ASME VIII Div 1 & 2 recommendations. (author)

Hazard and operability study (Haz Op) of the 2 MW IEA-R1 reactor startup procedures

International Nuclear Information System (INIS)

Sauer, Maria E.L.J.; Correa, Francisco; Sara Neto, Antonio J.; Costa, Carlos A.R. da; Santos, Cilas C. dos; Cardenas, Jose P.N.; Berretta, Jose R.; Neves Conti, Thadeu das

1997-01-01

This work presents the Hazard and Operability Study (Haz Op) applied to startup procedures of the 2 MW IEA-R1 research reactor, at IPEN/CNEN-S P. The Haz Op was developed by reviewing the procedures of the installation startup, in order to identify hazards and/or operational problems caused by deviations in the execution of these routines. This paper summarizes this study. describing some potential problems of relevant importance to safety as well as preventives and/or correctives measures to avoid their occurrence. Besides, an benefits evaluation and the technique limitations is made. (author). 5 refs., 1 tab

Fast reactors: R and D targets and outlook for their introduction

International Nuclear Information System (INIS)

Poplavsky, V.; Barre, B.; Aizawa, K.

1997-01-01

In this paper the current status of fast reactors development is briefly outlined, including experimental, demonstration, and commercial installations. Data on the experience gained in development and operation of NPPs with reactors of this type are presented. The issues are discussed in connection with possibilities of fast reactor development in the nuclear power structure for the near (up to 2010-2020) and distant future. In the final part of the paper, an analysis is given of possible ways for R and D development in the field of NPPs with fast neutron reactors. (author)

Obtaining of total and thermal neutron flux in the carousel facility of the TRIGA MARK IPR-R1 reactor using the Monte Carlo transport method

International Nuclear Information System (INIS)

Guerra, Bruno Teixeira

2011-01-01

The IPR-R1 is a reactor type TRIGA, Mark-I model, manufactured by the General Atomic Company and installed at Nuclear Technology Development Centre (CDTN) of Brazilian Nuclear Energy Commission (CNEN), in Belo Horizonte, Brazil. It is a light water moderated and cooled, graphite-reflected, open-pool type research reactor. IPR-R1 works at 100 kW but it will be briefly licensed to operate at 250 kW. It presents low power, low pressure, for application in research, training and radioisotopes production. The fuel is an alloy of zirconium hydride and uranium enriched at 20% in 235 U. The goal this work is modelling of the IPR-R1 Research Reactor TRIGA using the codes MCNPX2.6.0 (Monte Carlo N-Particle Transport extend) and MCNP5 to the calculating the neutron flux in the carousel facility. In each simulation the sample was placed in a different position, totaling forty positions around of the reactor core. The comparison between the results obtained with experimental values from other work showing a relatively good agreement. Moreover, this methodology is a theoretical tool in validating of the experimental values and necessary for determining neutron flux which can not be accessible experimentally. (author)

Data acquisition and signal processing system for IPR R1 TRIGA-Mark I nuclear research reactor of CDTN

International Nuclear Information System (INIS)

Mesquita, A.Z.; Maretti, F. Jr.; Rezende, H.C.; Tambourgi, E.B.

2004-01-01

The TRIGA IPR-R1 Nuclear Research Reactor, located at the Nuclear Technology Development Center (CDTN/CNEN) in Belo Horizonte, Brazil, is being operated since 44 years ago. The main operational parameters were monitored by analog recorders and counters located in the reactor control console. The reactor operators registered the most important operational parameters and data in the reactor logbook. This process is quite useful, but it can involve some human errors. It is also impossible for the operators to take notes of all variables involving the process mainly during fast power transients in some operations. A PC-based data acquisition was developed for the reactor that allows online monitoring, through graphic interfaces, and shows operational parameters evolution to the operators. Some parameters that were not measured, like the power and the coolant flow rate at the primary loop, are monitored now in the computer video monitor. The developed system allows measuring out all parameters in a frequency up to 1 kHz. These data is also recorded in text files available for consults and analysis. (author)

Strengthening the R and D on fast reactor technology, and promoting its industrialization

International Nuclear Information System (INIS)

Wan Gang

2008-01-01

Based on the strategic thoughts of energy development in China expounded by Jiang Zemin in the article entitled 'Reflections on Energy Issues in China', the author points out in this paper that R and Ds on fast reactor technology shall be carried out timely in China by taking full advantage of international scientific resources, and overall planning in this regard shall be made as well. The point of view of strengthening fast reactor technology R and D and promoting its industrialization is also put forward in the paper. (authors)

Characterization of filters cartridges from the water polishing system of IEA-R1 reactor: radiometric methods

International Nuclear Information System (INIS)

Tessaro, Ana Paula G.; Vicente, Roberto

2015-01-01

The acceptance of radioactive waste in a repository depends primarily on knowledge of the radioisotopic inventory of the material, according to regulations established by regulatory agencies. The primary characterization is also a fundamental action to determine further steps in the management of the radioactive wastes. The aim of this work is to report the development of non-destructive methods for primary characterization of filters cartridges discarded as radioactive waste. The filters cartridges are used in the water polishing system of the IEA-R1 reactor retaining the particles in suspension in the reactor cooling water. The IEA-R1 is a pool type reactor with a thermal power of 5 MW, moderated and cooled with light water. It is located in the Energy and Nuclear Research Institute (IPEN-CNEN), in São Paulo, Brazil. The cartridge filters become radioactive waste when they are saturated and do not meet the required flow for the proper operation of the water polishing system. The activities of gamma emitters present in the filters are determined using gamma spectrometry, dose rate measurements and the Point Kernel Method to correlate results from both measurements. For the primary characterization, one alternative method is the radiochemical analysis of slices taken from each filter, what presents the disadvantage of higher exposures personnel and contamination risks. Another alternative method is the calibration of the measurement geometry of a gamma spectrometer, which requires the production of a standard filter. Both methods are necessary but can not be used in operational routine of radioactive waste management owing to cost and complexity. The method described can be used to determine routinely the radioactive inventory of these filters and other radioactive wastes, avoiding the necessity of destructive radiochemical analysis, or the necessity of calibrating the geometry of measurement. (author)

Estimations hypoelliptiques globales et compacit\\'e de la r\\'esolvante Estimations hypoelliptiques globales et compacit\\'e de la r\\'esolvante pour des op\\'erateurs de Fokker-Planck ou des laplaciens de Witten

CERN Document Server

Helffer, B

2004-01-01

Ces derni\\`eres ann\\'ees, les estimations hypoelliptiques ont connu une nouvelle jeunesse en liaison avec des questions provenant de la th\\'eorie cin\\'etique des gaz. Dans cette direction de nombreux auteurs ont en effet eu besoin de d\\'emontrer des estimations maximales pour en d\\'eduire la compacit\\'e de l'op\\'erateur de Fokker-Planck et avoir des estimations sur la r\\'esolvante permettant d'aborder la question du retour \\`a l'\\'equilibre. Dans un article tr\\`es r\\'ecent, F.~H\\'erau et F.~Nier (inspir\\'es par des calculs explicites du livre de Risken) ont mis en \\'evidence les liens \\'etroits entre ces questions et des questions analogues pour un laplacien de Witten. L'\\'etude de ces liens est poursuivie et syst\\'ematis\\'ee dans un livre en pr\\'eparation \\'ecrit en collaboration avec F.~Nier dont nous allons pr\\'esenter quelques aspects ici en pr\\'esentant parfois un \\'eclairage diff\\'erent sur un probl\\`eme qui laisse encore beaucoup de conjectures non r\\'esolues.

What Drives Innovativeness? Entrepreneurship and Regional Clustering in Three Biotechnology Hotspots L’entreprenariat et les réseaux régionaux d’entreprises, moteurs de l’innovation dans trois bioclusters

Directory of Open Access Journals (Sweden)

Jerry Haar

2009-10-01

Full Text Available Cet article s’attache à mettre en évidence le lien entre innovation, entreprenariat et développement de réseaux d’entreprises au sein de pôles régionaux. L’innovation y est ainsi abordée à la fois dans sa relation avec l’entreprenariat et dans sa dimension géographique. L’accent est plus particulièrement mis sur les facteurs et les forces qui alimentent l’innovation dans un secteur d’activité dont l’importance va croissant, celui des biotechnologies. L’exemple de trois pôles régionaux, respectivement situés autour de la Baie de San Francisco, à Boston et dans sa périphérie, et dans une zone couvrant une partie de la Pennsylvanie et la vallée de la Delaware, montre que l’innovation résulte de processus qui varient considérablement d’une région à l’autre. En effet, si les trois bioclusters qu’étudie l’article sont caractérisés par un taux élevé d’activité innovante, un équilibre différent dans chaque cas s’y est établi entre les variables liées à l’entreprenariat et celles qui sont relatives à la constitution d’un réseau régional d’entreprises. Il n’existe donc pas de formule éprouvée pour stimuler l’innovation. Une conclusion s’impose, toutefois : l’entreprenariat et la constitution de clusters sont des facteurs de première importance.

Physique et humanités scientifiques. Autour de la réforme de l'enseignement de 1902. Études et documents

OpenAIRE

Tiberghien, Andrée

2006-01-01

Cet ouvrage porte sur la réforme de l'enseignement expérimental de la physique et de la chimie pour plus de 60 ans. Une première partie analyse cette réforme et la seconde comporte des documents originaux. Dans l'esprit de cette réforme, les sciences doivent désormais faire partie de la culture, on parle d'« humanités scientifiques ». Les concepteurs introduisent un renouveau pédagogique où l'expérience et la méthode inductive ont une place prépondérante. Ce livre met en évidence de façon trè...

Total Synthesis of (R, R, R)-gamma-Tocopherol through Cu-Catalyzed Asymmetric 1,2-Addition

NARCIS (Netherlands)

Wu, Zhongtao; Harutyunyan, Syuzanna R.; Minnaard, Adriaan J.

2014-01-01

Based on the asymmetric copper-catalyzed 1,2-addition of Grignard reagents to ketones, (R,R,R)--tocopherol has been synthesized in 36% yield over 12 steps (longest linear sequence). The chiral center in the chroman ring was constructed with 73% ee by the 1,2-addition of a phytol-derived Grignard

Synthèse et diffusion de résultats de recherche à l'échelle régionale ...

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

PRE) du CRDI a financé plusieurs projets en Afrique orientale et australe. Ces projets ont permis de produire un imposant corpus de connaissances, mais la diffusion de leurs résultats a été limitée. La subvention servira à financer une synthèse ...

Revue des aspects hydrodynamiques des réacteurs catalytiques gaz-liquide-solide à lit fixe arrosé Hydrodynamics of Gas-Liquid-Solid Trickle-Bed Reactors: a Critical Review

Directory of Open Access Journals (Sweden)

Attou A.

2006-12-01

élation empirique de la perte de pression et du taux de rétention de liquide ne correspond à une erreur relative moyenne de prédiction acceptable. Seul le modèle phénoménologique étendu d'Al-Dahhan et al. (1998 semble constituer une technique satisfaisante pour la prédiction des deux paramètres hydrodynamiques en régime ruisselant. Néanmoins, son principal inconvénient réside dans la nécessité de déterminer préalablement les deux coefficients du modèle au moyen d'expériences sur des écoulements monophasiques gazeux. De telles expériences restent difficiles à réaliser dans la pratique. Il est cependant regrettable de constater qu'aucune des ces méthodes, qui se distinguent par leurs résultats, n'est basée sur une approche physique des phénomènes hydrodynamiques permettant d'améliorer la connaissance de ces écoulements et de prédire leur comportement en dehors des domaines de conditions expérimentales testées. De ce travail, il ressort la nécessité d'appliquer les outils classiques de la mécanique des fluides diphasique à la description de ces écoulements, en apportant une attention particulière aux phénomènes d'interactions hydrodynamiques auxquelles sont soumises les trois phases du système (gaz, liquide et solide. While it is recognised that the hydrodynamic aspects have a considerable importance in the design and the operation of gas-liquid-solid trickle-bed reactors, the accuracy of the proposed calculation methods remains poor. Most studies in this field have been performed in atmospheric conditions in contrast of industrial reactors operating at quite high pressures. Only recently, some experimental results have been obtained at elevated pressures and correlations have been proposed in these conditions in order to predict the tricking-pulsing transition, the pressure drop and the liquid holdup. The scope of this article is twice. Firstly, the knowledge on the several hydrodynamic aspects of three-phase trickle-bed reactors, including

Application of TEMPPC code to the IEA-R1 nuclear reactor core hydrothermal calculations operating at 2 MW for determining the minimal coolant flow

International Nuclear Information System (INIS)

Frajndlich, R.; Sousa, J.A. de.

1985-01-01

A thermohydraulic study of the IEA-R1 nuclear reactor core on steady-state operating condition and forced convection, is presented. The objective of this calculation is to obtain the minimal flow rate of coolant necessary at the reactor core, limited by the temperature associated to the beginning of nucleate boiling over the fuel plates at a normal operating power (2MW) for a certain inlet coolant temperature. The coolant system safety level is also calculated in this paper, which is divided in three steps: thermohydraulic calculation, without using the uncertainty factors and, after that, considering these factor by two methods: the statistical and the conventional ones. Whichever the method accepted, the results obtained by the program TEMPPC show a great safety margin with respect to the termohydraulic parameters from the IEA-R1 nuclear reactor. (Author) [pt

The Canadian R and D program targeted at CANDU reactors

International Nuclear Information System (INIS)

Moeck, E.O.

1988-01-01

CANDU reactors produce electricity cheaply and reliably, with miniscule risk to the population and minimal impact on the environment. About half of Ontario's electricity and a third of New Brunswick's are generated by CANDU power plants. Hydro Quebec and utilities in Argentina, India, Pakistan, and the Republic of Korea also successfully operate CANDU reactors. Romania will soon join their ranks. The proven record of excellent performance of CANDUs is due in part to the first objective of the vigorous R and D program: namely, to sustain and improve existing CANDU power-plant technology. The second objective is to develop improved nuclear power plants that will remain competitive compared with alternative energy supplies. The third objective is to continue to improve our understanding of the processes underlying reactor safety and develop improved technology to mitigate the consequences of upset conditions. These three objectives are addressed by individual R and D programs in the areas of CANDU fuel channels, reduced operating costs, reduced capital costs, reactor safety research, and IAEA safeguards. The work is carried out mainly at three centres of Atomic Energy of Canada Limited--the Chalk River Nuclear Laboratories, the Whiteshell Nuclear Research Establishment, and the Sheridan Park Engineering Laboratories--and at Ontario Hydro's Research Laboratories. Canadian universities, consultants, manufacturers, and suppliers also provide expertise in their areas of specialization

Activité collective et réélaboration des règles : des enjeux pour la santé au travail

OpenAIRE

Caroly , Sandrine

2010-01-01

L'activité collective se définit comme une articulation entre le travail collectif et le collectif de travail. Le travail collectif correspond aux modes de coopération et de collaboration entre les membres d'une équipe. Il facilite dans certains cas la mise en œuvre de régulations individuelles et collectives pour gérer les perturbations issues de situations caractérisées par des conflits de but et donnent une ressource à chacun pour ne pas être seul face à la diversité des prescriptions, not...

Development Plan and R and D Status of China Lead-based Reactor

Energy Technology Data Exchange (ETDEWEB)

Wu, Yican; Bai, Yunqing; Song, Yong; Li, Yazhou; Team, FDS [Institute of Nuclear Energy Safety Technology, Beijing (Switzerland)

2013-07-01

Chinese Academy of Sciences (CAS) launched an engineering project to develop ADS system and lead-based reactors named China LEAd-based Reactor (CLEAR) series. The Institute of Nuclear Energy Safety Technology (INEST) will be responsible for the CLEAR design and R and D. In this project, CAS plans to develop the lead-based reactors through 3 phases which are 10MWth lead based research reactor (CLEAR-I), 100MWth lead-based experimental reactor (CLEAR-II), 1000MWth lead-based demonstration reactor (CLEAR-III). As a pre-testing facility, a lead-based zero-power reactor (CLEAR-0) is required to be built before CLEAR-I construction and operation. The new conceptual design of lead-based reactors, including hydrogen production, tritium production for fusion energy and thorium utilization, is also on-going. Lead-lithium cooled fusion reactor blanket design and lead-lithium experimental loops have been developed more than 10 years. CLEAR series reactor conceptual design has been finished and detailed engineering design for CLEAR-I is underway. The R and D activities for CLEAR reactor including design and safety software, key components, structural materials, lead-based experimental loops and neutronics experimental platform are developing. Series of liquid lead-based experimental loops named DRAGON (Lead-Lithium) and KYLIN (Lead-Bismuth) have already been built or on constructing to performed experiments investigating the structure material corrosion issues and the thermal-hydraulic properties of lead-based coolant. The Highly Intensified D-T Neutron Generator HINEG for neutron experiment and software validation will be constructed. Series advanced reactor design software and nuclear library have been developed for lead-alloy cooled reactor, including CAD based Multi-Functional 4D Neutronics Simulation System (Visual Bus), Monte Carlo Automatic Modeling Program for Radiation Transport Simulation (MCAM), Super Monte Carlo Simulation Program (SuperMC), Nuclear Radiation

Development Plan and R and D Status of China Lead-based Reactor

International Nuclear Information System (INIS)

Wu, Yican; Bai, Yunqing; Song, Yong; Li, Yazhou; Team, FDS

2013-01-01

Chinese Academy of Sciences (CAS) launched an engineering project to develop ADS system and lead-based reactors named China LEAd-based Reactor (CLEAR) series. The Institute of Nuclear Energy Safety Technology (INEST) will be responsible for the CLEAR design and R and D. In this project, CAS plans to develop the lead-based reactors through 3 phases which are 10MWth lead based research reactor (CLEAR-I), 100MWth lead-based experimental reactor (CLEAR-II), 1000MWth lead-based demonstration reactor (CLEAR-III). As a pre-testing facility, a lead-based zero-power reactor (CLEAR-0) is required to be built before CLEAR-I construction and operation. The new conceptual design of lead-based reactors, including hydrogen production, tritium production for fusion energy and thorium utilization, is also on-going. Lead-lithium cooled fusion reactor blanket design and lead-lithium experimental loops have been developed more than 10 years. CLEAR series reactor conceptual design has been finished and detailed engineering design for CLEAR-I is underway. The R and D activities for CLEAR reactor including design and safety software, key components, structural materials, lead-based experimental loops and neutronics experimental platform are developing. Series of liquid lead-based experimental loops named DRAGON (Lead-Lithium) and KYLIN (Lead-Bismuth) have already been built or on constructing to performed experiments investigating the structure material corrosion issues and the thermal-hydraulic properties of lead-based coolant. The Highly Intensified D-T Neutron Generator HINEG for neutron experiment and software validation will be constructed. Series advanced reactor design software and nuclear library have been developed for lead-alloy cooled reactor, including CAD based Multi-Functional 4D Neutronics Simulation System (Visual Bus), Monte Carlo Automatic Modeling Program for Radiation Transport Simulation (MCAM), Super Monte Carlo Simulation Program (SuperMC), Nuclear Radiation

Preliminary analysis of control rod accidents in the CRCN-R1 multipurpose reactor core of Recife in Brazil

International Nuclear Information System (INIS)

Souza dos Santos, Rubens; Rubens Maiorino, Jose

1999-01-01

The paper shows some results of the neutronic accident analyses arisen by uncontrolled control rod withdrawal, based on the Conceptual Project of the CRCN-R1 MultiPurpose Reactor of Recife. In that reactor, a project of the CNEN/Brazil, under the leadership of the IPEN/Sao Paulo, is verified the thermal hydraulic limits in the reactor core during transients that simulate startup and power operation accidents. It has utilized a computer program that solved the kinetic equations based on multigroup diffusion theory, in our case we have used 4 energy groups, Two-Dimensional X-Y in the space, and 6 groups of delayed neutrons. A simple model of feedback is admitted in the capture and scattering macroscopic cross sections, in the fuel regions, temperature and coolant densities dependents. Based on those models, the results demonstrated that the reactor exhibits good degree of safety. (author)

R and D relative to the serious accidents in the PWR type reactors: assessment and perspectives; R and D relative aux accidents graves dans les reacteurs a eau pressurisee: bilan et perspectives

Energy Technology Data Exchange (ETDEWEB)

Bentaib, A.; Bonneville, H.; Caroli, H.; Chaumont, B.; Clement, B.; Cranga, M.; Koundy, V.; Laurent, B.; Micaelli, J.C.; Meignen, R.; Pichereau, F.; Plassart, D.; Van-Dorsselaere, P. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Ducros, G.; Journeau, Ch.; Magallon, D. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Durin, M.; Studer, E. [CEA Saclay 91 - Gif sur Yvette (France); Seiler, J.M. [CEA Grenoble, 38 (France); Ranval, W. [Electricite de France (EDF), 75 - Paris (France)

2006-07-01

This document presents the current state of the research relative to the grave accidents realized in France and abroad. It aims at giving the most exhaustive possible and objective vision of this original field of research. He allows to contribute to the identification and to the hierarchical organization of the needs of R and D, this hierarchical organization in front of, naturally, to be completed by a strong lighting on needs in terms of safety analyses associated with the different risks and the physical phenomena, in particular with the support of probability evaluations of safety level 2, whose the level of sharpness must be sufficient not to hide, by construction, physical phenomena of which the limited knowledge leads to important uncertainties. Let us note that neither the safety analyses, nor the E.P.S. 2 are presented in this document. This report presents the physical phenomena which can arise during a grave accident, in the reactor vessel and in the reactor containment, their chain and the means allowing to ease the effects. The corresponding scenarios are presented to the chapter 2. The chapter 3 is dedicated to the progress of the accident in the reactor vessel; the degradation of the core in reactor vessel (3.1), the behavior of the corium in bottom of reactor vessel (3.2) the break of the reactor vessel (3.3) and the fusion in pressure (3.4) are thus handled there. The chapter 4 concerns the phenomena which can lead to a premature failure of the containment, namely the direct heating of gases of the containment (4.1), the hydrogen risk (4.2) and the vapor explosion (4.3). The phenomenon which can lead to a delayed failure from the containment, namely the interaction corium-concrete, is approached on the chapter 5. The chapter 6 is dedicated to the problems connected to the keeping back and to the corium cooling in reactor vessel and out of reactor vessel, namely the keeping back in reactor vessel by re-flooding of the primary circuit or by re

Safety-related Innovative Nuclear Reactor Technology Elements R and D (SINTER) Network and Global HTGR R and D Network (GHTRN). Strategic benefits of international networking

International Nuclear Information System (INIS)

Von Lensa, W.

1998-01-01

The nuclear industries and the nuclear research and development (R and D) programmes world-wide have undergone considerable changes over recent years which have resulted in the formation of international industrial consortiums on the one hand and the need for synergistic collaboration in the R and D area due to the reductions of national R and D activities in the nuclear field on the other hand. International networking starting from precompetitive medium- or long-term oriented R and D could be an efficient mean to overcome the problems nuclear energy is facing today with respect to the lack of public acceptance and economic attractivity in a joint effort. Additional motivation is provided by the fact that there is not only a globalisation of markets but also a 'globalisation of problems' to be addressed internationally like reductions of environmental impacts and long-term availability of economic energy supply. The tools for telecommunication and telecollaboration are evolving in parallel and offer better conditions for closer collaboration of different R and D teams at distant locations than ever before. It is obvious that these trends and boundary conditions will drastically influence the structures of collaboration not only in the industries, but for R and D on an international level, too. The chances emerging from the creation of a European Union and from the globalisation trends have to be converted into strategic benefits by active response on these 'historic changes'. New initiatives have been undertaken in Europe to push for innovations of nuclear reactor technologies via international R and D Networks under the European R and D Framework Programmes (FWP). Innovative approaches are already addressed with limited funding under the actual 4th FWP and should be extended for complementing the commercial efforts on evolutionary LWR concepts by medium- and long-term oriented innovations and R and D. The MICHELANGELO initiative as well as the EU-funded Concerted

Synthesis of carbasugars from aldonolactones, part III - A study on the allylic substitution of (1R,5R,8R)- and (1R,5R,8S)-8-hydroxy-2-oxabicyclo[3.3.0]oct-6-en-3-one derivatives - Preparation of (1S,2R,3R)-9-[2-hydroxy-3-(2-hydroxyethyl)cyclopent-4-en-1-yl]-9H-adenine

DEFF Research Database (Denmark)

Johansen, Steen Karsk; Lundt, Inge

2001-01-01

The palladium-catalyzed substitution of acylated (1R,5R,8R)- and (1R,SR,8S)-8-hydroxy-2-oxabicyclo[3.3.0] ones has been studied using a number of C- and N-nucleophiles, In all cases, the exo derivatives (8R) were found to be more reactive than the corresponding endo derivatives (8S). The reaction...... with these nucleophiles. Additionally, Mitsunobu substitution of (1R,5R,8R)-8-hydroxy-2-oxabicyclo[3.3.0]oct-B-en-3-one (3) with 6-chloropurine, followed by reduction of the lactone moiety and treatment with Liquid ammonia, gave the carbocyclic nucleoside (1S,2R,3R)-9-[2-hydroxy-3-(2-hydroxyethyl)cyclopent-4-en-1-yl]-9H...

Invention de soi et compétences à l’ère des réseaux sociaux

Directory of Open Access Journals (Sweden)

Daniel Apollon

2011-06-01

Full Text Available Les réseaux sociaux en ligne encouragent de nouvelles approches de la compétence centrées sur la construction biographique de l’individu et l’invention de soi. Ce nouvel art de faire des « produsagers », répond au besoin d’inventer une réponse individuelle et collective au sentiment aliénant de vacuité des sociétés post-industrielles et post-traditionnelles. Combinant opposition et soumission aux éléments structurants et aliénants de cette modernité tardive, ces produsagers réactualisent diverses ruses, tactiques et schèmes immémoriaux déjà explorés par divers auteurs avant Internet. Sur cette toile de fond, l’auteur propose une réinterprétation plus large de la notion de compétence.Social media practices encourage new approaches and visions of competence focusing on the construction of individual biography and the "invention of oneself". The new "artful skills" of "produsers" address the need to invent individual and collective responses to the sense of alienating emptiness pervading postindustrial and posttraditional societies. Combining and submission and opposition to both structuring and alienating aspects of late modernity, these produsagers actualize various tricks, tactics and immemorial schemes already mapped by various authors before the Internet. On this backdrop the author proposes a broader reinterpretation of the concept of competence.

Study of IPR-R1 dynamics by reactivity random excitations

International Nuclear Information System (INIS)

Roedel, G.

1983-01-01

To demonstrate the viability of the utilization of analitical techniques of neutronic noise, a dynamic model for IPR-R1 reactor from CDTN was developed. This model allows reactivity feedback due to variations of temperature in fuel and coolant [pt

Géochimie des résines et asphaltènes Geochernistry of Resins and Asphaltenes

Directory of Open Access Journals (Sweden)

Tissot B.

2006-11-01

Full Text Available Les produits lourds des huiles brutes (résines et asphaltènes jouent un rôle important dans la genèse et l'accumulation du pétrole, ainsi que dans la mise en production par des méthodes conventionnelles ou par récupération assistée. Les asphaltènes et résines sont considérés ici comme des fragments de kérogène, avec une structure d'ensemble comparable : ils peuvent constituer des intermédiaires dans la genèse de l'huile brute par dégradation thermique du kérogène. De plus, la pyrolyse des asphaltènes séparés à partir d'un pétrole biodégradé peut produire de nouveaux hydrocarbures saturés qui reproduisent la fraction saturée primitive, détruite par la dégradation ; on peut ainsi disposer d'un nouvel outil pour corréler ce type d'huiles brutes. Les produits lourds semblent défavorisés par rapport aux hydrocarbures, dans la migration de la roche-mère vers le réservoir, où les résines et asphaltènes sont proportionnellement moins abondants. La structure physique des asphaltènes et résines dans les pétroles, et en particulier l'existence d'une macrostructure du type micelles ou agrégats, est probablement responsable de la viscosité élevée des huiles lourdes. Une meilleure connaissance de cette macrostructure pourrait suggérer de nouvelles méthodes pour diminuer la viscosité et améliorer la récupération des huiles lourdes. The heavy constituents of crude oil (resins and asphaltenes play an important role in generation and accumulation of petroleum, and also in production by conventional and enhanced oil recovery processes. Asphaltenes and resins are considered here as small fragments of kerogen, with a comparable overall structure: they may act as intermediate compounds in oil generation by thermal breakdown of kerogen. Furthermore, pyrolysis of asphaltenes separated from a degraded crude oil is able to generate a new saturated hydrocarbon fraction which duplicates the original one, now degraded

Jeunes et stratégies de résilience à la violence et à la criminalité en ...

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

L'objectif général de ce projet est de contribuer à rompre le cycle de production de violence et de criminalité chez les jeunes à travers une meilleure compréhension des facteurs et stratégies de résilience des jeunes et de leurs communautés contre ces violences en Afrique de l'Ouest et en particulier au Burkina Faso et au ...

Y a-t-il convergence réelle et structurelle des pays de l'UEMOA?

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

CHASSEM

variables du cadre macroéconomique et fait l'objet d'une évaluation régulière à travers le suivi des critères de convergence. • la convergence réelle concerne le niveau de revenu ou du PIB par tête. • La convergence structurelle porte sur les caractéristiques structurelles (convergence des structures de demande et d'offre).

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

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

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

Considerations about decommissioning of the IEA-R1 research reactor and the future of its installations after shutdown

International Nuclear Information System (INIS)

Frajndlich, Roberto

2014-01-01

The IEA-R1 Nuclear Research Reactor, in operation since 1957, in the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), is one of the oldest research reactors in the world. However at some point in time in the future, as example of the other reactors, it will be shutdown definitively. Before that time actually arrives, the operational organization needs to plan the future of its installations and define the final destination of equipment and radioactive as well as non-radioactive material contained inside the installations. These and other questions should be addressed in the so called Preliminary decommissioning plan of the installation, which is the subject of this work. The work initially presents an over view about the theme and defines the general and specific objectives describing, in succession, the directions that the operating organization should consider for the formulation of a decommissioning plan. The present structure of the Brazilian nuclear sector emphasizing principally the norms utilized in the management of radioactive waste is also presented. A description of principle equipment of the IEA-R1 reactor which constitutes its inventory of radioactive and non-radioactive material is given. The work emphasizes the experience of the reactor technicians, acquired during several reforms and modifications of the reactor installations realized during its useful life time. This experience may be of great help for the decommissioning in the future. An experiment using the high resolution gamma spectrometric method and computer calculation using Monte Carlo theory were performed with the objective of obtaining an estimate of the radioactive waste produced from dismantling of the reactor pool walls. The cost of reactor decommissioning for different choices of strategies was determined using the CERREX code. Finally, a discussion about different strategies is presented. On the basis of these discussions it is concluded that the most advantageous

2. Le théâtre en révolution. Jeux et enjeux juridiques et politiques 1789–1799

Directory of Open Access Journals (Sweden)

Jahiel Ruffier-Méray

2017-08-01

Full Text Available Cette étude porte sur la manière dont le pouvoir politique a tenté d’instrumentaliser le théâtre et examine les différents moyens juridiques utilisés pour transformer l’art théâtral en outil de propagande durant la période révolutionnaire. Durant tout l’Ancien Régime, le système des spectacles privilégiés règne en maître. En plaçant certaines troupes en situation de monopole, l’État fait le choix d’une politique de régulation des salles. Quant à la surveillance des divertissements, elle est assurée à la fois par la police des spectacles et par la censure. En 1789, avec l’abolition des privilèges, les révolutionnaires remettent en cause tout ce système. Inévitablement, ils sont obligés de s’interroger sur les politiques à mener en matière théâtrale et de repenser les modalités de l’offre artistique. Le théâtre apparaît, dès lors, comme un enjeu majeur situé au cœur des préoccupations révolutionnaires. L’art dramatique concentre à lui seul, toutes les questions débattues avec passion à l’Assemblée.

Leaching Studies on ACR-1000{sup R} Fuel Under Reactor Operating Conditions

Energy Technology Data Exchange (ETDEWEB)

Sunder, S. [Atomic Energy of Canada Limited, Fuel and Fuel Channel Safety Branch, Chalk River, Ontario, K0J 1J0 (Canada)

2009-06-15

ACR-1000{sup R} is the latest nuclear power reactor being developed by AECL. The ACR-1000 fuel uses a modified CANFLEX{sup R} fuel bundle that contains low-enriched uranium and pellets of burnable neutron absorbers (BNA) in a central element. Dysprosium and gadolinium are used as the burnable neutron absorbers and are present as oxides in a 'fully-stabilized' zirconia matrix. The BNA material in the centre element is designed to limit the coolant void reactivity of the reactor core during postulated loss-of-coolant accidents. As part of the ACR-1000 fuel development, the stability of the BNA material under conditions associated with defects of the Zircaloy sheathing of the BNA central element has been investigated. The results of these tests can be used to demonstrate the phase stability and leaching behaviour of the ACR-1000 fuel under reactor operating conditions. The samples were disks, about 3-4 mm thick, obtained from BNA pellets and Candu fuel (natural uranium UO{sub 2}) pellets (the UO{sub 2} measurements provide a reference point). Leaching tests were carried out in light water at 325 deg. C, above the maximum coolant temperature in an ACR-1000 fuel channel during normal operating conditions (319 deg. C). This temperature also bounds the maximum operating temperature for the current Candu reactors (311 deg. C). The initial pH of the solution (measured at room temperature) used in the leaching tests was 10.3. The leach rates were determined by monitoring the amount of metals leached into solutions. Leaching tests were also carried out with BNA pellet samples in the presence of Zr-2.5%Nb pressure tube coupons to determine the effects, if any, of the presence of pressure tube material on leach rates. Other leaching tests with BNA pellet samples and UO{sub 2} pellets were conducted at 80 deg. C to study the effects of temperature on the leach rates. The temperature of 80 deg. C was selected as representative of typical shutdown temperatures

Entre libération et représentation réductrice : La pornographie gaie masculine comme véhicule de stéréotypes

Directory of Open Access Journals (Sweden)

Geneviève Rail

2010-02-01

Full Text Available Inspirée d’un cadre poststructuraliste, cette étude qualitative de « réception d’un médium » nous a permis de mettre en lumière les « lectures » que font une vingtaine de consommateurs de pornographie des notions de masculinité, de race et ethnicité, du milieu gai et du genre en lien avec la pornographie qu’ils consomment. Les résultats qui émergent de notre analyse critique de discours sont à l’effet que les lectures des consommateurs sont majoritairement dominantes, reproduisant ainsi les stéréotypes présents en société et qui sont re/produits et véhiculés dans la pornographie qu’ils consomment. Les récits des participants attestent du fait que ces derniers remettent peu en question ce qu’ils voient dans le matériel pornographique ; matériel pouvant avoir certaines répercussions sur des indicateurs de santé mentale en accentuant et perpétuant certaines formes de stigmatisation chez certains groupes sociaux. Inspired by a poststructuralist perspective, our qualitative exploratory media reception study offers a critical discourse analysis of 20 male pornography consumers, focusing on their readings of masculinity, race/ethnicity, the gay world, and gender in relation to the pornography they consume. For the most part, results show dominant readings of these categories, which suggests that social stereotypes are produced, reproduced, and transmitted through the medium of pornography. Participant narratives reveal individuals who rarely question what is shown in pornographic material; the latter having potential implications for certain mental health indicators, as well as perpetuating and accentuating forms of stigmatization among specific social groups.

Justice devant les tribunaux, réparations et reddition de comptes en ...

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

Justice devant les tribunaux, réparations et reddition de comptes en lien avec les massacres religieux ou liés à la caste en Inde. La constitution laïque de l'Inde protège les minorités religieuses, les dalits et les communautés tribales et garantit à tous les citoyens l'égalité devant la loi. Or, dans les faits, les épisodes ...

Real-Time Monitoring of Neutron Capture Cross Section in the IPR-R1 TRIGA Research Reactor as a Fuel Temperature Function

Energy Technology Data Exchange (ETDEWEB)

Palma, D.A.P. [Comissao Nacional de Energia Nuclear, CNEN, General Severiano Street, 90, 22290-901, Rio de Janeiro (Brazil); Mesquita, A.Z.; Souza, R.M.G.P. [Comissao Nacional de Energia Nuclear, CNEN/CDTN, Av. Presidente Antonio Carlos, 6627, 31270-901, Belo Horizonte (Brazil); Martinez, A.S. [Programa de Engenharia Nuclear, COPPE/UFRJ, Av. Horacio Macedo, 2030, Bloco G, 21941- 914, Rio de Janeiro (Brazil)

2011-07-01

Nuclear reactor operators have to monitor the behaviour of different nuclear and design parameters that vary in time to ensure the operating safety of the reactor. In recent years several operating parameters for the IPR-R1 TRIGA research reactor were monitored and indicated in real-time by the data acquisition system developed for the reactor, with all the data being stored in a hard disk in the data acquisition computer, to build in this way a database. The goal of this work is to insert in the set of parameters already collected the neutron capture cross sections for the fuel, from the power and temperature numbers obtained in real-time. The experimental data was obtained by using a fuel element instrumented with temperature sensors, located in the core of the IPR-R1 TRIGA research reactor at the CDTN - Centre for Development of Nuclear. This information is useful for the continuous monitoring of the reaction rate in neutron capture. For that, a new analytical formulation is used for the Doppler broadening function proposed by Palma and Martinez which is free from special functions in its functional form and with easy computing implementation. The results obtained were satisfactory from the standpoint of accuracy in comparison with the numerical reference method and indicate that it is possible to carry out real-time monitoring of the neutron capture cross section in the fuel. (author)

Fission track dating method: I. Study of neutron flux uniformity in some irradiation positions of IEA-R1 reactor

International Nuclear Information System (INIS)

Osorio, A.M.; Hadler, J.C.; Iunes, P.J.; Paulo, S.R. de

1993-06-01

In order to use the fission track dating method the flux gradient was verified within the sample holder, in some irradiation positions of the IEA-R1 reactor at IPEN/CNEN, Sao Paulo. The fission track dating method considers only the thermal neutron fission tracks, to subtract the other contributions sample irradiations with a cadmium cover was performed. The neutron flux cadmium influence was studied. (author)

Interactions inter/intra stades de développement et régénération de ...

African Journals Online (AJOL)

SARAH

31 janv. 2014 ... Objectifs : Cette étude a été réalisée dans l'objectif de comprendre la dynamique de régénération via la répartition spatiale et interaction inter/intra stade ... mécanismes de recrutement dans les populations d'arbres indigènes du miombo katangais et de l'autre d'approfondir les connaissances concernant ...

Impact of uranium concentration reduction in side plates of the fuel elements of IEA-R1 reactor on neutronic and thermal hydraulic analyses

International Nuclear Information System (INIS)

Rios, Ilka Antonia

2013-01-01

This master thesis presents a study to verify the impact of the uranium concentration reduction in the side plates of the reactor IEA-R1 fuel elements on the neutronic and thermal-hydraulic analyses. To develop such study, a previous IPEN-CNEN/SP research was reproduced by simulating the fuel elements burn-up, with side plate uranium density reduced to 50, 60 and 70% of the standard fuel element plates. This research begins with the neutronic analysis using the computer code HAMMER and the first step consists in the calculation of the cross section of all materials presented at the reactor core, with their initial concentration; the second step consists in the calculation of the fast and thermal neutron group fluxes and power densities for fuel elements using the computer code CITATION. HAMMER output data is used as input data. Once the neutronic analysis is finished and the most critical fuel elements with highest power density have been defined, the thermal-hydraulics analysis begins. This analysis uses MCTR-IEA-R1 thermal-hydraulics model, which equations are solved by commercial code EES. Thermalhydraulics analysis input is the power density data calculated by CITATION: it is considered the highest power density on each fuel element, where there is a higher energy release and, consequently, higher temperatures. This data is used on energy balance equations to calculate temperatures on critical fuel element regions. Reactor operation comparison for three different uranium densities on fuel side plates is presented. Uranium density reduction contributes to the cladding surface temperature to remain below the established limit, as reactor operation safety requirement and it does not affect significantly fuel element final burn-up nor reactor reactivity. The reduction of uranium in the side plates of the fuel elements of the IEA-R1 showed to be a viable option to avoid corrosion problems due to high temperatures. (author)

The neutron and gamma-ray dose characterization using the Monte Carlo method to study the feasibility of the Prompt Gamma Activation Analysis technique at IPR-R1 TRIGA reactor in Brazil

Energy Technology Data Exchange (ETDEWEB)

Guerra, Bruno T.; Soares, Alexandre L.; Grynberg, Suely E.; Menezes, Maria Angela B.C., E-mail: brunoteixeiraguerra@yahoo.com.br, E-mail: menezes@cdtn.br, E-mail: asleal@cdtn.br, E-mail: seg@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

The IPR-R1 is a reactor type TRIGA, Mark-I model, manufactured by the General Atomic Company and installed at Nuclear Technology Development Centre (CDTN) of Brazilian Nuclear Energy Commission (CNEN), in Belo Horizonte, Brazil. It is a light water moderated and cooled, graphite-reflected, open-pool type research reactor. IPR-R1 works at 100 kW but it will be briefly licensed to operate at 250 kW. It presents low power, low pressure, for application in research, training and radioisotopes production. The fuel is an alloy of zirconium hydride and uranium enriched at 20% in {sup 235}U. The Implementation of the PGNAA (Prompt Gamma Neutron Activation Analysis) Technical at the TRIGA IPR-R1 research reactor of the CDTN will significantly increase in the types of matrices analyzable. A project is underway in order to implement this technique in CDTN. In order of verified the feasibility of the PGNAA at the TRIGA reactor, the MCNP (Monte Carlo N-Particle) method is used to theoretical calculations. This paper presents the results of a preliminary study of the neutron and gamma-ray dose in the room where the reactor is located, in case of implementation of this technique in the IPR-R1. (author)

The neutron and gamma-ray dose characterization using the Monte Carlo method to study the feasibility of the Prompt Gamma Activation Analysis technique at IPR-R1 TRIGA reactor in Brazil

International Nuclear Information System (INIS)

Guerra, Bruno T.; Soares, Alexandre L.; Grynberg, Suely E.; Menezes, Maria Angela B.C.

2013-01-01

The IPR-R1 is a reactor type TRIGA, Mark-I model, manufactured by the General Atomic Company and installed at Nuclear Technology Development Centre (CDTN) of Brazilian Nuclear Energy Commission (CNEN), in Belo Horizonte, Brazil. It is a light water moderated and cooled, graphite-reflected, open-pool type research reactor. IPR-R1 works at 100 kW but it will be briefly licensed to operate at 250 kW. It presents low power, low pressure, for application in research, training and radioisotopes production. The fuel is an alloy of zirconium hydride and uranium enriched at 20% in 235 U. The Implementation of the PGNAA (Prompt Gamma Neutron Activation Analysis) Technical at the TRIGA IPR-R1 research reactor of the CDTN will significantly increase in the types of matrices analyzable. A project is underway in order to implement this technique in CDTN. In order of verified the feasibility of the PGNAA at the TRIGA reactor, the MCNP (Monte Carlo N-Particle) method is used to theoretical calculations. This paper presents the results of a preliminary study of the neutron and gamma-ray dose in the room where the reactor is located, in case of implementation of this technique in the IPR-R1. (author)

Métagénomique virale et pathologie: une histoire récente

OpenAIRE

Bernardo, Pauline; Albina, Emmanuel; Eloit, Marc; Roumagnac, Philippe

2013-01-01

L’étude des maladies virales humaines, animales et végétales a récemment bénéficié du développement de la métagénomique en écologie. Cette approche, dite sans a priori, consiste à décrire le génome viral total, ou virome, d’une fraction d’un écosystème sans tenir compte de cibles moléculaires déjà connues. Les premiers résultats de la métagénomique en pathologie virale ont été obtenus très localement au niveau d’un tissu ou d’un organe. Ils ont débouché sur la découverte de nouveaux virus et ...

40 CFR Table 1 to Subpart R of... - General Provisions Applicability to Subpart R

Science.gov (United States)

2010-07-01

... Subpart R 1 Table 1 to Subpart R of Part 63 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... Pipeline Breakout Stations) Pt. 63, Subpt. R, Table 1 Table 1 to Subpart R of Part 63—General Provisions Applicability to Subpart R Reference Applies to subpart R Comment 63.1(a)(1) Yes 63.1(a)(2) Yes 63.1(a)(3) Yes...

Hydrologic Tests at Characterization Wells R-9i, R-13, R-19, R-22, and R-31, Revision 1

Energy Technology Data Exchange (ETDEWEB)

S.G.McLin; W.J. Stone

2004-06-01

Hydrologic information is essential for environmental efforts at Los Alamos National Laboratory. Testing at new characterization wells being drilled to the regional aquifer (''R wells'') to improve the conceptual hydrogeologic model of the Pajarito Plateau is providing such information. Field tests were conducted on various zones of saturation penetrated by the R wells to collect data needed for determining hydraulic properties. This document provides details of the design and execution of testing as well as an analysis of data for five new wells: R-9i, R-13, R-19, R-22, and R-31. One well (R-13) was evaluated by a pumping test and the rest (R-9i, R-19, R-22, and R-31) were evaluated by injection tests. Characterization well R-9i is located in Los Alamos Canyon approximately 0.3 mi west of the Route 4/Route 502 intersection. It was completed at a depth of 322 ft below ground surface (bgs) in March 2000. This well was constructed with two screens positioned below the regional water table. Both screens were tested. Screen 1 is completed at about 189-200 ft bgs in fractured basalt, and screen 2 is completed at about 270-280 ft bgs in massive basalt. Specific capacity analysis of the screen 1 data suggests that the fractured basalt has a transmissivity (T) of 589 ft{sup 2}/day and corresponds to a hydraulic conductivity (K) of 7.1 ft/day based on a saturated thickness of 83 ft. The injection test data from the massive basalt near screen 2 were analyzed by the Bouwer-Rice slug test methodology and suggest that K is 0.11 ft/day, corresponding to a T of about 2.8 ft{sup 2}/day based on a saturated thickness of 25 ft. Characterization well R-13 is located in Mortandad Canyon just west of the eastern Laboratory boundary. It was completed at a depth of 1029 ft bgs in February 2002. This well was constructed with one 60-ft long screen positioned about 125 ft below the regional water table. This screen is completed at about 958-1019 ft bgs and straddles the

R[ionuclide transport after the Chernobyl reactor accident and derivation of r[ioecological parameters

International Nuclear Information System (INIS)

Bonka, H.

1998-01-01

Since due to the nuclear reactor accident in Chernobyl r[ionuclides arrived in the vicinity of Aachen, the enhancement of the local dose rate, the deposition of the different r[ionuclides on ground and vegetation and the transport of the r[ionuclides into the environment were measured. Partly the measurements were continued until today. Very informative time sequences of the specific activity in grass, food, cow's milk, beef, in the different plants, trees, ploughed soil and undisturbed soil, mushrooms, game, in humans etc. resulted. During different private and official journeys in the old Laender of the Federal Republic of Germany surface covering measurements of the 134 Cs and 137 Cs activity deposited on grass land at different places were carried out. These data were implemented into a map on ground contamination in 1986 in Germany, published in 1991 by the Institute for Water, Soil and Air Hygiene of the Federal Public Health Department in Berlin. Transfer factors soil-grass were measured in the whole Federal Republic of Germany analyzing grass samples which were partly taken at the same time. A large amount of r[ioecological parameters could be derived from the different time sequences. These are in particular: The deposition velocity for iodine and particle bound r[ioanuclides on grass and in forests, the rainout coefficient in dependence of the precipitation intensity, the retention factors on grass, the biological half-life time on grass, the transfer factor soil-grass in dependence of time, the transfer factor food-milk during the pasture period and during stable stay, the transfer factor food-beef, the transfer factors in eatable mushrooms, the translocation factor of cesium in cereals etc. A multi-compartment model was developed to calculate the specific Cs activity in cow's milk and beef. The specific activity in milk can be calculated sufficiently exact using a simple single compartment model. The correlation of the specific Cs activity in spruce

ORNL R and D on advanced small and medium power reactors: selected topics

International Nuclear Information System (INIS)

White, J.D.; Trauger, D.B.

1989-01-01

From 1984-1985, ORNL studied several innovative small and medium power nuclear concepts with respect to viability. Criteria for assessment of market attractiveness were developed and are described here. Using these criteria and descriptions of selected advanced reactor concepts, an assessment of their projected market viability in the time period 2000-2010 was made. All of these selected concepts could be considered as having the potential for meeting the criteria but, in most cases, considerable R and D would be required to reduce uncertainties. This work and later studies of safety and licensing of advanced, passively safe reactor concepts by ORNL are described. The results of these studies are taken into account in most of the current (FY 1989) work at ORNL on advanced reactors. A brief outline of this current work is given. One of the current R and D efforts at ORNL which addresses the operability and safety of advanced reactors is the Advanced Controls Program. Selected topics from this Program are described

P R Vasudeva Rao

Indian Academy of Sciences (India)

Home; Journals; Sadhana. P R Vasudeva Rao. Articles written in Sadhana. Volume 27 Issue 5 October 2002 pp 527-558. Development of fuels and structural materials for fast breeder reactors · Baldev Raj S L Mannan P R Vasudeva Rao M D Mathew · More Details Abstract Fulltext PDF. Fast breeder reactors (FBRs) are ...

Mécanismes d’activation et interactions fonctionnelles hétérologues des récepteurs aux chimiokines

OpenAIRE

de Poorter, Cédric

2012-01-01

Mécanismes d’activation et conséquences fonctionnelles de la dimérisation des récepteurs aux chimiokinesLes chimiokines sont de petites protéines qui régulent la migration des cellules immunitaires. Elles exercent leur action en se liant à des récepteurs appartenant à la famille des récepteurs couplés aux protéines G (RCPG) dont la fonction est intimement liée à la régulation des cellules immunitaires. Notre laboratoire étudie depuis plusieurs années les relations reliant la structure et la f...

77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

Science.gov (United States)

2012-05-03

... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...

Les "Questions et réponses sur les évangiles" d'Eusèbe de Césarée: étude et édition du résumé grec

OpenAIRE

Zamagni, Claudio; Junod, Eric; Le Boulluec, Alain

2005-01-01

Cette thèse propose la première édition critique de l’une des traditions les plus importantes des Questions et réponses sur les évangiles d’Eusèbe de Césarée, dont l’original est perdu. Il s’agit de l’édition du manuscrit contenant l’anthologie grecque du manuscrit Vaticanus Pal. Gr. 220. Cette anthologie est composée presque intégralement d’une suite d’extraits du texte original, non résumés, dont l’auteur n’est pas Eusèbe et dont la date ne peut pas être reportée avant le V-VIème siècle. Ce...

Différences de sexe et rôle de l'internalisation des règles sur la propension des enfants à prendre des risques à vélo

OpenAIRE

GRANIE, Marie-Axelle

2011-01-01

L'objectif de cette étude est d'explorer les différences de sexe et l'effet de l'internalisation des règles routières sur la propension des enfants à prendre des risques à vélo. La perception du risque accidentel pour soi, l'internalisation des règles routières relatives aux comportements cyclistes et la propension à prendre des risques à vélo de 145 enfants (86 garçons et 59 filles) de 9 à 12 ans ont été mesurés par un autoquestionnaire. Les résultats montrent des différences de sexe sur l'i...

Molecular characterization of the Jatropha curcas JcR1MYB1 gene encoding a putative R1-MYB transcription factor

Directory of Open Access Journals (Sweden)

Hui-Liang Li

2014-09-01

Full Text Available The cDNA encoding the R1-MYB transcription factor, designated as JcR1MYB1, was isolated from Jatropha curcas using rapid amplification of cDNA ends. JcR1MYB1 contains a 951 bp open reading frame that encodes 316 amino acids. The deduced JcR1MYB1 protein was predicted to possess the conserved, 56-amino acid-long DNA-binding domain, which consists of a single helix-turn-helix module and usually occurs in R1-MYBs. JcR1MYB1 is a member of the R1-MYB transcription factor subfamily. A subcellular localization study confirmed the nuclear localization of JcR1MYB1. Expression analysis showed that JcR1MYB1 transcripts accumulated in various examined tissues, with high expression levels in the root and low levels in the stem. JcR1MYB1 transcription was up-regulated by polyethylene glycol, NaCl, and cold treatments, as well as by abscisic acid, jasmonic acid, and ethylene treatment. Analysis of transgenic tobacco plants over-expressing JcR1MYB1 indicates an inportant function for this gene in salt stress.

Measurement of thermal, epithermal and fast neutron flux in the IEA-R1 reactor by the foil activation method

International Nuclear Information System (INIS)

Koskinas, M.F.

1979-01-01

Experimental and theoretical details of the foil activation method applied to neutrons flux measurements at the IEA-R1 reactor are presented. The thermal - and epithermal - neutron flux were determined form activation measurements of gold, cobalt and manganese foils; and for the fast neutron flux determination, aluminum, iron and nickel foils were used. The measurements of the activity induced in the metal foils were performed using a Ge-Li gamma spectrometry system. In each energy range of the reactor neutron spectrum, the agreement among the experimental flux values obtained using the three kind of materials, indicates the consistency of the theoretical approach and of the nuclear parameters selected. (Author) [pt

Design and properties of marine reactors and associated R and D

Energy Technology Data Exchange (ETDEWEB)

Gagarinski, A; Ignatiev, V [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation); Devell, L [Studsvik Eco and Safety AB, Nykoeping (Sweden)

1996-05-01

The report is a review of open information available in the USA, UK, France, Russia and other countries on the design and properties of marine reactors and associated R and D. First, a short discussion is given of the milestones and main trends for the development of nuclear-powered ships. Then a brief review is presented of features for ship reactor design. Light water and liquid metal cooled reactor technologies are described and reactor operating experiences for Russian ice-breakers assessed. Traditional and alternative civil uses of submarine and surface shipboard reactor technology in Russia and Japan are also treated. Finally, some problems connected with radioactive waste by the nuclear-powered fleet are briefly considered. 41 refs, 27 figs, 19 tabs.

Design and properties of marine reactors and associated R and D

International Nuclear Information System (INIS)

Gagarinski, A.; Ignatiev, V.; Devell, L.

1996-05-01

The report is a review of open information available in the USA, UK, France, Russia and other countries on the design and properties of marine reactors and associated R and D. First, a short discussion is given of the milestones and main trends for the development of nuclear-powered ships. Then a brief review is presented of features for ship reactor design. Light water and liquid metal cooled reactor technologies are described and reactor operating experiences for Russian ice-breakers assessed. Traditional and alternative civil uses of submarine and surface shipboard reactor technology in Russia and Japan are also treated. Finally, some problems connected with radioactive waste by the nuclear-powered fleet are briefly considered. 41 refs, 27 figs, 19 tabs

Utilisation des antibiotiques et profil de résistance des souches de ...

African Journals Online (AJOL)

sanitaire des élevages avicoles (OMS/FAO,. 2002 ; Chahed, 2007). Considérées le plus souvent comme des .... base du type d'exploitation : la première de type semi-industriel et la seconde de type traditionnel. Les ... industriel sur les antibiotiques enregistrés était de 100% et largement supérieure à celui observé chez les ...

Les séries et la guerre (pistes de lectures et de réflexion)

OpenAIRE

Boutet, Marjolaine

2016-01-01

Guerre, mémoire, identité Avec les séries policières, les séries historiques sont le genre le plus populaire sur les télévisions du monde entier. Parce que la télévision s’est construite d’abord comme un média national et, particulièrement en Occident, comme un média de reconstruction nationale après la Seconde Guerre mondiale, elle fut aussi, plus ou moins consciemment, un vecteur important du « récit national ». Au sein de ces récits, les guerres occupent une place particulière, puisque, co...

Steviamine, a new class of indolizidine alkaloid [(1R,2S,3R,5R,8aR-3-hydroxymethyl-5-methyloctahydroindolizine-1,2-diol hydrobromide

Directory of Open Access Journals (Sweden)

Amber L. Thompson

2009-11-01

Full Text Available X-ray crystallographic analysis of the title hydrobromide salt, C10H20N+·Br−, of (1R,2S,3R,5R,8aR-3-hydroxymethyl-5-methyloctahydroindolizine-1,2-diol defines the absolute and relative stereochemistry at the five chiral centres in steviamine, a new class of polyhydroxylated indolizidine alkaloid isolated from Stevia rebaudiana (Asteraceae leaves. In the crystal structure, molecules are linked by intermolecular O—H...Br and N—H...Br hydrogen bonds, forming double chains around the twofold screw axes along the b-axis direction. Intramolecular O—H...O interactions occur.

Influence de la pression et de la non-idéalité des gaz dans le calcul d'un réacteur d'ammoniac Influence of Gas Pressure and Non-Iddeality on Designing an Ammonia Reactor

Directory of Open Access Journals (Sweden)

Scheiderman B.

2006-11-01

Full Text Available Le mélange gazeux qui parcourt un réacteur de synthèse d'ammoniac présente des écarts notables par rapport aux gaz idéaux. On a établi les équations de calcul d'un réacteur à gradient thermique optimum en tenant compte de l'influence de ces écarts sous trois pressions d'opération (150, 300 et 500 atm.. On a vérifié que les corrections principales à effectuer sont dues à la fugacité; les autres sont d'une importance moindre, et affectent surtout le contrôle du réacteur. En outre, on a mis en évidence l'influence considérable de la pression totale. The gaseous mixture flowing through an ommonia synthesis reactor shows considerable divergences from the behovior of ideal gases. These divergences are examined at three operating pressures (150, 300 and 500 atm, and the corresponding design equations for an optimum temperature progression are determined. The main diver gences are those caused by fugacity. The others are of lesser importance. At the same time, the great influence of total pressure is demonstrated.

Allocutions et présentations du Jour 1: Ouverture et Session ...

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

Allocutions et présentations du Jour 1: Ouverture et Session introductive. 04 novembre 2010. Jérôme Gérard. Retrouvez les documents présentés lors de la cérémonie d'ouverture et de la session introductive du Colloque ci-dessous. Interventions de la Cérémonie d'ouverture: Pr. Dieudonné OUEDRAOGO, Directeur de ...

Application of non-destructive methods for qualification of the U3O8-Al and U3Si2-Al dispersion fuels in the IEA-R1 Reactor

International Nuclear Information System (INIS)

Silva, Jose Eduardo Rosa da

2011-01-01

IPEN/CNEN-SP manufactures fuels to be used in its nuclear research reactor - the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil doesn't have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP has conducted a fuel qualification program based on the use of uranium compounds, internationally tested and qualified to be used in research reactors, and has gotten experience in the technological development stages for the manufacturing of fuel plates, irradiation and non-destructive post-irradiation testing. Fuel elements containing low volume fractions of fuel in the dispersion were manufactured and irradiated successfully directly in the core of the IEA-R1. However, there are plans to increase the uranium density of these fuels. The objective of this thesis work was to study and to propose a set of non-destructive methods to qualify the dispersions fuels U 3 O 8 -Al e U 3 Si 2 -Al with high uranium density produced at IPEN/CNEN-SP. For that, the irradiation resources in the IEA-R1, and the application of non-destructive methods in the reactor pool available in the Institution were considered. The proposal is to specify, manufacture and irradiate fuel mini plates in IEA-R1 at the maximum densities, qualified internationally, and to monitor their general conditions during the period of irradiation, using non-destructive methods in the reactor pool. In addition to the non-destructive visual inspection and sipping methods, already used at the Institution, the infrastructure for dimensional sub-aquatic testing to evaluate the swelling of irradiated fuel mini plates was completed. The analyses of the results will provide means to assess and decide whether or not to continue with the irradiation of mini plates, until the desired burnup for the irradiation tests at IEA-R1 are reached. (author)

Texte itératif et stéréotypes chez William Burroughs : de l’intertextualité à l’autostéréotypie

Directory of Open Access Journals (Sweden)

Benoît Delaune

2009-12-01

Full Text Available L’auteur américain William Burroughs, dans sa Trilogie des années 1960 à 1968 (The Soft Machine, The Ticket That Exploded, Nova Express a largement recouru, via sa technique du « cut-up » ou découpage/remontage de textes, à des emprunts littéraux ou indirects à toutes les littératures et paralittératures, et plus globalement à des procédures de reprise voire de ressassement continuel de textes, sous forme littérale ou tronquée. Nous nous proposons d’étudier la manière dont, de livre en livre, William Burroughs construit un véritable réseau de stéréotypes personnels qui lui permettent de mettre en place une identité textuelle forte, selon ce qu’on pourrait qualifier d’autostéréotypie (Stéphanie Orace et Jean-Louis Dufays. L’application de la théorie de l’autostéréotypie sur un texte « résistant » comme le texte cut-up burrougshien permet de dépasser les limites des différents théories de l’intertextualité (transtextualité, autotextualité, intratextualité et de tenter une théorisation à un niveau plus global des phénomènes de reprises textuelles littérales, tronquées, réécrites ou remontées sur un corpus de textes défini.The American writer William Burroughs, in his Trilogy written and published from 1960 to 1968 (The Soft Machine, The Ticket That Exploded, Nova Express has largely used, via his “cut-up” technique of cutting/reassembling different texts, directly or indirectly, every type of texts and literatures, including popular literatures. More generally he used some techniques of repeating a continuous text, literally or incompletely. We study the way in which, book after book, William Burroughs built a network of personal stereotypes which enable him to establish a strong textual identity, according to what is essentially called “autostéréotypie” (Stephanie Orace and Jean-Louis Dufays. The application of the theory of “autostéréotypie” on “resisting” texts as

Dénonciation et récupération du stéréotype dans l'œuvre romanesque de Jardiel Poncela

Directory of Open Access Journals (Sweden)

Cécile François

2009-12-01

Full Text Available Fondée sur une esthétique de la répétition, voire du ressassement perpétuel, la littérature populaire de masse constitue une forme de « prêt-à-lire » à destination d'un lecteur considéré avant tout comme un consommateur. A l'intérieur de cette production, le roman d'amour apparaît comme un genre particulièrement codifié, qui s'organise autour de motifs récurrents et de séquences narratives et thématiques stéréotypées. Dans sa trilogie romanesque, qu'il définit d'emblée comme une satire littéraire, Enrique Jardiel Poncela propose au lecteur une promenade ludique et démystifiante dans les coulisses du genre. Rédigée à la fin des années 1920, l'œuvre de l'écrivain madrilène s'inscrit, en effet, dans un contexte de méfiance généralisée à l'égard des stéréotypes, caractéristique des Avant-gardes littéraires et artistiques. Outre la dénonciation directe par le biais de commentaires métanarratifs particulièrement caustiques, la dimension iconoclaste de la trilogie apparaît sous la forme d'une dénudation systématique et ironique des paradigmes narratifs traditionnels. La séquence stéréotypée du fameux duo d'amour, avec ses traits récurrents, tels que la promenade au clair de lune, le premier baiser ou les larmes de l'héroïne, fait ainsi les frais de l'humour anticonformiste et subversif de l'auteur. Toutefois, pour Jardiel Poncela, déconstruction n'est pas synonyme de destruction. A l'encontre des Dadaïstes qui prétendaient faire table rase des conventions dominantes, le jeune auteur, quant à lui, entend faire œuvre de création grâce à une récupération ludique et inventive du stéréotype. C'est ainsi que pour redynamiser des pratiques romanesques sclérosées, Jardiel Poncela se réfère non seulement à de nouveaux moyens d'expression, tels que la bande dessinée ou le cinéma, mais il sollicite également la coopération d'un lecteur complice qu'il associe en permanence à ses jeux de

Les marqueurs de l'inflammation chez les bovins : nature, physiopathologie et intérêt diagnostique

OpenAIRE

Corbière, Fabien

2002-01-01

La réaction inflammatoire non spécifique est un mécanisme de défense de l'organisme face aux micro-organismes et aux destructions tissulaires. Elle se traduit par des modifications locales et générales visant essentiellement à éliminer l'agent agresseur et restaurer l'homéostasie. Les variations de certains paramètres biochimiques et hématocytologiques induites par la réaction inflammatoire peuvent être utilisées à des fins diagnostiques. Pour être interprétables, ces paramètres doivent dépen...

Pensées répétitives et contrôle cognitif : quels liens avec l'anxiété et la dépression ?

OpenAIRE

Ismaili, Tringa

2013-01-01

L’objectif de cette recherche a été d’examiner les liens entre : (1) deux formes de pensées répétitives (PR), les ruminations et les inquiétudes, et les symptômes d’anxiété et de dépression ; (2) entre le processus de flexibilité de source et la fréquence de diverses pensées répétitives. 97 jeunes adultes issus de la population générale ont été inclus dans l’étude. Les analyses de corrélations ont montré de forts liens entre les PR et les symptômes d’anxiété et de dépression. Une analyse de c...

Barium from a mini r-process in supernovae

Science.gov (United States)

Heymann, D.

1983-01-01

McCulloch and Wasserburg (1978) have reported nonlinear isotopic anomalies in barium for two Ca-Al-rich inclusions of the Allende carbonaceous chondrite, known as EK-1-4-1 and C-1. In an attempt to account for these anomalies, it has been proposed that Ba from an r-process of nucleosynthesis, containing Ba-135 and Ba-137, was injected into the primeval color system but was not totally homogenized. Questions arise in connection with the relations of Xe isotopes in carbonaceous chondrites. This has prompted Heymann and Dziczkaniec (1979, 1980, 1981) to study the formation of r-Xe, r-Kr, and r-Te by the mini r-process which is thought to occur in the O, Ne-rich shells of Type II supernovae. Lee et al. (1979) have studied the formation of r-Ba, r-Nd, and r-Sm by the same process. Certain differences regarding the approaches used by Lee et al. and by Heymann and Dziczkaniec make it necessary to restudy the work of Lee et al. Attention is given to the survival probabilities of nuclear species of interest, taking into accounts the elements Cs, Ba, I, and Xe.

Neutron activation analysis at CDTN/CNEN using the IPR-R1 Triga Mark I reactor

International Nuclear Information System (INIS)

Menezes, Maria Angela de B.C.; Maretti Junior, Fausto; Kastner, Geraldo Frederico; Amaral, Angela Maria; Souza, Wagner de

2009-01-01

This paper describes in summary the activities developed by the Laboratory for Neutron Activation Analysis since the starting up of the IPR-R1 TRIGA Mark I research reactor in 1960. This Laboratory is located at Centro de Desenvolvimento da Tecnologia Nuclear (Nuclear Technology Development Centre) / Comissao Nacional de Energia Nuclear (Brazilian Commission for Nuclear Energy), CDTN/CNEN. The activities of the Laboratory comprise the delayed fission neutron activation analysis, instrumental (comparative and parametric methods) and radiochemical / chemical methods. These methods are responsible for significant percentage of CDTN's analytical demand, meeting the clients' analytical needs and researches developed by the Laboratory, by CDTN and by other institutions. Over the years the work has been linked to the goals of the country and the institutions. Nowadays the neutron activation analysis is responsible for 70% of the analytical demand and the k 0 - Instrumental method for 80% of this demand answering clients' request and researches. In Brazil, CDTN is the only Institute that fully masters the Instrumental Neutron Activation Analysis k 0 -method using its own nuclear reactor. (author)

Chocolat, sexe et argent: comment le cerveau représente-t-il les récompenses?

NARCIS (Netherlands)

Sescousse, G.; Bault, N.; Chambon, V.; Roy, J.M.; Bault, N.; Chambon, V.; Maionchi-Pino, N.; Pénicaud, F.X.; Putois, B.

2011-01-01

Quoi de commun entre un carré de chocolat, une séance de strip-tease et un billet de 100 € ? Peu de choses à première vue… sinon que ces stimuli sont considérés par la plupart des individus comme plaisants, et constituent à ce titre des « récompenses », au sens défini par les psychologues. Depuis

Real-time neutron radiography at the Iea-R1 m nuclear research reactor

International Nuclear Information System (INIS)

Menezes, M.O. de; Pugliesi, R.; Pereira, M.A.S.; Andrade, M.L.G.

2003-01-01

A LIXI (Light Intensifier X-ray Image) device has been employed in a real-time neutron radiography system. The LIXI is coupled to a video camera and the real-time images can be observed in a TV monitor, and processed in a computer. In order to get the real-time system operational, the neutron radiography facility installed at the IEA-R1 m nuclear research reactor of the IPEN-CNEN/S P has been optimized. The most important improvements were the neutron/gamma ratio, the effective energy of the neutron beam, decrease of the scattered radiation at the irradiation position, and the additional shielding of the video camera. Several one-frame as well as computer processed images are presented. The overall Modulation Transfer Function for the real-time system was obtained from the resolution parameter p = 0:44 +- 0:04 mm; the system sensitivity, evaluated for a Perspex step wedge, was determined and the average value is 0:70 +- 0:09 mm. (author)

Civilsamfundets ABC: R for Regulering

DEFF Research Database (Denmark)

Meyer, Gitte; Lund, Anker Brink

2016-01-01

Hvad er civilsamfundet? Anker Brink Lund og Gitte Meyer fra CBS Center for Civil Society Studies gennemgår civilsamfundet bogstav for bogstav. Vi er nået til R for Regulering.......Hvad er civilsamfundet? Anker Brink Lund og Gitte Meyer fra CBS Center for Civil Society Studies gennemgår civilsamfundet bogstav for bogstav. Vi er nået til R for Regulering....

ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN THE R AND P REACTOR VESSELS

Energy Technology Data Exchange (ETDEWEB)

Wiersma, B.

2010-05-24

The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D and D). D and D activities consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS and T) of the Savannah River National Laboratory (SRNL) has been requested to review and evaluate existing experimental and analytical studies of this issue to determine if any process constraints on the chemistry of the fill material and the fill operation are necessary. Various options exist for the type of grout material that may be used for D and D of the reactor vessels. The grout formulation options include ceramicrete (pH 6-8), low pH portland cement + silica fume grout (pH 10.4), or Portland cement groupt (pH 12.5). The assessment concluded that either ceramicrete or the silica fume grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters does not provide a margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. It is recommended that this grout not be utilized for this task. The R-reactor vessel cotnains significantly less aluminum based on current facility process knowledge, surface observations, and drawings. Therefore, a Portland cement grout may be considered for grouting operations as well as the other grout formulations. For example, if the grout fill rate is less than 1 inch/min and the grout temperature is maintained at 70 C or less, the risk of hydrogen accumulation during fill

Characterizing the role of endothelin-1 in the progression of cardiac hypertrophy in aryl hydrocarbon receptor (AhR) null mice

International Nuclear Information System (INIS)

Lund, Amie K.; Goens, M. Beth; Nunez, Bethany A.; Walker, Mary K.

2006-01-01

The aryl hydrocarbon receptor (AhR) is a ligand-activated transcription factor characterized to play a role in detection and adaptation to environmental stimuli. Genetic deletion of AhR results in hypertension, and cardiac hypertrophy and fibrosis, associated with elevated plasma angiotensin II (Ang II) and endothelin-1 (ET-1), thus AhR appears to contribute to cardiovascular homeostasis. In these studies, we tested the hypothesis that ET-1 mediates cardiovascular pathology in AhR null mice via ET A receptor activation. First, we determine the time courses of cardiac hypertrophy, and of plasma and tissue ET-1 expression in AhR wildtype and null mice. AhR null mice exhibited increases in heart-to-body weight ratio and age-related expression of cardiac hypertrophy markers, β-myosin heavy chain (β-MHC), and atrial natriuretic factor (ANF), which were significant at 2 months. Similarly, plasma and tissue ET-1 expression was significantly elevated at 2 months and increased further with age. Second, AhR null mice were treated with ET A receptor antagonist, BQ-123 (100 nmol/kg/day), for 7, 28, or 58 days and blood pressure, cardiac fibrosis, and cardiac hypertrophy assessed, respectively. BQ-123 for 7 days significantly reduced mean arterial pressure in conscious, catheterized mice. BQ-123 for 28 days significantly reduced the histological appearance of cardiac fibrosis. Treatment for 58 days significantly reduced cardiac mass, assessed by heart weight, echocardiography, and β-MHC and ANF expression; and reduced cardiac fibrosis as determined by osteopontin and collagen I mRNA expression. These findings establish ET-1 and the ET A receptor as primary determinants of hypertension and cardiac pathology in AhR null mice

Development of a computational program to planning and control of the IEA-R1 reactor maintenance

International Nuclear Information System (INIS)

Martins, Mauro Onofre; Madi Filho, Tufic

2013-01-01

Maintenance is an essential activity in nuclear reactors. The components of safety systems of an industrial plant should have a low probability of failure, especially if there is a high risk of accidents that may cause environmental damage. In nuclear facilities, the presence of security systems is a technical specification and a requirement for their license and operation. In order to manage the entire information flow from the maintenance of the IEA-R1, a computational program (software) was developed, which not only plans and control all the maintenance, but also updates the documents and records to safeguard the quality, ensuring the safe operation of the reactor. The software has access levels and provides detailed reports of all maintenance planned and implemented, together with an individual history of the equipment during its lifetime in the facility. This work presents all the stages of the software development, description, compatibility, application, advantages and results obtained experimentally. (author)

Fonctionnalité, résilience, maintenance, acides gras insaturés Un exemple : l’acide linoléique et les récepteurs du LDL-cholestérol

Directory of Open Access Journals (Sweden)

Mendy François

2001-07-01

Full Text Available Fonctionnalité, résilience, maintenance, et acides gras poly-insaturés. Il deviendra impossible dans le futur de poser le problème des apports nutritionnels conseillés sans se poser la question : Conseillés dans quel but ? Comptable, humanitaire, épanouissement individuel ? Obtenir une croissance, une reproduction, un gain de masse musculaire dans le plus court temps sont des objectifs de nutritionnistes zoo-techniciens. Dans ce système, l’objectif final est la mort programmée dans un abattoir dans le délai le plus court et le plus rentable possible. En nutrition humaine, l’objectif est d’obtenir la meilleure adaptabilité possible dans n’importe quelle situation et le plus longtemps possible. L’objectif n’est plus comme à la fin du xviiie et xixe siècle, d’obtenir une main-d’oeuvre pouvant se développer et se reproduire le plus rapidement possible, assurer un travail physique efficace au moindre coût. Peut-être est-il la transmission des connaissances anciennes, l’acquisition et la transmission de connaissances nouvelles, durant le plus lontemps possible. Pour l’homme, la définition des apports nutritionnels conseillés devrait être la définition des marges de sécurités entre les apports minimaux acceptables et les apports maximaux tolérables. Ces marges de sécurité devraient permettre d’obtenir une fonctionnalité réelle, soit la meilleure conformation récepteurs-enzymes, malgré des status génétiques variés (mutations, polymorphisme, etc., un environnement aléatoire, d’obtenir la résislience, l’adaptabilité individuelle, maximale, durant le plus longtemps possible (maintenance. Il n’existe pas d’autres possibilités de prévention des maladies conformationnelles nouvellement décrites. À titre d’exemple, les conditions d’obtention du niveau de régulation optimale du récepteur LDL, la dégradation sécrétoire de l’ApoB par le récepteur LDL sur le chemin de la s

Shadow corrosion testing in the INCA facility in the Studsvik R2 reactor

International Nuclear Information System (INIS)

Nystrand, A.C.; Lassing, A.

1999-01-01

Shadow corrosion is a phenomenon which occurs when zirconium alloys are in contact with or in proximity to other metallic objects in a boiling water reactor environment (BWR, RBMK, SGHWR etc.). An enhanced corrosion occurs on the zirconium alloy with the appearance of a 'shadow' of the metallic object. The magnitude of the shadow corrosion can be significant, and is potentially limiting for the lifetime of certain zirconium alloy components in BWRs and other reactors with a similar water chemistry. In order to evaluate the suitability of the In-Core Autoclave (INCA) in the Studsvik R2 materials testing reactor as an experimental facility for studying shadow corrosion, a demonstration test has been performed. A number of test specimens consisting of Zircaloy-2 tubing in contact with Inconel were exposed in an oxidising water chemistry. Some of the specimens were placed within the reactor core and some above the core. The conclusion of this experiment after post irradiation examination is that it is possible to use the INCA facility in the Studsvik R2 reactor to develop a significant level of shadow corrosion after only 800 hours of irradiation. (author)

Distinct human and mouse membrane trafficking systems for sweet taste receptors T1r2 and T1r3.

Science.gov (United States)

Shimizu, Madoka; Goto, Masao; Kawai, Takayuki; Yamashita, Atsuko; Kusakabe, Yuko

2014-01-01

The sweet taste receptors T1r2 and T1r3 are included in the T1r taste receptor family that belongs to class C of the G protein-coupled receptors. Heterodimerization of T1r2 and T1r3 is required for the perception of sweet substances, but little is known about the mechanisms underlying this heterodimerization, including membrane trafficking. We developed tagged mouse T1r2 and T1r3, and human T1R2 and T1R3 and evaluated membrane trafficking in human embryonic kidney 293 (HEK293) cells. We found that human T1R3 surface expression was only observed when human T1R3 was coexpressed with human T1R2, whereas mouse T1r3 was expressed without mouse T1r2 expression. A domain-swapped chimera and truncated human T1R3 mutant showed that the Venus flytrap module and cysteine-rich domain (CRD) of human T1R3 contain a region related to the inhibition of human T1R3 membrane trafficking and coordinated regulation of human T1R3 membrane trafficking. We also found that the Venus flytrap module of both human T1R2 and T1R3 are needed for membrane trafficking, suggesting that the coexpression of human T1R2 and T1R3 is required for this event. These results suggest that the Venus flytrap module and CRD receive taste substances and play roles in membrane trafficking of human T1R2 and T1R3. These features are different from those of mouse receptors, indicating that human T1R2 and T1R3 are likely to have a novel membrane trafficking system.

77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

Science.gov (United States)

2012-11-15

... Research Institute TRIGA Reactor: Facility Operating License No. R-84 AGENCY: Nuclear Regulatory Commission... considering an application for the renewal of Facility Operating License No. R-84 (Application), which... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to operate...

R2/R0-WTR decommissioning cost. Comparison and benchmarking analysis

International Nuclear Information System (INIS)

Varley, Geoff; Rusch, Chris

2001-10-01

of plant layout for proper scheduling of activities and form a robust basis for a D and D plan. The loss of expert knowledge between the time of plant shutdown and the beginning of D and D activities can be an obstacle to D and D efficiency. The WTR was shutdown for over 30 years between final shutdown and the beginning of D and D work. The obstacles can be reduced if: Plant drawings and records are updated during the operational phase of plant life so that such documents accurately reflect the condition of the plant at the time of final shutdown. In the case of WTR, drawings and records were segregated at the time of shutdown according to those records needed for D and D and those records that would not be needed. Unfortunately, plant staff confused the two groups of records and the records needed for D and D were discarded. If the reactor is associated with a large organization, a search of the organization for those with knowledge should be performed. The WTR D and D representatives indicated that if the records are up to date and of good quality, the need for personnel knowledge is diminished. Given the difference in labour rates between R2 and WTR, the work for an equivalent task at R2 would have to be performed about 30 to 40 percent more efficiently in order for the labour cost of the task to equal the WTR labour cost. The overall projected cost of the R2 D and D is MSEK 190.93 (2000 money values) compared to the WTR actual figure of MSEK 274.653 (1 USD approx. 10 SEK). The overall scale and composition of R2 is very similar to WTR, albeit with a smaller and lighter reactor vessel. With the major difference in labour rates, it is therefore somewhat surprising to find that the R2 estimate is approximately 30 per cent lower than the WTR actual cost. The adjusted project management WTR costs are just slightly more than the estimated project management costs for R2, whilst transport and disposal costs for WTR tend to be lower than for R2. Focus therefore turns to

Nondestructive inspection of the tubes of TRIGA IPR-R1 reactor heat exchanger by eddy current testing

International Nuclear Information System (INIS)

Silva Junior, Silverio F.; Silva, Roger F.; Oliveira, Paulo F.; Barreto, Erika S.; Ribeiro, Isabela G.; Fraiz, Felipe C.

2013-01-01

The IPR-R1 TRIGA MARK 1 reactor is an open pool type reactor, cooled light water. It is used for research activities, personnel training and radioisotopes production, in operation since 1960 at the Nuclear Technology Development Center - CDTN/CNEN. It operates at a maximum thermal power of 100 kW and usually, the fuel cooling is done by natural circulation. If necessary, an external auxiliary cooling system, with a shell-and-tube type heat exchanger, can be used to improve the water heat removal. As part of the ageing management program of the reactor, a nondestructive evaluation of their heat exchanger stainless steel tubes will be performed, in order to verify its integrity. The examinations will be performed using the eddy current test method, which allows the detection and characterization of structural discontinuities in the wall of the tubes, if existing. For this purpose, probes and reference standards were designed and manufactured at CDTN facilities and test procedures were established and validated. In this paper, a description of the proposed infrastructure as well as the test methodology to be used in the examinations are presented and discussed. (author)

Compétence artistique, réception et démocratisation

OpenAIRE

Coavoux, Samuel

2014-01-01

Cet article soutient que nulle approche de la démocratisation artistique n’est possible sans une théorie de la réception, dans la mesure où les inégalités culturelles sont présentes autant dans les modalités du rapport à l’œuvre que dans la fréquence de la participation culturelle. Cependant, dans la mesure où elles privilégient l’interprétation et ignorent les effets de légitimité, les approches traditionnelles de la réception s’avèrent d’une efficacité limitée pour penser la démocratisation...

Magnétochiralité et résonances stochastiques dans les lasers

Science.gov (United States)

Bonnet, C.; Bretenaker, F.; Brunel, M.; Chauvat, D.; Emile, O.; Lai, N. D.; Le Floch, A.; Ropars, G.; Ruchon, T.; Singh, K.; Thépot, J.-Y.; Vallet, M.

2002-06-01

Les états propres d'un laser constituent un outil de choix pour étudier les différents rôles joués par le bruit dans un système. D'une part, si on veut isoler un effet petit difficilement accessible par les méthodes classiques, ces états propres permettent de réaliser des mesures différentielles de haute précision, à condition de pouvoir éliminer les bruits mécaniques, optiques, électroniques. A titre d'exemple, nous avons utilisé les états propageant et contrapropageant d'un laser ionique en anneau pour mesurer une interaction fondamentale faible: la biréfringence magnétochirale. Cette "biréfringence" se manifeste en effet par une petite variation d'indice selon le sens de parcours de l'anneau, de l'ordre de Δ n.10^{-11}, indépendante de la polarisation. A l'opposé, les deux états propres d'un laser du type Fabry-Perot constituent un système idéal pour explorer les résonances stochastiques à deux dimensions. Les résonances stochastiques par inhibition et par rotation sont isolées en présence de bruits blancs gaussiens tant pour les bruits optiques que magnétiques. L'utilisation possible de l'émission spontanée comme bruit actif est démontrée.

(1R,2R,3R,4R,5S-2,3-Bis[(2S′-2-acetoxy-2-phenylacetoxy]-4-azido-1-[(2,4-dinitrophenylhydrazonomethyl]bicyclo[3.1.0]hexane

Directory of Open Access Journals (Sweden)

Robert McDonald

2008-02-01

Full Text Available In the title compound, C38H29N7O12, the five-membered ring adopts an envelope conformation in which the `flap' is cis to the cyclopropane group. This conformation is similar to those of other bicyclo[3.1.0]hexane analogues for which crystal structures have been reported. The absolute configuration of the stereogenic centers on the cyclopentane ring, as determined by comparison with the known configurations of the stereogenic centers in the (2S-2-acetoxy-2-phenylacetoxy groups, is 1(R, 2(R, 3(R, 4(R and 5(S. An intramolecular N—H...O hydrogen bond is present.

Effets de vieillissement accéléré sur la germination et l ...

African Journals Online (AJOL)

de la performance des graines ou lots de graines pendant la ... conditions extrêmes et ensuite mesurer le taux de germination, un test ..... l'étude, la conservation et la gestion ex situ du matériel végétal. ... Controle de la qualité des céréales et.

Les destins divergents des régionalismes flamands et francophones : une perspective historique

Directory of Open Access Journals (Sweden)

Geoffrey Pion

2011-04-01

Full Text Available Les tensions entre francophones et néerlandophones tournant autour d'une régionalisation de compétences fédérales ne sont pas nouvelles et s'inscrivent dans un lent processus de poussée régionaliste émanant aussi bien du sud que du nord du pays depuis près d'un siècle. Nous reviendrons dans cet article sur l'histoire politique et électorale du régionalisme en Belgique. Nous montrerons comment des poussées régionalistes régulières ont transformé l’État belge unitaire en un État décentralisé dans lequel le fédéral a perdu peu à peu ses prérogatives. L’hypothèse principale qui sous-tend cet article est que les partis régionalistes ont connu des succès électoraux temporaires (1919-21, 1936, 1965-77, 2009- ?, suivis de déclins dès que les revendications régionalistes des opinions étaient satisfaites. La vague suivante repose alors sur un approfondissement des revendications régionalistes. Dans ce cadre, nous insisterons en particulier sur le soutien croissant des partis régionalistes au nord du pays contrastant avec l'absence de parti régionaliste wallon depuis le milieu des années 1980. Nous montrons enfin que les vagues régionalistes successives reposent sur des géographies à chaque fois renouvelées, à l’exception notable du rôle d’Anvers au sein du mouvement flamand.The tensions between French-speaking and Dutch-speaking communities in Belgium about the regionalization of federal competences are not new and have to be understood in the long history of regionalism. This article tells the history and the geography of regional waves in Belgium. We will in particular show how these successive regionalist fevers have progressively reshaped the Belgian Central State into a federal State where regions gain in competences over the time. The main hypothesis is that regionalist parties have gone through temporary electoral successes (1919-21, 1936, 1965-77, 2009-?, followed by long period of decline as

Les facies gypso-salins dans la région d'Oran et leurs ...

African Journals Online (AJOL)

SARAH

31 août 2016 ... (Gaucher et al, 1974); de plus, à la transgression de l'Oligocène, a succédé une régression importante qui a duré plus de 5 millions d'années (Dercourt et al, 1995) favorable à des mécanismes de croissance cristallines et de litifaction, propices à la stratification des sels; par la suite, les mouvements ...

Les facies gypso-salins dans la région d'Oran et leurs ...

African Journals Online (AJOL)

Conclusion et application des résultats: La salinité associée à l'érosion (hydrique et éolienne du fait de l'absence de végétation) au fil du temps, a non seulement affecté les terres et les nappes, mais a contribué à la mise en place d'un synclinal ou sebkha en raison de la subsidence suite aux apports continuels de ...

Introduction. Théâtre et révolutions

OpenAIRE

Bourdin, Philippe

2012-01-01

La réflexion his­­to­­rique, esthé­­tique, musicologique, théo­­rique et cri­­tique sur le théâtre de la Révo­­lu­­tion fran­­çaise a connu depuis le Bicen­­te­­naire une efflo­­res­­cence notoire. Plu­­ri­­dis­­cip­­li­­naire, asso­­ciant his­­to­­riens, his­­to­­riens de l’art, musi­­co­­logues et lit­­té­­raires, cette recherche a jeté ces der­­nières années des ponts solides de part et d’autre de l’Atlan­­tique, et déborde actuel­­le­­ment des fron­­tières fran­­çaises pour trou­­ver écho...

Spin reorientation phenomena in (R{sub 1-x}R`{sub x}){sub 2}Co{sub 14}B (R = La, R` = Dy and Ho)

Energy Technology Data Exchange (ETDEWEB)

Myojin, T. [Takamatsu Nat. Coll. of Technol. (Japan); Ohno, T. [Tokushima Univ. (Japan). Faculty of Engineering; Mizuno, K. [Tokushima Univ. (Japan). Faculty of Integrated Arts and Sciences; Tsujimura, A. [Faculty of Engineering, Tokushima Bunri Univ., Kagawa Shido (Japan); Kojima, K. [Hiroshima Univ. (Japan). Faculty of Integrated Arts and Sciences

1997-07-01

The variations of magnetization with temperature in (La{sub 1-x}R`{sub x}){sub 2}Co{sub 14}B (R` = Dy and Ho) have been measured to determine spin reorientation temperature T{sub SR} of these compounds. The phase diagrams of spin arrangement thus obtained indicate monotonous increase in T{sub SR} with R` concentration x. Also, T{sub SR}`s of R{sub 2}Co{sub 14}B(R = Tb, Dy and Ho) are found to vary linearly with the Stevens factor {alpha} of R. (orig.). 4 refs.

Normalisation et réglementation des matériaux recyclés

OpenAIRE

Turtschy, J.-C.; Kellenberger, M.

2004-01-01

La volonté politique qui va dans le sens du développement durable et de la protection de l'environnement s'est concrétisée au travers des lois dès 1983. Il aura fallu presque 20 ans pour que ces principes soient appliqués globalement jusqu’au niveau cantonal; deux décennies pour passer d'une idée théorique aux applications réelles dans le domaine de la construction. Cependant, au vu des nombreuses lois, ordonnances, prescriptions, directives, règlements, normes, cas pa...

Consolidation du réseautage dans les domaines de la recherche et ...

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

L'UbuntuNet Alliance for Research and Education Networking a été créée en 2005 pour traiter ces questions et dans le but de stimuler la création de réseaux nationaux de recherche et d'éducation (RNRE) en Afrique. Les RNRE sont une forme de collaboration à l'échelle nationale favorisée par des connexions Internet à ...

Le(s Sud en quête du Sud. Une construction entre stéréotype et réalité.

Directory of Open Access Journals (Sweden)

Mabel Franzone

2010-11-01

Full Text Available Nous pouvons faire de multiples lectures du/ des Sud (s, tant de ses propres représentations que des figurations prêtées par le Nord, comme de ses créations, de ses réactions, de sa quête incessante d’identité. Ce sont des lectures multiples obéissant à de multiples situations, qui font appel à des croisements inaliénables entre divers peuples et ethnies, à diverses disciplines, et suscitent des sentiments mélangés, pouvant aller du rejet à l’attraction presque magnétique qu’exerce chacun des deux des hémisphères l’un sur l’autre. Notre intention première était de réunir divers points de vue liés aux problématiques actuelles du Sud (s, liées à l’imaginaire.

Neutronic, thermal-hydraulics and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor

Energy Technology Data Exchange (ETDEWEB)

Domingos, Douglas Borges; Silva, Antonio Teixeira e; Umbehaun, Pedro Ernesto; Silva, Jose Eduardo Rosa da; Conti, Thadeu das Neves; Yamaguchi, Mitsuo [Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), Sao Paulo, SP (Brazil)], e-mail: douglasborgesdomingos@yahoo.com.br

2009-07-01

Neutronic, thermal-hydraulics and accident analysis calculations were developed to estimate the safety of an irradiation device placed in the IEA-R1 reactor core. The irradiation device will be used to receive miniplates of U{sub 3}O{sub 8}-Al e U{sub 3}Si{sub 2}-Al dispersion fuels, LEU type (19.9% of {sup 235}U), with uranium densities of, respectively, 3.0 gU/cm{sup 3} and 4.8gU/cm{sup 3}. The fuel miniplates will be irradiated to nominal {sup 235}U burnup levels of 50% and 80%, in order to qualify the above high-density dispersion fuels to be used in the Brazilian Multipurpose Reactor, now in the conception phase. For the neutronic calculation, the computer code CITATION was utilized. The computer code FLOW was used to calculate the coolant flow rate in the irradiation device, allowing the determination of the fuel miniplate temperatures with the computer model MTRCR-IEA-R1. A postulated Loss of Coolant Accident (LOCA) was analyzed with the computer codes LOSS and TEMPLOCA, allowing the calculation of the fuel miniplate temperatures after the reactor pool draining. The calculations showed that the irradiation of the fuel miniplates will happen without any adverse consequence in the IEA-R1 reactor. (author)

Studies review and exploration purpose of neutron radiography technique in the TRIGA IPR-R1 reactor at CDTN, Brazil

International Nuclear Information System (INIS)

Costa, Antonella Lombardi; Amorim, Valter Alves de; Stasiulevicius, Roberto; Rocha, Zildete

2002-01-01

Neutron Radiography - NR - consists of obtaining on a sensitive plate, the image produced by neutron flux after crossing an object. Through NR is possible to inspect plastics and explosives materials and organic composition. Is difficult to analyze these materials by the radiography technique. The neutron beam extractor was installed, in the TRIGA IPR-R1 reactor at the CDTN. This work presents preliminaries results of the NR researches in the past at CDTN, which are being retaken. (author)

Justice, réforme du secteur de la sécurité et meilleure gouvernance ...

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

GSJ) du CRDI, où je me concentre sur la région MOAN et sur des projets qui contribuent aux processus de réforme à la lumière des soulèvements sociopolitiques dans le monde arabe. Ma stratégie repose sur la justice ...

The combinatorial PP1-binding consensus Motif (R/Kx( (0,1V/IxFxx(R/Kx(R/K is a new apoptotic signature.

Directory of Open Access Journals (Sweden)

Angélique N Godet

Full Text Available BACKGROUND: Previous studies established that PP1 is a target for Bcl-2 proteins and an important regulator of apoptosis. The two distinct functional PP1 consensus docking motifs, R/Kx((0,1V/IxF and FxxR/KxR/K, involved in PP1 binding and cell death were previously characterized in the BH1 and BH3 domains of some Bcl-2 proteins. PRINCIPAL FINDINGS: In this study, we demonstrate that DPT-AIF(1, a peptide containing the AIF(562-571 sequence located in a c-terminal domain of AIF, is a new PP1 interacting and cell penetrating molecule. We also showed that DPT-AIF(1 provoked apoptosis in several human cell lines. Furthermore, DPT-APAF(1 a bi-partite cell penetrating peptide containing APAF-1(122-131, a non penetrating sequence from APAF-1 protein, linked to our previously described DPT-sh1 peptide shuttle, is also a PP1-interacting death molecule. Both AIF(562-571 and APAF-1(122-131 sequences contain a common R/Kx((0,1V/IxFxxR/KxR/K motif, shared by several proteins involved in control of cell survival pathways. This motif combines the two distinct PP1c consensus docking motifs initially identified in some Bcl-2 proteins. Interestingly DPT-AIF(2 and DPT-APAF(2 that carry a F to A mutation within this combinatorial motif, no longer exhibited any PP1c binding or apoptotic effects. Moreover the F to A mutation in DPT-AIF(2 also suppressed cell penetration. CONCLUSION: These results indicate that the combinatorial PP1c docking motif R/Kx((0,1V/IxFxxR/KxR/K, deduced from AIF(562-571 and APAF-1(122-131 sequences, is a new PP1c-dependent Apoptotic Signature. This motif is also a new tool for drug design that could be used to characterize potential anti-tumour molecules.

Glutamate Receptors GluR1 and GluR4 in the Hamster Superior Colliculus: Distribution and Co-localization with Calcium-Binding Proteins and GABA

International Nuclear Information System (INIS)

Choi, Jae-Sik; Lee, Jea-Young; Jeon, Chang-Jin

2009-01-01

We investigated the distributions of AMPA glutamate receptor subtypes GluR1 and GluR4 in the hamster superior colliculus (SC) with antibody immunocytochemistry and the effect of enucleation on these distributions. We compared these labelings to those of GluR2/3 in our previous report (Park et al., 2004, Neurosci Res., 49:139–155) and calcium-binding proteins calbindin D28K, calretinin, parvalbumin, and GABA. Anti-GluR1-immunoreactive (IR) cells were scattered throughout the SC. By contrast, anti-GluR4-IR cells formed distinct clusters within the lower lateral stratum griseum intermediale (SGI) and lateral stratum album intermediale (SAI). The GluR1- and GluR4-IR neurons varied in size and morphology. The average diameter of the GluR1-IR cells was 13.00 µm, while the GluR4-IR cells was 20.00 µm. The large majority of IR neurons were round or oval cells, but they also included stellate, vertical fusiform and horizontal cells. Monocular enucleation appeared to have no effect on the GluR1 and GluR4 immunoreactivity. Some GluR1-IR cells expressed calbindin D28K (9.50%), calretinin (6.59%), parvalbumin (2.53%), and GABA (20.54%). By contrast, no GluR4-IR cells expressed calcium-binding proteins or GABA. Although the function of the AMPA receptor subunits in SC is not yet clear, the distinct segregation of the GluR subunits, its differential colocalization with calcium-binding proteins and GABA, and differential responses to enucleation suggest the functional diversity of the receptor subunits in visuo-motor integration in the SC

Lieu de résidence réel et lieu de résidence idéal : une approche fondée sur la théorie de la décision

Directory of Open Access Journals (Sweden)

Anne-Marie Meyer

2007-07-01

Full Text Available Cette recherche examine la capacité d'une théorie de la décision à estimer le lieu de résidence réel des personnes. Son objectif est double : d'une part, proposer une méthode pour tester empiriquement la théorie de la Subjective Expected Utility appliquée au choix résidentiel, et d'autre part, mettre en évidence les différences dans l'évaluation des quartiers d'une ville liées à l'existence de groupes de population définis par leurs statuts familial et social. Grâce à une enquête, la validité de cette théorie de la décision peut être en partie confirmée, mais sa mise en pratique pose également un ensemble de difficultés, liées notamment à l'acquisition de l'information.

Upregulation of miR-150* and miR-630 induces apoptosis in pancreatic cancer cells by targeting IGF-1R.

Directory of Open Access Journals (Sweden)

Lulu Farhana

Full Text Available MicroRNAs have been implicated in many critical cellular processes including apoptosis. We have previously found that apoptosis in pancreatic cancer cells was induced by adamantyl retinoid-related (ARR molecule 3-Cl-AHPC. Here we report that 3-Cl-AHPC-dependent apoptosis involves regulating a number of microRNAs including miR-150* and miR-630. 3-Cl-AHPC stimulated miR-150* expression and caused decreased expression of c-Myb and IGF-1R in the pancreatic cancer cells. 3-Cl-AHPC-mediated reduction of c-Myb resulted in diminished binding of c-Myb with IGF-1R and Bcl-2 promoters, thereby causing repression of their transcription and protein expression. Over-expression of miR-150* also resulted in diminished levels of c-Myb and Bcl-2 proteins. Furthermore, the addition of the miRNA inhibitor 2'-O-methylated miR-150 blocked 3-Cl-AHPC-mediated increase in miR-150* levels and abrogated loss of c-Myb protein. Knockdown of c-Myb in PANC-1 cells resulted in enhanced apoptosis both in the presence or absence of 3-Cl-AHPC confirming the anti-apoptotic property of c-Myb. Overexpression of miR-630 also induced apoptosis in the pancreatic cancer cells and inhibited target protein IGF-1R mRNA and protein expression. Together these results implicate key roles for miR-150* and miR-630 and their targeting of IGF-1R to promote apoptosis in pancreatic cancer cells.

Synthèse des résultats de l'enquête Récoltes et flux de graines - Campagne 2009-2010

OpenAIRE

Brochet, A.; Bilger, I.

2011-01-01

/ Cette note de synthèse présente les résultats de l'enquête statistique annuelle sur les récoltes et flux de graines forestières pour la campagne 2009-2010. Cette campagne a été marquée par des récoltes relativement importantes pour les essences feuillues, avec augmentation de plus de 300% par rapport aux mauvaises récoltes de la campagne précédentes et des récoltes faibles pour les essences résineuses, avec une diminution de 75%. Cette diminution des résineux est à mettre en relation avec ...

Favoriser l'élaboration de politiques et de règlements fondés sur des ...

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

Favoriser l'élaboration de politiques et de règlements fondés sur des données probantes pour accroître l'utilisation des TIC (LIRNEasia - phase II). De grandes avancées ont permis de réduire le fossé numérique en Asie-Pacifique, et cela est surtout attribuable à l'essor de la téléphonie mobile. Près d'un milliard de ...

Angiomyolipome rénal bilatéral et hémorragique: A propos d\\'un cas ...

African Journals Online (AJOL)

Un mois après, devant la récidive d\\'une hématurie massive avec état de choc hémorragique clinique et biologique, une néphrectomie droite d\\'hémostase était réalisée. L\\'évolution a été favorable et le recul actuel est de 24 mois. Keywords: Angiomyolipome, sclérose tubéreuse de Bourneville, embolisation artérielle ...

Conflits et résistances de la gentrification de Harlem

Directory of Open Access Journals (Sweden)

Charlotte Recoquillon

2011-12-01

Full Text Available Longtemps symbole de la ségrégation des Noirs américains et de la ghettoïsation de leurs quartiers, Harlem connaît une renaissance depuis le début des années 1980. Les enjeux qui entourent la gentrification de ce quartier sont immenses tant sa portée symbolique est grande. C’est pourquoi la thèse dont sont extraites les images ci-dessous s’attache à démontrer que la gentrification de Harlem est le résultat de politiques publiques volontaristes et d’investissements massifs orientés vers des partenaires…

Culture du résultat et pilotage par les indicateurs dans le secteur public

OpenAIRE

Chatelain-Ponroy, Stéphanie; Sponem, Samuel

2008-01-01

Depuis 20 ans, la question de la gestion de l’État est au cœur des réformes de l’administration dans tous les pays de l’OCDE. À cet égard, l’introduction d’une culture du résultat et des dispositifs de contrôle de gestion qui l’accompagnent dans l’administration publique telle qu’elle est mise en avant dans la LOLF, si elle peut avoir des effets positifs en termes d’évaluation des politiques publiques et d’incitation des agents, peut aussi engendrer des effets pervers. En la matière, l’expéri...

Copernic et la révolution héliocentrique aux sources de l'astrophysique contemporaine

CERN Document Server

Mettra, Mélanie

2015-01-01

Découvrez enfin tout ce qu'il faut savoir sur Copernic et la révolution héliocentrique en moins d'une heure ! On ne parle pas sans raison de révolution copernicienne. Multipliant les calculs et les observations, Copernic parvient à formuler une théorie qui va changer à jamais l'avenir de la science : c'est bien le Soleil, et non la Terre, qui est au centre de l'univers. Ses hypothèses sont à la source d'une cascade de découvertes qui fondent l'astrophysique contemporaine. Ce livre vous permettra d'en savoir plus sur : La vie de Copernic Le contexte de l'époqu

Development of an artificial neural network for nuclear power monitoring and fault detection in the IEA-R1 research reactor at IPEN

International Nuclear Information System (INIS)

Bueno, Elaine Inacio; Ting, Daniel Kao Sun; Goncalves, Iraci M.P.

2005-01-01

The purpose of this paper is to develop a system to monitor the nuclear power of a reactor using Artificial Neural Networks. The database used in this work was developed using a theoretical model of IEA-R1 Research Reactor. The IEA-R1 is a pool type reactor of 5 MW, cooled and moderated by light water, and uses graphite and beryllium as reflector. To monitor the nuclear power the following variables were chosen: T3 . temperature above the reactor core, T4 . outlet core temperature, FE01 . primary loop flow rate and the nuclear power. The inputs are T3, T4 and FE01 and the output is the nuclear power. It was used several networks using the backpropagation algorithm. The conclusion is that the multiplayer perceptrons networks (MLPs), training by the backpropagation algorithm, can be used to solve this problem. The results obtained with the MLPs networks are satisfactory and the mean square error was in the order of 10 -4 during the network training and in the order of 10 -2 during the network testing. We intend to monitor the other variables of this model using the same methodology, and after this we will use the real database from the system to compare the results obtained with the model. The monitoring of the reactor variables is part of the development of a fault detection and isolation system which is underway and which is, by its turn, part of a comprehensive ageing management program. (author)

LA COMMUNICATION SANTE : NOUVEL ENJEU DE LA CONSOMMATION ALIMENTAIRE Contexte réglementaire et statut juridique des aliments santé

Directory of Open Access Journals (Sweden)

Coutrelis Nicole

2001-07-01

Full Text Available À la frontière de l’aliment et du médicament, les « aliments santé » sont aujourd’hui au centre de toutes les attentions - et de toutes les interrogations - du secteur de l’agroalimentaire. La notion n’étant pas définie par la loi et le vocabulaire utilisé variant d’un ouvrage ou d’un auteur à l’autre, la matière est difficilement et diversement appréhendée par les professionnels et les consommateurs. Aussi, afin d’assurer à la présente étude la cohérence nécessaire à la compréhension du sujet, lui-même fort complexe, on privilégiera une définition large (et nécessairement subjective de la notion d’aliments santé 1. Dès lors, celle-ci recouvrira : - les aliments traditionnels comportant des allégations faisant un lien, quel qu’il soit, avec la santé ; - les aliments dits « fonctionnels » ; - les aliments traditionnels supplémentés; - l’alimentation particulière; - les compléments alimentaires. Tels que définis, les aliments santé sont soumis à un régime juridique au centre d’un prisme composé de nombreuses réglementations, communautaires et françaises, relatives aux denrées alimentaires et aux médicaments. La multiplicité de ces réglementations ne va pas sans difficulté, leur mise en oeuvre manquant parfois de la cohérence qui serait nécessaire à la sécurité juridique. Essentiellement centrée sur l’information et la protection du consommateur, la réglementation actuellement applicable en France est à la fois générale et spécifique. Générale en ce sens que les règles relatives à la sécurité des produits 2, l’étiquetage et la présentation 3, et en matière de responsabilité civile 4 sont applicables aux aliments santé comme à tout autre produit. Spécifique dans la mesure où des textes plus précis concernent plus directement et/ou exclusivement les aliments santé. En synthétisant à l’extrême les règles applicables à la matière, l�

Angiomyolipome rénal agressif avec extension à la veine rénale: à ...

African Journals Online (AJOL)

Exceptionnellement la tumeur peut avoir un caractère agressive avec extension locorégionale et veineuse (la veine rénale et la veine cave inferieure). Nous présentons une observation d'une patiente âgée de 37 ans présentant un Angiomyolipome rénal volumineux avec extension à la veine rénale. Mots clés: Rein ...

Les réminiscences spartiates dans les discours et la politique de Robespierre de 1789 à Thermidor

OpenAIRE

Rosso, Maxime

2010-01-01

La Grèce antique est une des sources les plus riches de la pensée politique occidentale. Les réflexions de ses philosophes et les institutions de ses cités ont servi de modèles et appuyé les constructions intellectuelles, depuis la fin de cet ancien monde jusqu’au XXe siècle, où, il est vrai, la référence antique s’estompe un peu. Deux systèmes se détachent de l’ensemble et ont retenu l’attention de par leur importance historique et de par l’obstination des auteurs à opposer leurs lois et leu...

The past and the future in the forty years of the IPR-R1 TRIGA MARK I reactor operation

International Nuclear Information System (INIS)

Maretti Junior, Fausto

2008-01-01

Full text: The nuclear IPR-R1 TRIGA Mark I Reactor operating in the Nuclear Technology Development Center, originally Institute for Radioactive Research in Minas Gerais, Brazil, was dedicated in November 11, 1960. Initially operating for the production of radioisotopes for different uses, it started later to be used in large scale for neutron activation analysis and training of operators for nuclear power plants. Many improvements have been made throughout these years to provide a better performance in its operation and safety conditions. A new cooling system to operate until 300 kW, a new control rod mechanism, an aluminum tank for the reactor pool, an optimization in the pneumatic system, a new reactor control console and a general remodeling of the reactor laboratory were some of the improvements added. During these years a lot of irradiations, analysis , MSc and PhD thesis, training courses and isotopes production take place at the reactor. This paper describes the improvements made, the results obtained during the past 40 years, type of works realized, isotopes produced, the neutron activation analysis and the precautions taken to ensure future safe operation of the reactor to give operators better conditions of safe work. (authors)

Des bananes plus nutritives et qui résistent aux maladies | CRDI ...

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

28 oct. 2010 ... Les petits agriculteurs jouissent de meilleurs revenus et d'une sécurité alimentaire accrue grâce à des variétés de bananes à haut rendement qui résistent aux maladies. Au cours des années 1980 et 1990, avec le soutien du CRDI, la Fundación Hondureña de Investigación Agricola (FHIA) a mis au point ...

Monde « réel » et monde imaginaire. Le rôle de la bande son dans Eraserhead, de David Lynch

OpenAIRE

Bobée, Emmanuelle

2012-01-01

Par définition, un film de fiction dépeint un monde imaginaire dans lequel évoluent – le plus souvent – des personnages, que le spectateur feint de considérer comme des êtres de chair et de sang, en vertu de ce que l’on nomme le « pacte de fiction ». Au sein de ce monde imaginaire ou monde diégétique, comment le spectateur peut-il faire la distinction entre ce qui est « réel », du point de vue des personnages, et ce qui ne l’est pas ? En effet, contrairement à ce qui se produit dans la vie ré...

Rites thérapeutiques : réflexion sur le terrain et les archives

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Chantal Radimilahy

2008-08-01

Full Text Available Rites thérapeutiques : réflexion sur le terrain et les archives. En comparant la façon dont l’écrit sert à noter et à fixer des pratiques de guérissage, d’une part dans les archives de L. Vig et d’autre part dans les carnets d’un guérisseur malgache contemporain, l’auteur esquisse une réflexion sur la stabilité apparente des formes du langage et des pratiques rituelles dans un contexte social transformé.Therapeutic rituals: consideration on fieldwork and archives. By comparing the way in which writing is used to record and establish traditional healing practices, on the one hand in the archives of L. Vig and on the other, in the notes of a contemporary Madagascan traditional healer, the author outlines her reflections on the apparent stability of language forms and ritual practices in a transformed social context.

Yağı Azaltılmış Et Ürünleri Üretim Tekniği

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Meltem Serdaroğlu

2015-02-01

Full Text Available Son yıllarda tüketiciler diyetlerinde yağ ve kalori alımını sınırlamak amacıyla yağsız veya yağı azaltılmış gıdalara yönelmektedirler. Az yağlı et ürünlerinin üretiminde yağın azaltılması çeşitli teknolojik problemlere yol açarak ürünün kabul edilebilirliğini azaltmaktadır. Yağı azaltılan et ürünlerinde formülasyonda çeşitli katkıların kullanımı duyusal özelliklerin tüketici tercihi doğrultusunda iyileştirilmesini sağlamaktadır. Yapılan çalışmada et ürünlerinde yağın azaltılması ile ortaya çıkan problemler ve çeşitli katkıların kullanımı literatüre dayanılarak incelenmiştir.

Biodiesel : la réglementation européenne et le débat sur son évolution

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Dusser Philippe

2013-09-01

Full Text Available La réglementation communautaire sur les biocarburants a été mise en place à partir de 2003 pour répondre à un triple objectif : réduction des émissions de gaz à effet de serre, réduction de la dépendance énergétique, et soutien à la production agricole dans un contexte où 10 % des terres étaient obligatoirement gelées. Cette réglementation a été renforcée en 2009 dans le cadre du « paquet énergie » par l’introduction par la directive energie renouvelable d’un objectif obligatoire d’incorporation de 10 % d’énergie renouvelable dans les carburants à l’horizon 2020. Cette législation est complétée par une directive qualité des carburants qui impose une réduction de 6 % d’ici 2020 de l’empreinte carbone des carburants. La forte diésélisation du parc de véhicule en Europe a conduit à une rapide progression de la consommation de biodiesel (11 millions de tonnes dont 9 produites dans l’UE. L’huile de colza est la principale matière première du biodiesel. L’augmentation de la production de colza a permis de répondre à cette demande, tout en fournissant un coproduit protéique permettant de réduire significativement le déficit en protéines européen. Le débat sur l’impact du CASI (changement indirect d’affectation des sols des biocarburants, ainsi que celui sur l’équilibre alimentaire, a conduit la Commission européenne, 3 ans après avoir défini sa politique, à proposer de plafonner les carburants issus des cultures (1ere génération à 5 % et à introduire des « facteurs CASI » dans l’évaluation des effets de réduction des gaz à effets de serre. Cette proposition qui pourrait fortement remettre en cause le développement du biodiesel...et de la culture de colza fait à la date de rédaction de cet article (juillet 2013 l’objet de difficiles négociations à Bruxelles, dont l’issue est difficile à prédire.

Effects of lactose as an inducer on expression of Helicobacter pylori rUreB and rHpaA,and Escherichia colirLTKA63 and rLTB

Institute of Scientific and Technical Information of China (English)

Jie Yan; Shou-Feng Zhao; Ya-Fei Mao; Yi-Hui Luo

2004-01-01

AIM: To demonstrate the effect of lactose as an inducer on expression of the recombinant proteins encoded by Helicobacter pylori ureB and hpaA, and Escherichia coli LTB and LTKA63 genes and to determine the optimal expression parameters.METHODS: By using SDS-PAGE and BIO-RAD gel image analysis system, the outputs of the target recombinant proteins expressed by pET32a-ureB-E. coliBL21, pET32ahpaA-E. coliBL21, pET32a-L TKA63-E. coliBL21 and pET32aLTB-E.coliBL21 were measured when using lactose as inducer at different dosages, original bacterial concentrations,various inducing temperatures and times. The results of the target protein expression induced by lactose were compared to those by isopropyl-β-D-thiogalactoside (IPTG).The proteins were expressed in E.coli.RESULTS: Lactose showed higher efficiency of inducing the expression of rHpaA, rUreB, rLTB and rLTKA63 than IPTG. The expression outputs of the target recombinant proteins induced at 37 ℃ were remarkably higher than those at 28 ℃. Other optimal expression parameters for the original bacterial concentrations, dosages of lactose and inducing time were 0.8, 50 g/L and 4 h for rHpaA; 0.8, 100 g/L and 4 h for rLTKA63; 1.2, 100 g/Land 5 h for both rUreB and rLTB, respectively.CONCLUSION: Lactose, a sugar with non-toxicity and low cost, is able to induce the recombinant genes to express the target proteins with higher efficiency than IPTG. The results in this study establish a beneficial foundation for industrial production of H pylori genetic engineering vaccine.

Comparaison des politiques fiscales et réglementaires pour prévenir ...

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

... en sucre, les huiles de palme et les cigarettes ont donné des résultats décevants. ... Agent(e) responsable du CRDI ... Effect of tobacco control measures during a period of rising cardiovascular disease risk in India : a mathematical model of ...

Theoretical studies aiming at the IEA-R1 reactor core conversion from high U-235 enrichment to low U-235 enrichment

International Nuclear Information System (INIS)

Frajndlich, R.

1982-01-01

The research reactors, of which the fuel elements are of MTR type, functions presently, almost in their majority with high U-235 enrichment. The fear that those fuel elements might generate a considerabLe proliferation of nuclear weapons rendered almost mandatory the conversion of highly enriched fuel elements to a low U-235 enrichment. As the IEA-R1 reactor of IPEN is operating with highly enriched fuel elements a study aiming at this conversion was done. The problems related to the conversion and the results obtained, demonstrated the technical viabilty for its realization. (E.G.) [pt

Accident vasculaire cérébral hémorragique du tronc cérébral suite à une éclampsie du post partum: à propos d’un cas et revue de la littérature

OpenAIRE

Ennaqui, Khadija; Makayssi, Assia; Boufettal, Houssine; Samouh, Naima

2017-01-01

Les accidents vasculaires cérébraux sont des accidents rares mais graves durant la grossesse et le post-partum, ils sont responsable d'une mortalité et d'une morbidité élevée, la pré éclampsie, l'éclampsie et les accidents vasculaires cérébraux sont significativement liés. Le dysfonctionnement endothélial, l'altération de l'autorégulation cérébrale, et l'hypertension sévère sont, probablement, la cause de nombreux accidents vasculaires cérébraux chez la femme enceinte et durant la période du ...

La 'mutilation anthropologique' et le réalignement de la littérature ...

African Journals Online (AJOL)

28 mars 2016 ... pologique et blessure existentielle: traversées intergénéra-tionnelles de la littérature camerounaise”. Les sessions qui réunissaient entre autres Frieda Ekoto, Gilbert Doho,. Juliana (Makuchi) Nfah-Abbenyi, Célestin Monga, Ambroise Kom et Nathalie Etoke reflétaient ce que je détectais comme le mal-être ...

Fertilité des sols agricoles sous vigne et sous blé de la région de ...

African Journals Online (AJOL)

L'objectif de ce travail est l'évaluation agronomique de la qualité du sol sous vigne et sous blé dans la région Mohammedia-Benslimane au Maroc, à travers les indicateurs chimiques de la qualité du sol (pH, CE, CaCO3, Carbone organique total, Azote, Phosphore et Potassium). Les résultats de cette étude montrent que ...

Les réacteurs à membranes : possibilités d'application dans l'industrie pétrolière et pétrochimique Membrane Reactors: Possibilities of Application in the Petroleum and Petrochemical Industry

Directory of Open Access Journals (Sweden)

Guy C.

2006-11-01

Full Text Available Cet article fait le point sur l'état de la recherche dans le domaine des réacteurs chimiques avec séparation par membrane intégrée et de leur applications dans le domaine du raffinage et de la pétrochimie. Trois applications potentiellement intéressantes sont identifiées et, pour chacune, les avantages de l'utilisation d'un réacteur à membrane sont discutés. Ce sont : la déshydrogénation du propane en propylène, la déshydrogénation d'un naphtène cyclohexanique et le vaporéformage du gaz naturel. Pour ces réactions, les membranes à base de palladium apparaissent les plus performantes compte tenu de leur tenue en température, de leur sélectivité et de leur perméabilité à l'hydrogène. Quelques éléments relatifs à leur développement sont présentés en conclusion. Recently, the use of membrane in reaction engineering has been more and more advocated. The selective separation of the products from the reaction mixture allows to achieve higher conversion or better selectivity or to operate under less severe conditions or with smaller units. This paper presents an update on the recent advances in the field of chemical membrane reactors and on their applications in refining and petrochemistry. Previous work. Most of the possible applications of membrane reactors in petroleum and petrochemical industry concern gaseous catalytic reactions. For this reason, gas permeation membranes are the primary component of membrane reactors. Gas permeation membranes present different types of physical structure : dense, microporous or asymmetric which is a combination of the two. Separating properties of dense membranes are function of the solubility and diffusivity of each gaseous component in the membrane material. For microporous membranes, they follow four mechanisms : Knudsen diffusion, surface diffusion, capillary condensation or molecular sieving. Although organic polymers are the common constituent of gas permeation membrane, their

A two dimensional code (R,Z) for nuclear reactor analysis and its application to the UAR-RI reactor

International Nuclear Information System (INIS)

Bishay, S.T.; Mikhail, I.F.I.; Gaafar, M.A.; Michaiel, M.L.; Nassar, S.F.

1988-01-01

A detailed study is given of fuel consumption in completely reflected cylindrical reactors. A two group, two dimensional (r,z) code is developed to carry out the required procedure. The code is applied to the UAR-RI reactor and the results are found to be in complete agreement with the experimental observations and with the theoretical interpretations. 7 fig., 12 tab

Differential expression of miR-1, a putative tumor suppressing microRNA, in cancer resistant and cancer susceptible mice

Directory of Open Access Journals (Sweden)

Jessica L. Fleming

2013-04-01

Full Text Available Mus spretus mice are highly resistant to several types of cancer compared to Mus musculus mice. To determine whether differences in microRNA (miRNA expression account for some of the differences in observed skin cancer susceptibility between the strains, we performed miRNA expression profiling of skin RNA for over 300 miRNAs. Five miRNAs, miR-1, miR-124a-3, miR-133a, miR-134, miR-206, were differentially expressed by array and/or qPCR. miR-1 was previously shown to have tumor suppressing abilities in multiple tumor types. We found miR-1 expression to be lower in mouse cutaneous squamous cell carcinomas (cSCCs compared to normal skin. Based on the literature and our expression data, we performed detailed studies on predicted miR-1 targets and evaluated the effect of miR-1 expression on two murine cSCC cell lines, A5 and B9. Following transfection of miR-1, we found decreased mRNA expression of three validated miR-1 targets, Met, Twf1 and Ets1 and one novel target Bag4. Decreased expression of Ets1 was confirmed by Western analysis and by 3’ reporter luciferase assays containing wildtype and mutated Ets1 3’UTR. We evaluated the effect of miR-1 on multiple tumor phenotypes including apoptosis, proliferation, cell cycle and migration. In A5 cells, expression of miR-1 led to decreased proliferation compared to a control miR. miR-1 expression also led to increased apoptosis at later time points (72 and 96 h and to a decrease in cells in S-phase. In summary, we identified five miRNAs with differential expression between cancer resistant and cancer susceptible mice and found that miR-1, a candidate tumor suppressor, has targets with defined roles in tumorigenesis.

IEA-R1 primary and secondary coolant piping systems coupled stress analysis

International Nuclear Information System (INIS)

Fainer, Gerson; Faloppa, Altair A.; Oliveira, Carlos A.; Mattar Neto, Miguel

2013-01-01

The aim of this work is to perform the stress analysis of a coupled primary and secondary piping system of the IEA-R1 based on tridimensional model, taking into account the as built conditions. The nuclear research reactor IEA-R1 is a pool type reactor projected by Babcox-Willcox, which is operated by IPEN since 1957. The operation to 5 MW power limit was only possible after the conduction of life management and modernization programs in the last two decades. In these programs the components of the coolant systems, which are responsible for the water circulation into the reactor core to remove the heat generated inside it, were almost totally refurbished. The changes in the primary and secondary systems, mainly the replacement of pump and heat-exchanger, implied in piping layout modifications, and, therefore, the stress condition of the piping systems had to be reanalyzed. In this paper the structural stress assessment of the coupled primary and secondary piping systems is presented and the final results are discussed. (author)

An approach to estimate the reactivity worth of R-5 poison tube system and experimental verification in ZERLINA reactor

International Nuclear Information System (INIS)

Khosla, S.K.; Paul, O.P.K.; Sengupta, S.N.

1976-01-01

It is proposed to employ a liquid poison injection system as an emergency shut down device for R-5 reactor. The liquid poison consists of gadolinium nitrate solution, which is injected into twenty poison tubes made of zircaloy that are located in between the regular lattice positions in R-5 reactor. The calculational model adopted to estimate the reactivity worth of the poison tubes so as to hold the reactor subcritical by 50 mk at full tank, is described. Similar reactivity estimates have also been carried out for R-5 poison tubes installed in Zerlina reactor in order to assess the adequacy of the calculational mode. The results of the calculations are compared with experimental values for single poison tubes. (author)

Amino methylation of 2-R-6-R_1-imidazo-[2.1-B]-1.3.4-thiadiazole

International Nuclear Information System (INIS)

Saidov, D.K.; Rakhmonov, R.O.; Khodzhiboev, Yu.; Kukaniev, M.A.; Bandaev, S.

2015-01-01

Present article is devoted to amino methylation of 2-R-6-R_1-imidazo-[2.1-B]-1.3.4-thiadiazole. The reaction of new modifications of derivatives of imidazo-[2.1-B]-1.3.4-thiadiazoles-2-bromine-6-p-bromophenyl and 2-alkyl alkylene sulfonyl-6-phenyl imidazo--[2.1-B]-1.3.4-thiadiazole on Mannich with secondary and heterocyclic amines was studied.