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Sample records for junta de energia nuclear portugal reactor

  1. Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal

    OpenAIRE

    Pedro, Miguel António de Morais

    2012-01-01

    O presente trabalho tem como objectivo avaliar economicamente e determinar a viabilidade da implementação de um reactor nuclear para produção de energia eléctrica. Faz-se uma abordagem a aspectos da energia nuclear no mundo e em particular a energia nuclear na união europeia, faz-se uma análise sobre a estrutura do sector nuclear em Espanha e o futuro da energia no mundo. É realizada uma análise sobre a energia nuclear em Portugal, são abordados aspectos como o planeamento energético, a local...

  2. A report with the results of measurements carried out in AQUILON 2 for the Junta de Energia Nuclear

    International Nuclear Information System (INIS)

    Lourme, P.; Jacquemart, R.; Ledanois, G.

    1964-01-01

    Buckling measurements have been performed in support of the 'Junta de Energia Nuclear' program in the heavy water moderated critical facility AQUILON concerning lattices of uranium carbide fuel assemblies. In part of the experiments, these fuel assemblies were sheathed by housing tubes filled with organic to simulate a coolant. Each fuel assembly is a cluster of nineteen aluminium cladded, 13 mm in diameter U C rods. Experiments were made using substitution method i.e. critical approach and pulsed neutron techniques. Results are compared to lattice calculation analogous to oxide cluster calculation except about p factor. (authors) [fr

  3. Order of 28 March 1980 on the transfer to ENUSA of duties of the Junta de Energia Nuclear connected with the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1980-01-01

    In implementation of the Royal Decree of 7 December 1979 the Minister of Industry and Energy made this Order regulating the transfer to ENUSA (National Uranium Undertaking) of the Junta de Energia Nuclear's duties relating to the nuclear fuel cycle. The Order sets up, within the Ministry of Industry and Energy, a Transfer Commission responsible for establishing the directives prior to the measures to be taken by the Ministry concerning the transfer to ENUSA of the duties, personnel and establishments of the Junta connected with the nuclear fuel cycle. It will also determine the dates of such transfer, according to the order of priority laid down in the Order. (NEA) [fr

  4. Protocol between the National Laboratory of Industrial Engineering and Technology of Portugal and the Junta de Energia Nuclear of Spain on supply and transfer of technology on uranium extraction from phosphoric acid

    International Nuclear Information System (INIS)

    1982-01-01

    This Protocol was signed between the JEN and the LNETI, in the framework of the Agreement of 14th January 1971 between Spain and Portugal for co-operation in the peaceful uses of nuclear energy. It is provided that the JEN and the LNETI will promote the application of their respective technologies in the field in Portugal as well as that of technology jointly developed on such extraction. The Protocol, which became operational on its date of signature will remain in force for five years. (NEA) [fr

  5. Projeto de pesquisa Energia Nuclear

    Directory of Open Access Journals (Sweden)

    Marcelo Henrique Barbosa Fiori

    2011-07-01

    Full Text Available Esse  projeto tem como intuito mostrar como pode se útil a utilização da energia nuclear para o abastecimento elétrico de uma escola. Mostrando que a energia nuclear é sim uma fonte viável de produção de energia “[...] meio quilo de urânio, do tamanho da ponta do meu dedo se você conseguir liberar toda a energia equivale a 5.000 barris de petróleo”.

  6. Efeitos da Energia de Soldagem e Consumível sobre a Resistência à Flexão Simples de Juntas Soldadas em Perfis Tubulares de Aço TMCP

    Directory of Open Access Journals (Sweden)

    Rafael Luciano Dalcin

    2016-03-01

    Full Text Available Resumo A introdução dos aços fabricados por processamento termomecânico controlado (TMCP demandou maiores propriedades mecânicas e metalúrgicas das juntas soldadas sobre eles produzidas. Em função desses fatores, a energia de soldagem é estritamente limitada, e para evitar uma eventual redução da resistência mecânica da zona afetada pelo calor (ZAC, é necessário testar os procedimentos de soldagem próximos daqueles que serão usados na estrutura real. Desta forma, o objetivo deste estudo é obter dados detalhados referentes à eficiência mecânica de juntas soldadas pelo processo MAG e com diferentes energias de soldagem, sobre perfis tubulares quadrados em aço TMCP, formando um conjunto soldado coluna/viga. Portanto, seis distintas energias de soldagem e dois metais de adição foram utilizados (AWS ER80S-G e AWS ER120S-G, com as soldas posicionadas em todo o contorno do perfil. As doze estruturas soldadas foram instrumentadas e submetidas à flexão simples. Comparando-se as juntas soldadas produzidas com mesma energia de soldagem, e apesar dos efeitos similares sobre a zona afetada pelo calor (ZAC, aquelas fabricadas com o consumível AWS ER120S-G apresentaram maior resistência mecânica.

  7. L'energia nuclear: pot resoldre el problema de l'escalfament global?

    OpenAIRE

    Puig, Josep

    2006-01-01

    Sovint es diu que l'energia nuclear pot ser la solució pel problema de l'escalfament global: l'article presenta dades i raonaments per concloure que, si tota l'electricitat mundial fos d'origen nuclear, l'escalfament global es reduiria tan sols en un 12%. També s'analitzen els subproductes militars de la indústria de l'energia nuclear "civil" i la problemàtica dels residus radioactius de l'energia nuclear de fissió. També s'analitza l'alt grau de dificultats que presenta l'energia nuclear de ...

  8. Neutronics and thermohydraulics of the reactor C.E.N.E. Pt. 1

    International Nuclear Information System (INIS)

    Caro, R.; Ahnert, C.; Esteban Naudin, A.; Martinez Fanegas, R.; Minguez, E.; Rovira, A.

    1976-01-01

    The analysis of neutronics (both statics and kinetics), of the 10 Mwt swimming pool reactor C.E.N.E. is included. A short description of the theoretical model used, along with the theoretical versus experimental cheking, carried out, whenever possible, with the reactors JEN-1 and JEN-2 of Junta de Energia Nuclear, is given in each of these chapters. (author) [es

  9. Installation and development of neutron radiography in the nuclear reactor (IEAR-1) of the Instituto de Energia Atomica, Brazil

    International Nuclear Information System (INIS)

    Fuga, R.

    1979-01-01

    Investigations on the field of Neutron Radiography have been performed at the IEAR-1, swimming pool reactor utilizing a collimated neutron beam and the so-called photographic transfer method as a mean of detection. The test object (sample) is placed between the neutron source (reactor core) and the gold foil. The acitivity of its different points is the inverse measure of the neutrons absorbed in the test sample at the corresponding points. The activity distribution on the gold foil is determined again by exposing it to an X-ray film. A multichannel type collimator consisting of an assemblage of stainless steel tubes inside an aluminium mantle (tube) was used as a direction beam selector. Improvements have been introduced in respect to the reduction of angular divergence and neutron scattering. To improve further the quality of the radiographs another collimator type has been developed using boric acid as a neutron absorber and moderator. Flux measurements by means of gold foil activation at reactor positions of interest were necessary to eliminate errors originating of different neutron flux values. The dependence of film darkening upon the neutron flux and other factors have been discussed. Finally neutron-and gama-radiographs of the same objects were evaluated in comparison. (author) [pt

  10. A junta patriótica do norte : um projecto republicano de rememoração da I Guerra Mundial em Portugal

    Directory of Open Access Journals (Sweden)

    Sílvia Correia

    2011-01-01

    Full Text Available The Junta Patriótica do Norte (JPN was created a month after Germany’s declaration of war, stating that one of its purposes would be to follow the conflict. However, its efforts were extended and intensified in the postwar period, particularly with respect to assistance to war orphans, the organization of war commemorations, and last but not least, the dissemination and implementation of artistic tributes to the war’s fallen men. This article intends, besides the organic understanding of the institution, to first explore the Junta’s role in the conflict’s mobilization efforts and, second, its role in how the memory – material and immaterial – of World War I in Portugal has be shaped.

  11. Management report 2003 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2003 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2003, involving the government programs in the areas of nuclear safety, medicine application, technological development, administration and miscellaneous.

  12. Evaluation of two processes of hydrogen production starting from energy generated by high temperature nuclear reactors; Evaluacion de dos procesos de produccion de hidrogeno a partir de energia generada por reactores nucleares de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Valle H, J., E-mail: jvalle@upmh.edu.mx [Universidad Politecnica Metropolitana de Hidalgo, Boulevard Acceso a Tolcayuca 1009, Ex-Hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2013-10-15

    In this work an evaluation to two processes of hydrogen production using energy generated starting from high temperature nuclear reactors (HTGR's) was realized. The evaluated processes are the electrolysis of high temperature and the thermo-chemistry cycle Iodine-Sulfur. The electrolysis of high temperature, contrary to the conventional electrolysis, allows reaching efficiencies of up to 60% because when increasing the temperature of the water, giving thermal energy, diminishes the electric power demand required to separate the molecule of the water. However, to obtain these efficiencies is necessary to have water vapor overheated to more than 850 grades C, temperatures that can be reached by the HTGR. On the other hand the thermo-chemistry cycle Iodine-Sulfur, developed by General Atomics in the 1970 decade, requires two thermal levels basically, the great of them to 850 grades C for decomposition of H{sub 2}SO{sub 4} and another minor to 360 grades C approximately for decomposition of H I, a high temperature nuclear reactor can give the thermal energy required for the process whose products would be only hydrogen and oxygen. In this work these two processes are described, complete models are developed and analyzed thermodynamically that allow to couple each hydrogen generation process to a reactor HTGR that will be implemented later on for their dynamic simulation. The obtained results are presented in form of comparative data table of each process, and with them the obtained net efficiencies. (author)

  13. Design of the zero power reactor core of Instituto de Energia Atomica, SP, Brazil

    International Nuclear Information System (INIS)

    Ferreira, Antonio Carlos de Almeida

    1974-01-01

    The main characteristics of a graphite moderated core of a critical assembly to be installed in the zero power reactor of the Instituto de Energia Atomica have been defined. Several simple geometric configurations have been selected and criticality studies have been made. The necessary quantity of fissile uranium has been calculated. (author)

  14. Efeito da energia de soldagem sobre a microestrutura e propriedades mecânicas da zona afetada pelo calor de juntas de aço inoxidável duplex Effect of the welding heat input on the microstructure and mechanical properties of the heat affected zone of multipass welded joints of duplex stainless steel

    Directory of Open Access Journals (Sweden)

    Everton Barbosa Nunes

    2011-09-01

    Full Text Available O objetivo deste trabalho é analisar a influência da energia de soldagem na zona afetada pelo calor (ZAC, de juntas soldadas do aço inoxidável duplex UNS S31803. Foram realizadas soldagens com eletrodo revestido AWS E2209-17 em junta tipo V de Aço Inoxidável Duplex UNS S31803, com dois níveis de energia (15 e 20 kJ/cm. A condição soldada com energia mais elevada apresentou uma ZAC mais extensa e microestrutura mais grosseira nos passes de acabamento. No entanto, nos passes de enchimento e de raiz, as ZAC's destas regiões foram mais refinadas e menos extensa. Em relação à microdureza, a condição soldada com energia de 15 kJ/cm apresentou níveis menores. Em relação à tenacidade, não foi verificada diferença significativa nos resultados.The aim this work is to evaluate the influence of multipass welding heat input on the microstructure and mechanical properties of the heat affected zone (HAZ of UNS S31803 duplex stainless steel multipass welded joints. The shielded metal arc welding process using as filler metal the AWS E2209-17 covered electrode were employed had been carried through V joint groove UNS S31803 DSS, so that two levels of energy (15 and 20 kJ/cm had been used in this experiment. The condition welded with higher energy higher a HAZ extensive and coarser microstructure in the finishing passes. On the other hand, in the wadding passes and root pass, the HAZ this region was more refined and less extensive. In respect of microhardness, the condition welded with energy of 15 kJ/cm got lower levels. In relation to toughness, it was not observed significant differences.

  15. Management report 2007 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2007 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous.

  16. Management report 2004 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2004 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  17. Management report 2005 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2005 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  18. Management report 2006 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2006 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  19. Applications of the gas chromatography in the nuclear science and technology; Aplicaciones de la cromatografia de gases a la ciencia y tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gasco Sanchez, L

    1972-07-01

    This paper is a review on the applications of the gas chromatography in the nuclear science and technology published up to December 1971. Its contents has been classified under the following heads; I) Radiogaschromatography, II) Isotope separation, III) Preparation of labelled molecules, IV) Nuclear fuel cycle, V) Nuclear reactor technology, VI) Irradiation chemistry, VIl) Separation of me tal compounds in gas phase, VIII) Applications of the gas chromatography carried out at the Junta de Energia Nuclear, Spain. Arapter VIII only includes the investigations carried out from January 1969 to December 1971. Previous investigations in this field has been published elsewhere. (Author)

  20. Provisions relating to Nuclear Energy. II - International Conventions

    International Nuclear Information System (INIS)

    This book published by the Portuguese Junta de Energia Nuclear (Nuclear Energy Commission) reproduces in Portuguese and in the original language (English or French), texts of a series of international conventions in the nuclear field and the Statutes of international nuclear organisations and undertakings. The following are among the texts included: the Statutes of the IAEA, NEA, Eurochemic; the Euratom Treaty; the Tlatelolco Treaty; the co-operation agreement between Portugal and the United States on the peaceful uses of nuclear energy. (NEA) [fr

  1. Neutronics and thermohydraulics of the reactor C.E.N.E.-Part I; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte I

    Energy Technology Data Exchange (ETDEWEB)

    Caro, R; Ahnert, C; Naudin, A E; Martinez Fanegas, R; Minguez, E; Rovira, A

    1976-07-01

    In this report the analysis of neutronics (both statics and kinetics), of the 10 MWt swimming pool reactor C.E.N.E, is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking, carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

  2. Neutronics and thermohydraulics of the reactor C.E.N.E. Part II; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte II

    Energy Technology Data Exchange (ETDEWEB)

    Caro, R

    1976-07-01

    In this report the analysis of neutronics thermohydraulics and shielding of the 10 HWt swimming pool reactor C.E.N.E is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

  3. Neutronics and thermohydraulics of the reactor C.E.N.E. Part II

    International Nuclear Information System (INIS)

    Caro, R.

    1976-01-01

    In this report the analysis of neutronics thermohydraulics and shielding of the 10 HWt swimming pool reactor C.E.N.E is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs

  4. Neutronics and thermohydraulics of the reactor C.E.N.E.-Part I

    International Nuclear Information System (INIS)

    Caro, R.; Ahnert, C.; Naudin, A. E.; Martinez Fanegas, R.; Minguez, E.; Rovira, A.

    1976-01-01

    In this report the analysis of neutronics (both statics and kinetics), of the 10 MWt swimming pool reactor C.E.N.E, is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking, carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs

  5. Small nuclear power reactor emergency electric power supply system reliability comparative analysis; Analise da confiabilidade do sistema de suprimento de energia eletrica de emergencia de um reator nuclear de pequeno porte

    Energy Technology Data Exchange (ETDEWEB)

    Bonfietti, Gerson

    2003-07-01

    This work presents an analysis of the reliability of the emergency power supply system, of a small size nuclear power reactor. Three different configurations are investigated and their reliability analyzed. The fault tree method is used as the main tool of analysis. The work includes a bibliographic review of emergency diesel generator reliability and a discussion of the design requirements applicable to emergency electrical systems. The influence of common cause failure influences is considered using the beta factor model. The operator action is considered using human failure probabilities. A parametric analysis shows the strong dependence between the reactor safety and the loss of offsite electric power supply. It is also shown that common cause failures can be a major contributor to the system reliability. (author)

  6. Centro de Energia Nuclear na Agricultura (CENA) - Sao Paulo, Brazil, - Annual report, 1978

    International Nuclear Information System (INIS)

    Anon.

    The activities carried out at 'Centro de Energia Nuclear na Agricultura (CENA) S.P., Brazil, in 1978 are related, such as : development of research on the use of radioisotopes in crop improvement and plant breeding, as well as in the improvement of animal production; works in collaboration with other entities; personnel formation and scientific exchange with other countries. (M.A.) [pt

  7. Consolidated progress report for 1975 on nuclear data activities outside the NDS service area: Austria, Belgium, Greece, Spain, Switzerland, Turkey

    International Nuclear Information System (INIS)

    1975-12-01

    A consolidated progress report for 1975 on nuclear data activities in the following countries and institutes is presented: Austria: Atominstitut der Oesterreichischen Hochschulen, Vienna; Institut fuer Radiumforschung und Kernphysik; Oesterreichische Studiengesellschaft fuer Atomenergie, Seibersdorf; Gesellschaft zur Foerderung der Kernenergie, Graz; Belgium: University of Ghent, Ghent; University of Louvain, Louvain; Nuclear Energy Center, Mol; Greece: N.R.C. ''Demokritos'', Athens; Spain: Junta de Energia Nuclear, Madrid; Universidad Complutense, Madrid; Universidad Autonoma de Madrid, Madrid; Instituto de Fisica Corpuscular, Valencia; Universidad de Valladolid; Universidad de Zaragoza; Switzerland: University of Neuchatel, Neuchatel; University of Fribourg, Fribourg; University of Zuerich, Zuerich; Eidgenoessische Technische Hochschule, Zuerich; Institute for Reactor Research, Wuerenlingen; Turkey: Cekmece Nuclear Research Center, Istanbul

  8. Protocol Additional to the Agreement between the Government of the Republic of Ghana and the International Atomic Energy Agency for the Application of Safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons; Protocolo Adicional Al Acuerdo Entre La Republica De Ghana Y El Organismo Internacional De Energia Atomica Para La Aplicacion De Salvaguardias En Relacion Con El Tratado Sobre La No Proliferacion De Las Armas Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-27

    The text of the Protocol Additional to the Safeguards Agreement concluded between the Government of the Republic of Ghana and the International Atomic Energy Agency for the application of safeguards in connection with the Treaty for the Non-Proliferation of Nuclear Weapons (NPT) is reproduced in this document for the information of all Members. The Additional Protocol was approved by the Board of Governors on 11 June 1998. It was signed in Vienna on 12 June 1998 [Spanish] Se transcribe en el presente documento, para informacion de todos los Estados Miembros, el texto del Protocolo adicional al Acuerdo de salvaguardias concertado entre la Republica de Ghana y el Organismo Internacional de Energia Atomica para la aplicacion de salvaguardias en relacion con el Tratado sobre la no proliferacion de las armas nucleares (TNP). El Protocolo adicional fue aprobado por la Junta de Gobernadores el 11 de junio de 1998 y firmado en Viena el 12 de junio de 1998.

  9. Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics; Futuro nuclear: refletindo para construir. Anais do 5. Encontro nacional de aplicacoes nucleares; 8. Congresso geral de energia nuclear; 12. Encontro nacional de fisica de reatores e termo-hidraulica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12. ENFIR), the 8. General congress on nuclear energy (8. CGEN), and the 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed.

  10. Nuclear future: thinking for building. Proceedings of the 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications; Futuro nuclear: refletindo para construir. Anais do 12. Encontro nacional de fisica de reatores e termo-hidraulica; 8. Congresso geral de energia nuclear; 5. Encontro nacional de aplicacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12 ENFIR), 8. General congress on nuclear energy (8. CGEN), and 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed.

  11. Energia nuclear em um cenário de trinta anos Nuclear energy over a 30-year scenario

    Directory of Open Access Journals (Sweden)

    Carlos Feu Alvim

    2007-04-01

    Full Text Available A perspectiva da Energia Nuclear no Brasil é analisada sob os aspectos demanda, custos, ambiental, tecnológico e estratégico. A demanda energética projetada, mesmo para crescimentos abaixo dos desejados e considerando algum esforço de redução da intensidade energética, mostra a necessidade de adicionar energia térmica à geração elétrica, hoje predominantemente hídrica. A energia nuclear deve ter participação nessa geração por motivos econômicos, ambientais, tecnológicos e estratégicos.The perspectives of nuclear energy in Brazil is analyzed regarding demand, costs, environmental, technological and strategic aspects. The projected energy demand, even for a growth rate below the desired one and considering some efforts relative to energy intensity reduction, shows the need of adding thermal energy to electricity generation, now predominantly hydraulic. Nuclear energy should have a share in this generation due to economical, environmental, technological and strategic reasons.

  12. The text of the agreement of 22 July 1977 between Argentina and the Agency for the application of safeguards in connection with a contract concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reactor Brennelement Union GmbH Hanau (Federal Republic of Germany) for co-operation in the field of fabrication of fuel elements for peaceful nuclear activities

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 22 July 1977 between Argentina and the IAEA for the application of safeguards in connection with a contract concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reactor Brennelement Union GmbH Hanau (Federal Republic of Germany) for co-operation in the field of fabrication of fuel elements for peaceful nuclear activities has been suspended

  13. Applications of the gas chromatography in the nuclear science and technology

    International Nuclear Information System (INIS)

    Gasco Sanchez, L.

    1972-01-01

    This paper is a review on the applications of the gas chromatography in the nuclear science and technology published up to December 1971. Its contents has been classified under the following heads; I) Radiogaschromatography, II) Isotope separation, III) Preparation of labelled molecules, IV) Nuclear fuel cycle, V) Nuclear reactor technology, VI) Irradiation chemistry, VIl) Separation of me tal compounds in gas phase, VIII) Applications of the gas chromatography carried out at the Junta de Energia Nuclear, Spain. Arapter VIII only includes the investigations carried out from January 1969 to December 1971. Previous investigations in this field has been published elsewhere. (Author)

  14. ACG55/2: Convocatoria de elecciones de representantes en Juntas de Facultades y Escuelas y Consejos de Departamento.

    OpenAIRE

    Universidad de Granada

    2012-01-01

    Convocatoria de elecciones de representantes en Juntas de Facultades y Escuelas y Consejos de Departamento. Aprobado en sesi??n extraordinaria del Consejo de Gobierno de la Universidad de Granada celebrada el 24 de febrero de 2012.

  15. Annual report of Diretoria de Pesquisa e Desenvolvimento da Comissao Nacional de Energia Nuclear - 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This report presents the research activities coordinated by the Planning and Development Directorship of the Brazilian Nuclear Energy Commission (CNEN), Brazil, in 1996, relating the works achieved in its three research institutes: Nuclear and Energetic Research Institute (IPEN), Nuclear Technology Development Center (CDTN) and Nuclear Engineering Institute (IEN). It describes the institute actions through the following topics: radiopharmaceuticals and radioisotopes production - production data and new products development; environmental and social applications in nuclear energy - environmental and occupational radioprotection; instrumentation and control; bioengineering and agriculture; health and environment; and physics, chemistry and industrial processes; reactors technology and fuel cycle -nuclear fuel, reprocessing and radioactive waste; reactors and nuclear safety; operating and research reactors maintenance; and advanced materials and technologies; human resources development - training, publications and participation in events; another themes - special projects and cooperation with another institutions; financial resources - distribution and income

  16. The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

  17. Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics; Futuro nuclear: refletindo para construir. Anais do 5. Encontro nacional de aplicacoes nucleares; 8. Congresso geral de energia nuclear; 12. Encontro nacional de fisica de reatores e termo-hidraulica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The VII General Congress on Nuclear Energy (VII CGEN) decided on another approach, in order to promote nuclear energy (NE) for the average public. Instead of promoting an event for the nuclear area, the VII CGEN was open to the general public, aiming at high schools of the city of Belo Horizonte, where the meeting was held. The papers submitted were classified to two poster sessions, one called journalistic, open to the public, and technical, for the congressmen. The authors of the former session were asked to make their posters understandable for an average person. The present article shows the strategies used in dealing with local high schools, which includes the preparation of two series of posters, one dealing with the history of NE until 1945, and the other with applications of NE, due to the lack of this kind of material in Portuguese. The results of these efforts are shown and discussed, in terms of a better public image for NE and her community in Brazil. The public response showed that there is more than enough public for this kind of event, but not events enough. (author)

  18. Perception of the nuclear energy in Mexico; Percepcion de la energia nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J.V.; Alonso V, G.; Gomez T, A.M.; Palacios H, J.C. [ININ, Carretera Mexico-Toluca s/n, La Marqesa, 52750 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: vxm@nuclear.inin.mx

    2007-07-01

    From their beginnings the Nuclear Energy has generated a lot of polemic, since on one hand it was seen as something completely harmful, due to the making of atomic weapons and those effects of the radiation (Hiroshima and Nagasaki). But on the other hand it has been saying that it could be the 'Panacea' of the humanity like an inexhaustible source of energy, this brought that a countless of reactors was built for the electric power production at world level, unfortunately some accidents as that of Chernobyl (Former Soviet Union 1986) as well as the contribution of the media of the fear toward the nuclear energy made that it was formed a barrier of the public opinion toward all that has to do with the nuclear energy, the construction of new power stations one came below and even in some countries the environmentalist organizations achieved their governments to close some power stations. In the last years the concern for the global heating and the climatic change has put in the world calendar the use of the nuclear energy again, by means of the new designs of advanced reactors with more safety measures, more efficient and economic. In several countries the public opinion is looking to the nuclear energy with good eyes, reason by a resurgence is glimpsed from the nuclear energy to great scale, so it is so several countries they have already begun the construction of new advanced reactors ones (Japan, China, Finland) and some included one already has them in operation. In Mexico, it is ignored to certain science which is the real posture of the public opinion with regard to this topic so controversial, reason why it was carried out this study to know the perception of the public in general with regard to this topic, as well as the convenience of enlarging the infrastructure of electric power generation in our country by means of this energy type. (Author)

  19. Nuclear public information activities in Chile; Programa de educacion publica de la energia nuclear en Chile

    Energy Technology Data Exchange (ETDEWEB)

    Munoz Quintana, R [Comision Chilena de Energia Nuclear, Santiago (Chile)

    1995-10-01

    Nuclear plans and developing programs in developing and developed countries are facing-in a higher or lower degree- opposition from public opinion. The objectives and contents of the public education program on nuclear energy in Chile are dealt with in this paper.

  20. Public perception of nuclear power in Mexico after Fukushima; Percepcion publica de la energia nuclear en Mexico despues de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Palacios, J. C.; Alonso, G.; Ramirez, R., E-mail: javier.palacios@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    This section presents some of the results of four studies on international public opinion about nuclear energy, the first one made several years before the Fukushima accident, conducted in 2005 by the IAEA through the company Globe Scan Inc. The second study was conducted by the same company in 2011 a few months after the Fukushima accident, including also corresponding results to two studies conducted by the British firm Ipsos Mori (of years 2011 and 2012 respectively). Finally three studies conducted by the Instituto Nacional de Investigaciones Nucleares (ININ) in 2006, 2008 and 2013 are presented. From the results of these studies was determined that the Fukushima accident itself had a negative effect on public opinion in Mexico, as throughout the world, but this trend is reversing. Also it found that public opinion in Mexico on using reactors to generate electricity is favorable, although not still has much support from the government for the construction of new nuclear power plants. (Author)

  1. Aquaculture investigations with nuclear energy techniques; Investigaciones acuicolas con tecnicas de energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Heredia Salazar, Brunilda [Fondo Nacional de Investigaciones Agropecuarias (FONAIAP), (CIAE), Estacion Experimental Guanapito, Guarico (Venezuela)

    1997-07-01

    The culture of aquatic organisms, especially that of fishes under controlled conditions, up to their harvesting, processing, commercialization and consumption, has been pointed out as an activity that produces a lot of benefits, among them: the obtention high proteic valued food, the incorporation to the economy of lands not usefull for agriculture activities, the increment of fishing resources, the recycling of organic matter produced in the units, the regional development, the generation of employment, technologies and foreign currencies. Several research areas are identified that can be developed, using the nuclear technologies, for example in the reproduction, nutrition, diagnose and control of illnesses, environmental monitoring and quality certification of products. In the concerning to the Venezuelan aquaculture, investigations are required that need to use those techniques. For example: 1) Production of autochthonous inductive agents, by means of radioinmunoenssay (RIA), to determine the gonadotropines coming from the hypophysis of fish cultivated with the purpose of gathering the glands in its best moment, to generate the final maturation and spawn in autochthonous species. 2) Genetic improvement of cultivated species through the knowledge of the genetic load of different lines and breeds found in the natural means, and to achieve its maintenance to solve inbreeding problems, in autochthonous species aswell in as in exotic ones, by the use of marking techniques (ADE, RFLA and microsatellite techniques). 3) Nutritional and feeding studies of species under commertial culture, especially on the effect of the aflatoxins in the inputs or the portions, substances that influence in a negative way the aquatic nutrition. In this case, competitive immunoassays of enzymes bounded (ELISA) and radioinmunoessays. 4) Illness diagnose, by means of the ELISA kit, specifically of the more common illness in fishes cultivated in the country. [Spanish] El cultivo de organismos

  2. Kinematics of high-energy nuclear processes; Cinematica de los procesos nucleares de alta energia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez del Rio, C

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title:Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  3. Kinematics of low-energy nuclear processes; Cinematica de los procesos nucleares de baja energia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez del Rio, C

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  4. Uso de detectores de neutrinos para el monitoreo de reactores nucleares Uso de detectores de neutrinos para el monitoreo de reactores nucleares

    Directory of Open Access Journals (Sweden)

    Gerardo Moreno

    2012-02-01

    Full Text Available Se estudia la factibilidad del uso de los detectores de antineutrinos para el monitoreo de reactores nucleares. Usando un modelo sencillo de cascada de fisión a dos componentes, se ilustra la dependencia del número de antineutrinos detectados a una distancia L del reactor según la composición nuclear del combustible. Se explica el principio de detección de neutrinos de reactores en base al decaimiento beta inverso y se describe como los detectores de neutrinos pueden emplearse para el monitoreo de la producción de materiales fisibles en el reactor. Se comenta como generalizar este análisis al caso real de un reactor nuclear in situ y uno de los principales experimentos internacionales dedicados a este propósito. We study the feasibility to use antineutrinos detectors for monitoring of nuclear reactors. Using a simple model of fission shower with two components, we illustrate how the numbers of antineutrinos detected at a distance L from the reactor depend on the composition of the nuclear combustible. We explain the principles of reactor neutrino detection using inverse beta decays and we describe how neutrinos detectors can be used for monitoring the production of fissile materials within the reactors. We comment how to generalize this analysis to the realistic case of a nuclear reactor in situ and one of the main international experiments dedicated to study the use of neutrinos detectors as nuclear safeguards.

  5. Development of technologies for nuclear reactors of small and medium sized; Desarrollo de Tecnologias para Reactores Nucleares de pequeno y medio tamano

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-08-15

    This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

  6. Act 25/1968 of 20 June amending Sections 9 and 16 of Act 25/1964 of 29 April on nuclear energy

    International Nuclear Information System (INIS)

    1968-01-01

    The main purpose of this Act to amend the 1964 Act on Nuclear Energy is to set the age limit for the Board of the Junta de Energia Nuclear at 70; that of the Director is set at 65. These same provisions also apply to the Chairman and the Director of the Institute for Nuclear Studies. Finally, the Act modifies the composition of the Board of the Junta which henceforth includes only one Vice-Chairman. (NEA) [fr

  7. Comportamiento mecánico de las juntas tipo T-bolt en materiales compuestos gruesos

    OpenAIRE

    Martínez Moll, Víctor

    2003-01-01

    En aquest treball s'ha realitzat una anàlisi de la junta T-bolt aplicada a la unió de laminats gruixuts amb elements metàl·lics. Més concretament, l'estudi es centra en el tipus de juntes T-bolt emprades en la unió entre les pales i la boixa de grans aerogeneradors, que constitueix una de les principals aplicacions d'aquest tipus de junta.En primer lloc, s'ha realitzat una anàlisi simplificada dels factors que influeixen al comportament de la junta, a partir del qual es justifica la necessit...

  8. Licensing for the construction of 'Almirante Alvaro Alberto' nuclear power plant

    International Nuclear Information System (INIS)

    1974-09-01

    The BRAZILIAN NUCLEAR ENERGIA COMMISSION (Comissao Nacional de Energia Nuclear - CNEN) presents in Report n 0 51 of its Reactors Department all the requirements for the construction permit of 'Almirante Alvaro Alberto' Nuclear Power Plant [pt

  9. The nuclear energy in the seawater desalination; La energia nuclear en la desalacion de agua de mar

    Energy Technology Data Exchange (ETDEWEB)

    Moreno A, J.; Flores E, R.M. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2004-07-01

    In general, the hydric resources of diverse regions of the world are insufficient for to satisfy the necessities of their inhabitants. Among the different technologies that are applied for the desalination of seawater are the distillation processes, the use of membranes and in particular recently in development the use of the nuclear energy (Nuclear Desalination; System to produce drinkable water starting from seawater in a complex integrated in that as much the nuclear reactor as the desalination system are in a common location, the facilities and pertinent services are shared, and the nuclear reactor produces the energy that is used for the desalination process). (Author)

  10. Study of nuclear reactions involving heavy nuclei and intermediate- and high-energy protons and an application in nuclear reactor physics (ADS); Estudo das reacoes nucleares envolvendo nucleos pesados e protons a energias intermediarias e altas de uma aplicacao em fisica de reatores nucleares (ADS)

    Energy Technology Data Exchange (ETDEWEB)

    Matuoka, Paula Fernanda Toledo

    2016-07-01

    In the present work, intermediate- and high-energy nuclear reactions involving heavy nuclei and protons were studied with the Monte Carlo CRISP (Rio - Ilheus - Sao Paulo Collaboration) model. The most relevant nuclear processes studied were intranuclear cascade and fission-evaporation competition. Preliminary studies showed fair agreement between CRISP model calculation and experimental data of multiplicity of evaporated neutrons (E < 20 MeV) from the p(1200 MeV) + {sup 208}Pb reaction and of spallation residues from the p(1000 MeV) + {sup 208}Pb reaction. The investigation of neutron multiplicity from proton-induced fission of {sup 232}Th up to 85 MeV showed that it was being overestimated by CRISP model; on the other hand, fission cross section were being underestimated. This behavior is due to limitations of the intranuclear cascade model for low-energies (around 50 MeV). The p(1200 MeV) + {sup 208}Pb reaction was selected for the study of a spallation neutron source. High-energy neutrons (E > 20 MeV) were emitted mostly in the intranuclear cascade stage, while evaporation presented larger neutron multiplicity. Fission cross section of 209 mb and spallation cross section of 1788 mb were calculated both in agreement with experimental data. The fission process resulted in a symmetric mass distribution. Another Monte Carlo code, MCNP, was used for radiation transport in order to understand the role of a spallation neutron source in a ADS (Accelerator Driven System) nuclear reactor. Initially, a PWR reactor was simulated to study the isotopic compositions in spent nuclear fuel. As a rst attempt, a spallation neutron source was adapted to an industrial size nuclear reactor. The results showed no evidence of incineration of transuranic elements and modifications were suggested. (author)

  11. Communication techniques and nuclear energy; Tecnicas de comunicacion y energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carpintero Santamaria, N.

    2005-07-01

    The paper presents some thoughts on several factors related to nuclear energy and the way they are presented by the mass media, usually provoking controversy to the Spanish society and thus, undermining public acceptance. Some possibilities for boosting nuclear energy among public opinion are suggested, emphasizing the fact that nuclear power is essential because it is both ecologically and economically sound. (Author)

  12. Teaching simulator for divulgation of the nuclear energy; Simulador docente para divulgacion de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ortega B, M.G.; Gutierrez F, R. [FI-UNAM, DEPFI Campus Morelos (Mexico)] e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    To solicitude of the authorities of the 'Universum' sciences museum of the UNAM, it develops a highly interactive computational system, to provide of information to the population in general about basic principles, uses and benefits of the nuclear energy. The objective is to achieve a better understanding and acceptance of the nuclear technology in our country. The system allows the visualization and simulation of nuclear processes as well as of its applications. The system is divided in three levels: basic, intermediate and simulation. In the basic level multimedia information is included on diverse basic concepts of the nuclear energy. The intermediate level includes the description and operation of some systems of the Laguna Verde nuclear power plant (CNLV). Finally the simulation level contains representative scenarios that the user can control by means of virtual control panels of the main systems of the CNLV. Inside the system a part of interactive games is included with the purpose that the user remembers with more easiness all the concepts and advantages of the nuclear energy mentioned during the previous levels. The system contributes, by means of the development of multimedia computational tools and of simulation, to the popularization of the use and applications of the nuclear energy in Mexico. (Author)

  13. The convenience of nuclear energy; La conveniencia de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lucena, A.

    2007-07-01

    It is unquestionable that the power sources must change, for the same reasons for which the propagandist ones have been appropriated of the nuclear energy: its use is not a sustainable practice and produces the climatic change and other many damages. In this sense, any alternative has to be considered, and, a priori, the nuclear one, that at this moment is very minority in the power system, does not have to be an exception. For that reason it is not necessary to let be critical with anyone of the alternatives that are considered, and this aspect also affects the nuclear energy. (Author)

  14. Comparing nuclear power with other energy sources; Comparacion de la energia nuclear con otras fuentes energeticas

    Energy Technology Data Exchange (ETDEWEB)

    Rey, Francisco C [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    The economics of electric generation of nuclear, hydro, oil and gas origin are compared. A similar comparison is also made from the health and environment standpoint for the fossil, nuclear, solar and wind generation. A risk assessment for energies of different origin is outlined and the significance of the greenhouse effect is emphasised. A comprehensive economic and environmental evaluation is recommended for the energy planning.

  15. ESTADO DE LAS NORMAS INTERNACIONALES EMITIDAS POR LA JUNTA DE NORMAS INTERNACIONALES DE CONTABILIDAD

    OpenAIRE

    Vílchez Olivares, Percy Antonio

    2014-01-01

    El presente artículo presenta el nuevo esquema contable internacional de la Junta de Normas Internacionales de Contabilidad, su historia, estructura actual, objetivos y el estado actual del marco normativo de las Normas Internacionales de Contabilidad. Con la vigencia Ley General de Sociedades Ley N.° 26887 de 1997, el Perú adoptó en forma legal las Normas Internacionales de Información Financiera (antes Normas Internacionales de Contabilidad), para su aplicación obligatoria en la preparación...

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  17. The Future of Nuclear Energy; El futuro de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, A.

    2005-07-01

    Current nuclear energy represents 23.5% of the total electrical power available within the OECD countries. This is the energy offering the lowest costs to generate, it does not emit greenhouse-effect fumes nor does it contribute to global warming, however, it does generate radioactive and toxic waste which society perceives as an unacceptable risk. For this reason the development of new nuclear installation in Europe is at a stand still or moving backward. Truthful information and social participation in decisions is the best way to achieve the eradication of the social phobia produced by this energy source. (Author)

  18. Asuntos de la dirección y gerencia en las juntas directivas

    OpenAIRE

    Corredor García, Héctor Manuel

    2009-01-01

    Las juntas directivas han tenido dificultades que han deteriorado su efectividad. A pesar de buscar el mejoramiento del desempeño de estas a través de regulaciones y de enfoques netamente financieros, el problema persiste. Este artículo busca determinar que un cambio en el grado de atención, en los temas y asuntos de dirección y gerencia que tratan las juntas directivas, puede contribuir a una mayor efectividad de estas. La metodología utilizada para este análisis se basa en una encuesta diri...

  19. The environment and nuclear energy development. El medio ambiente y el desarrollo de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Velez O, C [Instituto Nacional de Investigaciones Nucleares, Mexico City (Mexico)

    1989-01-01

    In the last years we have testified the concern about deterioration of environment, especially, for changes in global scale, either measured or calculated, with unlucky predictions for human kind. Phenomena as acid rain, destruction in the ozone layer and Greenhouse effect, has increased successively the state of alarm in global public opinion, which is already translated either in proliferation of International meetings or in the adoption of recommendations not always pondered and justified. With all these preoccupations, many people are rediscovering that nuclear power does not produce Greenhouse gases, especially CO[sub 2]. (Author).

  20. Nuclear energy through Philately; La energia nuclear a traves de la filatelia

    Energy Technology Data Exchange (ETDEWEB)

    Torres de la Pena, M. T.

    2016-08-01

    Postage stamps, apart from being signs of postage, are a valuable means of communication that reproduces, in mary ways, milestones of history. Postatge stamps have different formats and values, can be printed with different systems (offset, gravure or intaglio) and can also have several uses. Countries have used them to record important cultural, social, historical and scientific events that are often unknown, and generally to promote the image of a country. For this reason, postage stamps disclose international development in different disciplines; in this case, science and nuclear technology. (Author)

  1. INPRO Methodology to evaluate the Mexico nuclear energy system; Metodologia INPRO para evaluar el sistema de energia nuclear de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Cruz S, R. R.; Martin del C, C., E-mail: crzslns.ricardoruben@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2016-09-15

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  2. Decree-Law No. 48568 of 4 September 1968 - Competence of the J.E.N. to undertake scientific and technical inspections of private or public bodies involved in nuclear research or nuclear activities

    International Nuclear Information System (INIS)

    1968-01-01

    Under this Decree-Law, the Junta de Energia Nuclear (JEN) is empowered to inspect on a regular basis all establishments and installations involved in nuclear activities. These inspections are made to ensure that the installations are operated safely and efficiently and that radiation protection measures are properly applied. (NEA) [fr

  3. O espaço da energia nuclear no Brasil

    Directory of Open Access Journals (Sweden)

    Joaquim Francisco de Carvalho

    2012-01-01

    Full Text Available Este artigo repassa a história e descreve a experiência acumulada em energia nuclear no Brasil, mostrando que as aplicações biomédicas, industriais e agrícolas desenvolveram-se bem no país, a partir dos anos 1950. Em seguida, o artigo demonstra que o país pode cobrir seu consumo de energia elétrica apenas com fontes renováveis de energia, sem recorrer a usinas nucleares de potência. Por fim, são analisados os argumentos comuns na imprensa, a favor e contrários às centrais nucleares, e são discutidos alguns aspectos comerciais e políticos do problema. São também examinadas as estratégias de vendas da indústria nuclear no Brasil.This article reviews the history and describes the experience on nuclear energy in Brazil, showing that nuclear technology applied to biomedical sciences, industry and agriculture has been largely developed in this country, from the year 1950 on. Then the paper shows that Brazil can cover its electricity consumption with only renewable energy sources, without nuclear power plants. Finally the arguments usually employed in the press, pro and against nuclear power plants are analyzed and some commercial and political aspects of the problem are commented. The sales strategy of the nuclear industry in Brazil is also commented.

  4. Carga limite para juntas mecânicas em laminados de fibra de carbono

    OpenAIRE

    Arthur Chaves de Mas Santacreu

    1989-01-01

    Neste trabalho são testadas várias juntas parafusadas com laminados de fibra de carbono. São investigadas as influências dos parâmetros geométricos e dos parâmetros de constituição do laminado no comportamento da curva carga versus deformação do furo carregado. Paralelamente é desenvolvido um modelo de elementos finitos linear elástico para calcular a deformação do furo carregado a partir das propriedades mecânicas do material e da geometria da junta. É proposto um critério de previsão de car...

  5. Review of experience gained in fabricating nuclear grade uranium and thorium compounds and their analytical quality control at the Instituto de Energia Atomica, Sao Paulo, Brazil

    International Nuclear Information System (INIS)

    Abrao, A.; Franca Junior, J.M.; Ikuta, A.

    1977-01-01

    The main activities developed at 'Instituto de Energia Atomica' Sao Paulo, Brazil, on the recovery of uranium from ores, the purification of uranium and thorium raw concentrates and their transformation in nuclear grade compounds, are reviewed. The design and assemble of pilot facilities for ammonium diuranate (ADV) uranium tetrafluoride, uranium trioxide, uranium oxide microspheres, uranyl nitrate denitration, uranim hexafluoride and thorium compounds are discussed. The establishment of analytical procedures are emphasized [pt

  6. Juntas de contracción en canales y depósitos de agua

    Directory of Open Access Journals (Sweden)

    Safránez, Carlos

    1977-12-01

    Full Text Available In view of the lack of Information available on the subject of contraction joints in canals and water tanks, and this being of great importance for water-tightness in this type of construction, the data considered as essential for planning joints has been presented in a systematic way. The most common of joints, and their characteristics, are mentioned and listed in accordance with their design and the procedure used for sealing them. The great importance of joint design and dimensions in relation to their performance has been highlighted. In the projects carried out, referring to this type of joint, we see there is a lack of common criteria regarding the minimum requisites and conditions which the joints must have in order to duly fulfill their mission. Experience has proven that the results obtained with contraction joints in canals and water tanks have not been totally satisfactory. In a large number of cases, bothersome and costly repairs were necessary to overercome deficiencies observed. In order to improve this situation, the different factors which influence the contraction joint's performance are discussed and they should be taken into account when planning the joints and their dimensions, in order to insure greatest efficiency.Vista la escasa información disponible sobre las juntas de contracción en canales y depósitos de agua, siendo indiscutible su gran importancia para la estanquidad de estas obras, se han expuesto, en forma sistemática, los datos considerados esenciales para enfocar debidamente el proyecto de las juntas. Se han indicado los tipos de juntas más corrientes, ordenadas de acuerdo con su diseño y con el procedimiento empleado para su sellado, señalando sus características. Se ha tratado de la importancia primordial del diseño y de las dimensiones de las juntas en relación con su comportamiento. En los proyectos de las juntas ejecutadas llama la atención la falta de una unidad de criterio sobre las

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  8. O Processo de Avaliação de Estagiários da Comissão Nacional de Energia Nuclear - CNEN: focalizando seu instrumento

    Directory of Open Access Journals (Sweden)

    Regina Márcia Rocha Lidington

    2010-01-01

    Full Text Available O artigo apresenta o processo avaliativo e os resultados da avaliação do instrumento utilizado para a avaliação de estagiários da Comissão Nacional de Energia Nuclear - CNEN, denominado Avaliação do Estágio pelo Supervisor. A avaliação se concentrou na definição dos cinco Conceitos utilizados para avaliar os nove Aspectos que compõem o instrumento, buscando estabelecer Padrões capazes de minimizar o efeito das interferências subjetivas capazes de comprometer a avaliação do estagiário. Foram utilizadas as abordagens Centrada nos Consumidores, Centrada em Especialistas e Responsiva. Participaram do processo avaliativo os três públicos interessados: Ex-estagiários, Orientadores/Supervisores de Estágio e profissionais da área de Recursos Humanos que atuam no gerenciamento do Programa de Estágios, na Instituição. Os resultados do estudo englobam sugestões de ordem quantitativa e qualitativa para cada um dos Padrões propostos no instrumento.

  9. Chilean Nuclear Energy Commission dosimetric information system; Sistema de informacion dosimetrico de la Comision Chilena de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Guerrero Vallejos, Patricia Andrea

    1998-12-31

    This thesis discusses the nuclear radiation that people who work with radioactive material is exposed to and its control by the Chilean Nuclear Energy Commission. A full analysis of the System is presented with information about the Commission and the Department of Nuclear and Radiological Safety which runs the System. Ana analysis of the System is presented in order to obtain requirements. Management flow diagrams, the processes involved and current problems experienced by the users are described. A design logic is modeled producing Data Flow Diagrams (DFD). based on this physical design, or, Model of Physical Data, is prepared including tables, attributes, types of data, primary and foreign keys. A description is presented of how the System is implemented, the tools that are used and how the testing phase is carried out. The Dosimetry System meets the criteria for a Software Engineering project, where the basic cycle was used as a working methodology. The System developed supports the dosimetric control of people exposed to radioactive material. (author) Dissertation to obtain the degree of Computing and Informatics Engineer; 16 refs., 96 figs., 31 tabs.

  10. 2. Scientific meeting of Chilean Nuclear Energy Commission. Abstracts; Segundas jornadas cientificas de la Comision Chilena de Energia Nuclear. Resumenes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    This publication includes 33 papers in the fields on analytical methods nuclear and conventional, atomic and molecular physics, ionizing radiations, nuclear and non nuclear materials, radiological protection and nuclear safety.

  11. Nuclear instrumentation for research reactors; Instrumentacion nuclear para reactores nucleares de investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Hofer, Carlos G.; Pita, Antonio; Verrastro, Claudio A.; Maino, Eduardo J. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Unidad de Actividades de Reactores y Centrales Nucleares. Sector Instrumentacion y Control

    1997-10-01

    The nuclear instrumentation for research reactors in Argentina was developed in 70`. A gradual modernization of all the nuclear instrumentation is planned. It includes start-up and power range instrumentation, as well as field monitors, clamp, scram and rod movement control logic. The new instrumentation is linked to a computer network, based on real time operating system for data acquisition, display and logging. This paper describes the modules and whole system aspects. (author). 2 refs.

  12. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  13. AZTLAN platform: Mexican platform for analysis and design of nuclear reactors; AZTLAN platform: plataforma mexicana para el analisis y diseno de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edif. 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Francois L, J. L.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco No. 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

    2014-10-15

    The Aztlan platform Project is a national initiative led by the Instituto Nacional de Investigaciones Nucleares (ININ) which brings together the main public houses of higher studies in Mexico, such as: Instituto Politecnico Nacional, Universidad Nacional Autonoma de Mexico and Universidad Autonoma Metropolitana in an effort to take a significant step toward the calculation autonomy and analysis that seeks to place Mexico in the medium term in a competitive international level on software issues for analysis of nuclear reactors. This project aims to modernize, improve and integrate the neutron, thermal-hydraulic and thermo-mechanical codes, developed in Mexican institutions, within an integrated platform, developed and maintained by Mexican experts to benefit from the same institutions. This project is financed by the mixed fund SENER-CONACYT of Energy Sustain ability, and aims to strengthen substantially to research institutions, such as educational institutions contributing to the formation of highly qualified human resources in the area of analysis and design of nuclear reactors. As innovative part the project includes the creation of a user group, made up of members of the project institutions as well as the Comision Nacional de Seguridad Nuclear y Salvaguardias, Central Nucleoelectrica de Laguna Verde (CNLV), Secretaria de Energia (Mexico) and Karlsruhe Institute of Technology (Germany) among others. This user group will be responsible for using the software and provide feedback to the development equipment in order that progress meets the needs of the regulator and industry; in this case the CNLV. Finally, in order to bridge the gap between similar developments globally, they will make use of the latest super computing technology to speed up calculation times. This work intends to present to national nuclear community the project, so a description of the proposed methodology is given, as well as the goals and objectives to be pursued for the development of the

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  15. Co-operation Agreement. The Text of the Agreement of 25 May 1998 between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials; Acuerdo de Cooperacion. Texto del Acuerdo de 25 de Mayo de 1998 entre el Organismo Internacional de Energia Atomica y la Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-30

    The text of the Co-operation Agreement between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials is reproduced herein for the information of all Members. The Agreement entered into force on 25 May 1998, pursuant to Article 8 [Spanish] El texto del Acuerdo de Cooperacion entre el Organismo Internacional de Energia Atomica y la Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares se reproduce en el presente documento para informacion de todos los Miembros. El Acuerdo entro en vigor el 25 de mayo de 1998 en conformidad con lo dispuesto en el articulo 8.

  16. Law created by the National Commission for Nuclear Energy. Ley que crea la Comision Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    1955-12-01

    The National Commission for Nuclear Energy issued a law, enforced on January 1, 1956, in its position as an organ of the Federal Executive Power, with its own personality and patrimony, and the judicial capacities necessary to carry out its purposes: for all matters pertaining this law, 'atomic materials' are those included in the Mineral Resources; uranium, thorium and in general all elements from which energy may be obtained in large amounts through nuclear reactions, based upon the judgement of the Commission. The objective of the National Commission for Nuclear Energy is to control, survey, coordinate, foster and carry out: (a) Exploration and exploitation of atomic material deposits, as well as the deposits of all other material that may be of specific use for the construction of nuclear reactors. (b) Possession of atomic material. (c) Exports and imports of such material. (d) Imports and exports of equipment for the use of nuclear energy. (e) Trade and local transportation of these materials. (f) The production and use of nuclear energy, intended primarily to satisfy national needs. (g) Scientific research in the field of nuclear fission and all related technical and scientific disciplines.

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  18. Influence of the silicon content on the core corrosion properties of dispersion type fuel plates; Influencia del Contenido en silicio sobre la corrosion acuosa de los nucleos de placas combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Calvo, C; Saenz de Tejada, L M; Diaz Diaz, J

    1969-07-01

    A new process to produce aluminium base dispersion type fuel plates has been developed at the Spanish JEN (Junta de Energia Nuclear). The dispersed fuel material is obtained by an aluminothermic process to render a stoichiometric cermet of UAI{sub 3} and AI{sub 2}O{sub 3} according to the reaction. (Author)

  19. LA JUNTA CENTRAL DE HIGIENE DE COLOMBIA, OTRA DE LAS VÍCTIMAS DE LA PANDEMIA DE GRIPA DE 1918-1919.

    Directory of Open Access Journals (Sweden)

    Abel Fernando Martínez Martín

    2014-12-01

    Full Text Available Objetivo: El presente artículo, a través de las fuentes primarias, busca establecer el papel del estado y las medidas tomadas ante la aparición de la pandemia de gripa de 1918 en Bogotá. Materiales y métodos: Se consultaron como fuentes primarias los periódicos que circulaban en Bogotá y Colombia durante 1918, los informes oficiales de la Junta Central de Higiene y de la Junta de Socorros y las tesis de medicina de la Universidad Nacional de Colombia. Además de hacer una revisión de las fuentes secundarias sobre el tema. Conclusión: La Higiene Pública, en manos del Estado, se mostró incapaz de hacer frente a la pandemia, siendo la Junta de Socorros, un organismo privado constituido por los notables de la capital, la única institución que realizó acciones efectivas con los afectados. Esta institución aparece recordada y alabada por los medios escritos, en contraposición a la Dirección Nacional y Municipal de Higiene, que fueron fuertemente criticadas por su escasa intervención ante la pandemia y representadas como víctimas en las caricaturas. Palabras Clave: Gripa 1918, Pandemia, Bogotá, Junta de Socorros, Junta Central de Higiene.

  20. Energy analysis of a desalination process of sea water with nuclear energy; Analisis energetico de un proceso de desalinizacion de agua de mar con energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Martinez L, G.; Valle H, J., E-mail: julfi_jg@yahoo.com.mx [Universidad Politecnica Metropolitana de Hidalgo, Boulevard acceso a Tolcayuca No. 1009, Ex-hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2016-09-15

    In the present work, is theoretically proven that the residual heat, removed by the chillers in the stage prior to the compression of the recuperative Brayton cycle with which nuclear power plants operate with high temperature gas reactors (HTGR), can be used to produce stem and desalinate seawater. The desalination process selected for the analysis, based on its operating characteristics, is the Multi-Stage Distillation (Med). The Med process will use as energy source, for the flash evaporation process in the flash trap, the residual heat that the reactor coolant dissipates to the environment in order to increase the compression efficiency of the same; the energy dissipated depends on the operating conditions of the reactor. The Med distillation process requires saturated steam at low pressure which can be obtained by means of a heat exchanger, taking advantage of the residual heat, where the relative low temperatures with which the process operates make the nuclear plants with HTGR reactors ideal for desalination of sea water, because they do not require major modifications to their design of their operation. In this work the energy analysis of a six-stage Med module coupled to the chillers of an HTGR reactor of the Pebble Bed Modular Reactor type is presented. Mathematical modeling was obtained by differential equations of mass and energy balances in the system. The results of the analysis are presented in a table for each distillation stage, estimating the pure water obtained as a function of the heat supplied. (Author)

  1. Caracterização de Uma Junta Dissimilar entre Aço Carbono e Inconel 625 Obtida por Soldagem por Explosão

    Directory of Open Access Journals (Sweden)

    Rodrigo Andrade Ribeiro

    Full Text Available Resumo Neste trabalho é caracterizada uma junta dissimilar entre aço carbono e inconel 625 obtida pela soldagem por explosão. A caracterização metalográfica foi feita com uso de diferentes ataques químicos e observação microestrutural do metal de base (MB, a interface e o revestimento de inconel 625 por meio de microscopia ótica (MO, microscopia eletrônica de varredura (MEV e espectroscopia de energia dispersa (EDS. Ensaios de microdureza foram realizados em todas as regiões. Os resultados mostram forte deformação dos grãos na proximidade da interface, tanto do lado do MB quanto do lado do inconel, tendo sido verificado significativo aumento da dureza. Na interface, ocorre o aparecimento de zonas localmente fundidas devido à dissipação de energia no impacto durante a explosão. Estas zonas apresentam microestrutura provavelmente martensítica. O trabalho conclui que o processo atinge os níveis de qualidade e produtividade característicos do segmento offshore.

  2. Portfolio of patents after the Brazilian Innovation Act: the case of the Comissao Nacional de Energia Nuclear - CNEN (Brazilian National Nuclear Energy Commission)

    International Nuclear Information System (INIS)

    Pereira, Gustavo Jose; Guimaraes, Regia Ruth Ramirez; Perry, Katia da Silva Peixoto; Teruya, Dirceu Yoshikazu

    2013-01-01

    The process of technological development is due to the need to promote a solution to a particular problem of agents, compete with products and/or processes on the international market and to promote scientific advancement. Thus, the patent system is a repository of knowledge for protection, for promotion of diffusion through licensing agreements and an indicator of technological development. In 2004, the Brazilian Government enacted the Brazilian Innovation Act and the mechanisms were improved for cooperation between firms and public education, science and technology organisations and also promoted the commercialisation of technology produced by public education, science and technology organisations and the mandatory establishment of Technology Transfer Offices. The Comissao Nacional de Energia Nuclear (CNEN) is a federal agency responsible for basic and applied research in the field of nuclear technology and has used the patent system since the 1980s to protect its knowledge. With the advent of the Innovation Act in 2004, there was a significant boost in requests for patents in CNEN which also established an internal set of normative acts and created a System of Innovation Management and Technology Innovation Offices in its research institutes to support management and dissemination of knowledge. The aim of this case study is to present the profile of the requests for patents by CNEN before and after the enactment of the Brazilian Innovation Act covering the period of time between 1980 and 2010. (author)

  3. Un narrador insolidario: el caso de Junta de acreedores de julio Ramón Ribeyro

    Directory of Open Access Journals (Sweden)

    Jorge Valenzuela Garcés

    2011-05-01

    Full Text Available Se analiza al narrador en el cuento “Junta de acreedores” de Julio Ramón Ribeyro incluido en su primer libro Los gallinazos sin plumas. Nuestro propósito es probar que, por lo menos, en este cuento, el autor se aleja de la prédica neorrealista que la crítica le ha atribuido hasta ahora. Cuestionandoeste lugar común, proponemos una nueva lectura que descubre en el texto la defensa implícita de un sistema que valora positivamente la fortaleza de aquellos que saben adaptarse al cambio, frente a los que son vistos como incapaces de tal adaptación (las llamadas víctimas sociales reivindicadas por los neorrealistas. Finalmente se trabaja con un conceptoque críticos como James Higgins utilizan para juzgar los cuentos de Ribeyro: la inhumanidad del sistema. Aquí observamos cómo este concepto entra en crisis al ser aplicado al cuento, sobre todo cuando constatamos que en él,a través del narrador, hay una burla irónica contra el comportamiento de los más débiles. Palabras claves: Ribeyro, neorrealismo, narrador, inhumanidad del sistema.

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  6. Projeto de um controlador adaptativo para robôs manipuladores no espaço de juntas

    Directory of Open Access Journals (Sweden)

    Nardênio Almeida Martins

    2001-05-01

    Full Text Available Este artigo apresenta o projeto de um controlador adaptativo de robôs manipuladores no espaço de juntas. Uma nova lei de controle adaptativa composta, que usa o erro de predição e os erros de seguimento para direcionar a estimação de parâmetros, é baseada na passividade e no método direto de Lyapunov. A convergência e a estabilidade global são mostradas para o algoritmo de controle adaptativo. O algoritmo tem as vantagens de não necessitar da “medição” de aceleração nas juntas e de não necessitar que a inversa da matriz de inércia estimada seja limitada. Exemplos de simulação são fornecidos para demonstrar o desempenho do algoritmo proposto

  7. La correspondencia entre José M. Otero Navascués y Karl Wirtz, un episodio de las relaciones internacionales de la Junta de Energía Nuclear

    Directory of Open Access Journals (Sweden)

    Presas i Puig, Albert

    2000-12-01

    Full Text Available Not available

    Es una idea compartida que durante el primer franquismo la ciencia española padeció el mismo aislamiento que el resto de la sociedad civil. Al igual que en otros sistemas totalitarios, la labor científica estaba determinada por las purgas ideológicas, el oportunismo político y la inercia de actitudes rutinarias. Pero también es cierto que hubo espacio para propuestas innovadoras y generadoras de nuevas tendencias equiparables a los estandares internacionales. La correspondencia entre José M. Otero y Karl Wirtz se concentra en la década de los años 50 y muestra cómo junto al discurso autoritario habían iniciativas empeñadas en conectar con las tendencias más modernas, en este caso de la investigación nuclear.

  8. Problems to be Expected in Disposing of Fission Products from a Possible Nuclear Power Programme; Problemes Eventuels d'Elimination des Produits de Fission dans les Futures Centrales Nucleaires; 0412 0415 0420 041e 042f 0414 ; Problemas que Puede Plantear la Evacuacion de Productos de Fision Resultantes de la Ejecucion de un Programa de Produccion de Energia de Origen Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dickson, G. K. [Cenral Technical Services, Engineering and Development Group, United Kingdom Atomic Energy Authority, Risley (United Kingdom)

    1960-07-01

    typical British nuclear power programme covering the next few decades is examined. The types of reactor to be erected and the types of fuel to be initially used in them are well appreciated but of course the author's conclusions will necessarily become less certain with the passage of time. The chemical processes which must be applied to irradiated fuels will depend on the type of fuel, its burn-up etc., and so will change during the period under review. Consideration is therefore given to the quantities of fission products and heavy isotopes which may be produced, the forms in which they may leave the chemical processing streams and the methods available for handling them safely, either by storage or by disposal. (author) [French] L'auteur examine un programme d'energie nucleaire caracteristique pour la Grande-Bretagne et s'etendant sur les prochaines decennies. Il donne une evaluation fort judicieuse des types de reacteurs dont la construction est envisagee et des genres de combustibles qu'il est question d'y utiliser pendant la periode initiale; toutefois, ses conclusions auront avec le temps de moins en moins de valeur. En effet, le traitement chimique auquel on devra soumettre le combustible irradie depend du genre de ce dernier, de son taux de combustion, etc.; il subira inevitablement des modifications au cours de la periode consideree. L'auteur tient donc compte des quantites de produits fissiles et d'isotopes lourds qu'il sera possible de produire, des formes sous lesquelles ils pourront se presenter a la fin du traitement chimique et des methodes existantes permettant d'assurer leur manipulation sans danger en vue de leur stockage ou de leur elimination. (author) [Spanish] Esta memoria estudia un programa britanico caracteristico de produccion de energia nuclear que cubre las proximas decadas. Se sabe con bastante certeza que tipos de reactores se construiran y el tipo de combustible que se empleara en ellos en un principio, pero estos conocimientos son

  9. Information to the public on risk prevention arising from energy production in nuclear power plants; Informacion al publico sobre prevencion de riesgos en la produccion de energia nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Giannangeli, C A; Bermudez, L A; Sanchez, R A [Nucleoelectrica Argentina SA (NASA), Buenos Aires (Argentina)

    1999-12-31

    Full text: The lack of knowledge about ionizing radiation and the fear connected with their pacific applications, is a matchless fact, which is relevant in our society, promoting and important controversy. Several origin lines meet in this point: non pacific uses of nuclear energy, Chernobyl accident, final disposal of radioactive wastes, and manipulation of information against nuclear power. They are based on emotional strategies, producing a detriment in the value of impartial information, which lays in a secondary place. The aim of this paper is to analyze the conditions of a communication process, to transmit objective information about radiation, in different levels of reception, and present guide lines to socially relevant institutions, including physicians and health stations as well as public in general, in terms of training and contacts with groups closely related with radiation knowledge. To do this, a survey in a radius of 50 km around the nuclear stations to determine the factors affecting the perception of radiation risks was carried out. The results showed three outstanding factors: `fear`, `ignorance` and `exposed population` with different points of view related to the social context and individual characteristics of surveyed people. Within this framework, a health system for radiological events in three level of organization, as well as training programs and evaluation of the systems to face such events, is published. (author) [Espanol] Texto completo: El desconocimiento en torno a las radiaciones ionizantes y el temor que genera su uso pacifico, es un hecho incontrastable y evidenciable en nuestra sociedad, provocando un debate relevante. Convergen en este punto varias lineas de causalidad: la utilizacion belica de la energia nuclear, el accidente de Chernobyl, el destino de los residuos radiactivos, y la manipulacion de la informacion basada en una estrategia emocional, produciendose un detrimento en el valor de la informacion imparcial, que

  10. The development and work of the Centro de Energia Nuclear na Agricultura (CENA) in Piracicaba

    International Nuclear Information System (INIS)

    Cervellini, A.; Vose, P.B.

    1976-01-01

    CENA is organized in five major divisions: Plant Sciences (biochemistry, pathology, nutrition, radiogenetics and plant breeding, entomology). Animal Sciences, Soil Sciences (fertility, physics, chemistry, microbiology), Environmental Sciences (hydrology, stable isotopes), and Basic Sciences (analytical chemistry and radioprotection). The main projects are focussed on some of the greatest problems in Brazilian agriculture: water resources in Amazonia and the North East region; genetic improvement of basic crops such as beans, rice and wheat; methods for potential reduction in losses of stored grain; improved fertilizer practices and the biological fixation of nitrogen; protein quality and photosynthetic efficiency; mineral deficiency in livestock. In radiation mutation breeding, important successes have been achieved with beans (Phaseolus). Varieties are coming forward promising a yield potential substantially higher than existing varieties. Limited multiplication and testing should be possible later this year. Differences in protein content of several per cent have also been found. A mutant tolerant to Golden Mosaic disease has been obtained, and seed supplied to CIAT (Centro Internacional de Agriculture Tropical, Cali, Columbia) and five countries in South Central America. This was the result of screening some 750 M-progenies comprising 15000 plants in collaboration with the Virology Department of the Institute of Agronomy, Campinas. It should be seen in the perspective of 5000 lines from spontaneous collections having been tested in Central and South America without any tolerance being found. Limited mutation breeding with wheat and rice has produced wheat mutants more resistant to rust and also with shorter straw. Rice mutant lines maturing two weeks earlier and with shortened straw have been obtained

  11. Sistema de Monitoreo Electrónico de Desplazamiento de Tubos de Extensión para Junta Expansiva

    Directory of Open Access Journals (Sweden)

    J. Campuzano-Cervantes

    2017-07-01

    Full Text Available Resumen: En este trabajo se plantea el desarrollo de un dispositivo, llamado junta expansiva, para mitigar la ruptura de tuberías para el transporte de hidrocarburos, causada por deslizamientos de tierra o dilatación lineal. La solución propuesta, involucra el desplazamiento de 2 tubos que alargan el dispositivo, aliviando la tensión y retardando la ruptura de la tubería. La medida del desplazamiento de esos tubos, requiere ser monitoreada para determinar qué tan pronto ocurrirá la ruptura y emprender las acciones correctivas para evitar el derramamiento del hidrocarburo, razón por la que se plantea este sistema de monitoreo electrónico con interfaz gráfica de usuario que facilita la visualización del desplazamiento de manera remota. De esta forma se complementa la junta expansiva y se ofrece la posibilidad al operador de mantenimiento de la tubería monitoreada, de reaccionar a tiempo. Las pruebas ejecutadas mostraron la funcionalidad del sistema de monitoreo propuesto en la junta expansiva. Abstract: In this work the development of a device, called an expansion joint, is proposed to mitigate the rupture of pipelines for the transportation of hydrocarbons, caused by landslides or linear expansion. Proposed solution involves the displacement of two tubes which extend the device, relieving tension and slowing the rupture of the pipe. The measurement of displacement needs to be monitored to determine how soon the rupture occur and take corrective actions to prevent spillage of hydrocarbons. Then, a system of electronic monitoring with graphical user interface that facilitates the visualization of displacement remotely is proposed, complementing the expansion joint. Operators can maintain the monitored pipe and react in time. The tests performed showed the functionality of the proposed system in the expansion joint. Palabras clave: Junta expansiva, sistema de control monitoreado, transporte de hidrocarburos, tuberías, interfaz gr

  12. Designing a mini subcritical nuclear reactor; Diseno de un mini reactor nuclear subcritico

    Energy Technology Data Exchange (ETDEWEB)

    Escobedo G, C. R.; Vega C, H. R.; Davila H, V. M., E-mail: rafelaescobedo@hotmail.com [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Jardin Juarez 147, Col. Centro, 98000 Zacatecas, Zac. (Mexico)

    2015-10-15

    In this work the design of a mini subcritical nuclear reactor formed by means of light water moderator, uranium as fuel, and isotopic neutron source of {sup 239}PuBe was carried out. The design was done by Monte Carlo methods with the code MCNP5 in which uranium was modeled in an array of concentric holes cylinders of 8.5, 14.5, 20.5, 26.5, 32.5 cm of internal radius and 3 cm of thickness, 36 cm of height. Different models were made from a single fuel cylinder (natural uranium) to five. The neutron source of {sup 239}PuBe was situated in the center of the mini reactor; in each arrangement was used water as moderator. Cross sections libraries Endf/Vi were used and the number of stories was large enough to ensure less uncertainty than 3%. For each case the effective multiplication factor k{sub e}-f{sub f}, the amplification factor and the power was calculated. Outside the mini reactor the ambient dose equivalent H (10) was calculated for different cases. The value of k{sub eff}, the amplification factor and power are directly related to the number of cylinders of uranium as fuel. Although the average energy of the neutrons {sup 239}PuBe is between 4.5 and 5 MeV in the case of the mini reactor for a cylinder, in the neutron spectrum the presence of thermal neutrons does not exist, so that produced fissions are generated with fast neutrons, and in designs of two and three rings the neutron spectra shows the presence of thermal neutrons, however the fissions are being generated with fast neutrons. Finally in the four and five cases the amount of moderator is enough to thermalized the neutrons and thereby produce the fission. The maximum value for k{sub eff} was 0.82; this value is very close to the assembly of Universidad Autonoma de Zacatecas generating a k{sub eff} of 0.86. According to the safety and radiation protection standards for the design of mini reactor of one, two and three cylinders they comply with the established safety, while designs of four and five

  13. Intelligent use of the energy; Uso inteligente de la energia

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez Ahedo, Carlos [Director General de la Comision Nacional para el Ahorro de Energia (CONAE), Mexico D. F. (Mexico)

    2005-07-01

    Comision Nacional para el Ahorro de Energia (CONAE) is an administrative agency independent of the Secretaria de Energia that serves as a technical agency for consultancy in matters of efficient use of energy and advantageous use of renewable energies. This document searches to inform the population how to satisfy the necessity of energy in an intelligent way. For this purpose some useful actions to be performed were detected: the making of a balance between the supply and the energy demand, the consultancy on how the saving of energy is performed in order to reduce its waste, to count on equipment and efficient systems, to use domestic renewable energies and to use the solar energy and the biomass. [Spanish] La Comision Nacional para el Ahorro de Energia (CONAE) es el organo administrativo desconcentrado de la Secretaria de Energia que funge como organismo tecnico de consulta en materia de ahorro y uso eficiente de energia y aprovechamiento de energias renovables. Este documento busca informar a la poblacion acerca de como satisfacer la necesidad de energia a cambio de su utilizacion de manera inteligente, para ello se detectaron areas de oportunidad como: un balance entre la oferta y la demanda energetica, informar a la gente sobre como se efectua el ahorro de energia para con ello reducir el desperdicio de esta, contar con equipos y sistemas eficientes, usar energias renovables domesticas y utilizar la energia solar y la biomasa.

  14. Welding with the TIG automatic process of the end fittings for the execution of the Embalse nuclear power plant fuel channel rechange; Soldadura con proceso TIG automatico de los accesorios extremos (end fitting) para la ejecucion de un recambio de canal de combustible en el reactor de la Central Nuclear Embalse

    Energy Technology Data Exchange (ETDEWEB)

    Suarez, P O

    1991-12-31

    The present work describes the methodology for the cutting of the existing welding and subsequent welding applied by the TIG process of the coupling composed by the shroud ring and the end fitting ring from one of Embalse nuclear power plant`s fuel channels. The replacement will be previously determined by the SLAR-ETTE mechanism where a displacement operated among the Gartner Spring rings, the pressure tubes are separated from the Calandria tubes. The welding to be carried out has the function of stamping the CO{sub 2} annular gas (thermal insulator) circulating between the pressure tube and the Calandria one during the functioning of the plant. (Author). [Espanol] El presente trabajo describe la metodologia de corte de la soldadura existente y la posterior soldadura aplicada mediante proceso TIG de la junta compuesta por el aro de fuelle y el anillo del `end fitting`, de uno de los canales de combustibles del reactor de la Central Nuclear Embalse. El reemplazo, se determinara previamente mediante el mecanismo de SLAR-ETTE con lo cual se observara el desplazamiento operado entre los anillos garten spring que separan los tubos de presion de los tubos de calandria. La soldadura a efectuar cumple la funcion de sellar el gas anular CO{sub 2} (aislante termico) circulante entre el tubo de presion y el tubo de calandria durante el funcionamiento de la planta. (Autor).

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  16. Probabilistic analysis of safety of a production plant of hydrogen using nuclear energy; Analisis probabilistico de seguridad de una planta de produccion de hidrogeno utilizando energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Flores F, A. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico); Nelson E, P.F.; Francois L, J.L. [Facultad de Ingenieria, UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)]. e-mail: alain_fyf@yahoo.com

    2005-07-01

    The present work makes use of the Probabilistic Safety analysis to evaluate and to quantify the safety in a plant producer of hydrogen coupled to a nuclear reactor of high temperature, the one which is building in Japan. It is had the description of systems and devices of the HTTR, the pipe diagrams and instrumentation of the plant, as well as the rates of generic faults for the components of the plant. The first step was to carry out a HAZOP study (Hazard and Operability Study) with the purpose of obtaining the initiator events; once obtained these, it was developed a tree of events by each initiator event and for each system it was developed a fault tree; the data used for the quantification of the failure probability of the systems were obtained starting from several generic sources of information. In each tree of events different final states were obtained and it stops each one, their occurrence frequency. The construction and evaluation of the tree of events and of failures one carries out with the SAPHIRE program. The results show the safety of the shutdown system of the HTTR and they allow to suggest modifications to the auxiliary system of refrigeration and to the heat exchanger helium/water pressurized. (Author)

  17. Decree No. 2967 of 7 December 1979 on the regulation of activities in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1980-01-01

    Within the framework of the national energy plan, and for the purpose of ensuring the supply of uranium for nuclear power plants in Spain, this Decree reorganises and develops the duties and responsibilities of the National Uranium Undertaking (ENUSA) set up by Decree No. 3322 of 23 December 1971. ENUSA is a public undertaking, wholly controlled by the State, with a majority capital held by the National Institute for Industry and participation by the Junta de Energia Nuclear, which advises it in connection with research and development. ENUSA is responsible for the development of industrial and commercial activities related to the nuclear fuel cycle. While the Junta de Energia Nuclear remains responsible for final storage of radioactive waste, ENUSA is henceforth in charge of other activities in execution of the national plan for prospection for and investigation of uranium. (NEA) [fr

  18. A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mundim, Sergio Gorretta

    1971-02-15

    The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

  19. A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mundim, Sergio Gorretta

    1971-02-15

    The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

  20. The peaceful use of nuclear energy: National legal implications; El uso pacifico de la energia nuclear: implicaciones juridicas nacionales

    Energy Technology Data Exchange (ETDEWEB)

    Guadarrama A, M E

    2000-07-01

    This work analyses in broad sense the legal regime about the use, exploitation and improvement of the nuclear energy in Mexico and its relationship with the International confines . It was realized the study of the elemental concepts referred about the subject and it is described briefly the evolution of the figure in the frame of as National as International laws. The objective of this work finds its basis on the provisions which contemplate the in force statutory law of the 27 Constitutional article concerning Nuclear energy but before considering the legal nature and the main characteristics of this normative instrument. (Author)

  1. Nuclear Data for Safe Operation and Waste Transmutation: ANDES (Accurate Nuclear Data for nuclear Energy Sustainability); Datos nucleares para la operacion segura y la transmutacion de residuos: Andes (Datos Nucleares Precisos para la Sostenibilidad de la Energia Nuclear)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, E. M.

    2014-07-01

    Nuclear research within the 7th Framework Program (FP7 and FP7+2) of EURATOM has devoted a significant fraction of its efforts to the development of advanced nuclear fuel cycles and reactor concepts, mainly fast reactors, aiming to improve the long term sustainability by reduction of the final wastes, optimal use of natural resources and improvement of safety in the present and future nuclear installations. The new design need more accurate basic nuclear data for isotopes, like minor actinides, potentially playing an important role in the operation, fuel concept, safety or final wastes of those reactors and fuel cycles. Four projects, ANDES, ERINDA, EUFRAT and CHANDA, supported by EURATOM within the FP7 and FP7+2, have put together most of the European Nuclear Data community to respond efficiently and in a coordinated way to those needs. This paper summarizes the objectives, and main achievements of ANDES, the project responsible for most of the measurements and technical achievements that was coordinated by CIEMAT. Indeed, CIEMAT has coordinated the nuclear data R and D projects within EURATOM during the last 7 years (NUDATRA domain of EUROTRANS, and ANDES) and will continue this coordination in the CHANDA project till 2017. (Author)

  2. [Genetics and the Junta para Ampliación de Estudios e Investigaciones Científicas].

    Science.gov (United States)

    Peláez, Raquel Alvarez

    2007-01-01

    The aim of this paper is to show the essential paper developed by the Junta para Ampliación de Estudios in the origin of the Spanish genetics, using for that the most relevant researchers of the time, and between them two women, Jimena Fernández de la Vega and Käte Pariser.

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  4. Use of hafnium in control bars of nuclear reactors; Uso de hafnio en barras de control de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J.R.; Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: jrrs@nuclear.inin-mx

    2003-07-01

    Recently the use of hafnium as neutron absorber material in nuclear reactors has been reason of investigation by virtue of that this material has nuclear properties as to the neutrons absorption and structural that can prolong the useful life of the control mechanisms of the nuclear reactors. In this work some of those more significant hafnium properties are presented like nuclear material. Also there are presented calculations carried out with the HELIOS code for fuel cells of uranium oxide and of uranium and plutonium mixed oxides under controlled conditions with conventional bars of boron carbide and also with similar bars to which are substituted the absorbent material by metallic hafnium, the results are presented in this work. (Author)

  5. Las juntas directivas en la capitalización de empresas en Colombia para el periodo 1956-1973

    OpenAIRE

    Castellanos Cabrera, Germán Andrés

    2015-01-01

    El presente documento realiza una descripción de como estaban estructuradas las juntas directivas de las principales empresas del país para el periodo de 1956 a 1957. De manera simultánea, se lleva a cabo un cuidadoso análisis, junto con un ejercicio comparativo, de si estas estructuras estaban en acorde a lo que sugiere la literatura acerca de la Gobernanza Corporativa.

  6. Juntas de Vecinos: Características y alcances de la participación social en organizaciones comunitarias territoriales.

    Directory of Open Access Journals (Sweden)

    Ignacio José Rojas Dunlop

    2014-12-01

    Full Text Available El presente artículo consiste en la exposición de los resultados de una investigación etnográfica acerca de las características y alcances de la participación social que se da a partir de la membresía en organizaciones comunitarias territoriales: las juntas de vecinos. Previa exposición de los resultados propiamente tales, cabe señalar, se presenta una problematización, a modo de introducción, de los temas a tratar, una discusión conceptual y una breve referencia metodológica. Se sostiene que existen dos objetivos que tendrían las juntas de vecinos: uno explícito, relativo a la solución de problemas que aquejen al territorio que representan, y sus habitantes, y otro implícito, relacionado a un rol integrador que cumplirían en él. Para darles cumplimiento realizan distintos modos de participación ciudadana y comunitaria. En el primer caso, se da, mayormente, una participación instrumental, y en el segundo una participación pasiva, no precisamente comunitaria. Aun así, no se cree que exista modo unívoco de caracterizar la participación en juntas de vecinos, ya que esta adquiere diversas formas y alcances según diversos factores, tales como las actividades que realicen, las voluntades, capacidades, etc., de sus dirigentes, de las autoridades comunales, de sus socios, etc. Lo cierto es que dadas las condiciones estructurales actuales existen pocas posibilidades de que sea una participación empoderada y convocante.

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  8. Nuclear Power and Sustainable Development (Spanish Edition); Energia Nucleoelectrica y Desarrollo Sostenible

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-02-15

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible [Spanish] En cualquier analisis de las tendencias energeticas del siglo XXI hay que tomar en cuenta el desequilibrio energetico mundial. Aproximadamente 1 600 millones de persona aun no tienen acceso a servicios energeticos modernos, y pocos aspectos del desarrollo - ya se trate de los niveles de vida, la atencion sanitaria o la productividad industrial - pueden conseguirse sin el necesario suministro de energia. Si consideramos el siglo que tenemos por delante, vemos que el crecimiento de la demanda energetica sera sustancial y que una clave del progreso consistira en 'conectar a los que carecen de conexion'. Otro desafio sera la sostenibilidad. Como podemos satisfacer estas necesidades

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  11. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  12. [Neurocience in the Junta para Ampliación de Estudios].

    Science.gov (United States)

    Díaz, Alfredo Baratas

    2007-01-01

    The development of the Neurociencias in the Spain at the first third of the 20th century had a strong histological and pathological component. The work of Santiago Ramon and Cajal and Luis Simarro was continued by some excellent disciples: Nicolas Achúcarro, Gonzalo Rodriguez Lafora, Fernando de Castro, etc. Some of them had to make compatible diverse occupations, even the professional exercise of psychiatry, before obtaining a modest - but stable - position of investigation. In spite of some misalignments in the institutional development of the centers and the personal biographical ups and downs, the Junta para Ampliación de Estudios was the great institution that fomented the international formation of the investigators and equipped to them with the means to develop its work.

  13. Review of experience gained in fabricating nuclear grade uranium and thorium compounds and their analytical quality control at the Instituto de Energia Atomica, Sao Paulo, Brazil

    International Nuclear Information System (INIS)

    Abrao, A.; Franca, J.M. Jr.; Ikuta, A.; Pueschel, C.R.; Federgruen, L.; Lordello, A.R.; Tomida, E.K.; Moraes, S.; Brito, J. de; Gomes, R.P.; Araujo, J.A.; Floh, B.; Matsuda, H.T.

    1977-01-01

    This paper summarizes the main activities dealing with the fabrication of nuclear grade uranium and thorium compounds at the Instituto de Energia Atomica, Sao Paulo. Identification of problems and their resolutions, the experience gained in plant operation, the performance characteristics of an ion-exchange facility and a solvent extraction unit (a demonstration plant based on pulsed columns for purification of uranium and production of ammonium diuranate) are described. A moving-bed facility for UF 4 preparation and its operation is discussed. A pilot plant for uranium and thorium oxide microsphere preparation based on internal gelation for HTGR fuel type is also described. A solvent extraction pilot plant for thorium purification based on a compound extraction-scrubbing column and a mixer-settler battery and the involved technology for thorium purification are commented. The main products, namely ammonium diuranate, uranyl amonium tricarbonate, uranium trioxide, uranium tetrafluoride, thorium nitrate and thorium oxalate and their quality are commented. The development of necessary analytical procedures for the quality control of the mentioned nuclear grade products is summarized. A great majority of such procedures was particularly suitable for analyzing traces impurities. Designed for installation are the units for denitration of uranyl nitrate solutions and pilot plants for elemental fluorine and UF 6 . The installation of a laboratory-scale plant designed for reprocessing irradiated uranium and an experimental unit for the recovery of protactinium from irradiated thorium is in progress

  14. Ordens militares de cavalaria de Portugal

    Directory of Open Access Journals (Sweden)

    Álvaro da Veiga Coimbra

    1963-03-01

    Full Text Available Falar nas Ordens Militares de Cavalaria de Portugal, é ter presente a própria história da fundação da monarquia e de re-cuperação territorial e também dos descobrimentos de novos mundos para a civilização. Aos seus cavaleiros couberam no cenário das lutas sangrentas e constantes da dinastia afonsina, os grandes postos da vanguarda.

  15. Economic Aspects of Air and Gas Cleaning for Nuclear Energy Processes; Aspects Economiques de l'Epuration de l'Air et des Gaz au Cours des Operations Nucleaires; 042d 041a 041e 041d 041e 0414 0; Aspectos Economicos de la Depuracion del Aire y de los Gases en los Procesos de Obtencion de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, Leslie [Harvard School of Public Health, Boston, MA (United States)

    1960-07-01

    In this paper the basic requirements for control of gaseous and particulate effluents are given as applied to problems of feed material production, isotope separation, fuel element fabrication, fuel recovery and reactor operation. There are also instances where non-radioactive nuclear materials with toxic or nuisance effluents such as from beryllium and zirconium production are of concern and these too must be controlled at reasonable costs. The factors involved in capital and operating costs of gas cleaning equipment and the types of applications in the United States are described in some detail. Gaseous effluent problems have, of course, been attacked and controlled by several types of device but their performance has been measured on a comparable basis. It is thus possible to judge operating characteristics on an economic basis as related to power consumption, adsorbent costs, space charges, corrosion problems and other operational factors. The United States Atomic Energy Commission through its contract with the Harvard University Air Cleaning Laboratory has initiated an evaluation program with cooperation, from the various facilities and contractors to the Commission. In this study the basic factors necessary to obtain quantitative cost delineation and evaluation have been outlined and some preliminary findings will be presented. The paper also presents a review of other economic studies made in the United States on particular process or facility applications. (author) [French] Le memoire definit les regles fondamentales auxquelles doit obeir le controle des effluents gazeux et particulaires dans les domaines suivants : production des matieres destinees a alimenter les reacteurs, separation des isotopes, fabrication des cartouches de combustible, recuperation du combustible et fonctionnement des reacteurs. De plus - et c'est notamment ce qui se passe avec la production de beryllium et de zirconium -- il y a des cas ou des matieres nucleaires non radioactives

  16. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F; George, B V; Baglin, C J

    1978-05-10

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given.

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

    Purpose: To improve the nuclear reactor availability by enabling to continuously exchange fuels in the natural-slightly enriched uranium region during operation. Constitution: A control rod is withdrawn to the midway of a highly enriched uranium region by means of control rod drives and the highly enriched uranium region is burnt to maintain the nuclear reactor always at a critical state. At the same time, fresh uranium-slightly enriched uranium is continuously supplied gravitationally from a fresh fuel reservoir through fuel reservoir to each of fuel pipes in the natural-slightly enriched uranium region. Then, spent fuels reduced with the reactivity by the burn up are successively taken out from the bottom of each of the fuel pipes through an exit duct and a solenoid valve to the inside of a spent fuel reservoir and the burn up in the natural-slightly enriched uranium region is conducted continuously. (Kawakami, Y.)

  19. Nuclear energy - some aspects; Energia nuclear - alguns aspectos

    Energy Technology Data Exchange (ETDEWEB)

    Bandeira, Fausto de Paula Menezes

    2005-05-15

    This work presents a brief history of research and development concerning to nuclear technology worldwide and in Brazil, also information about radiations and radioactive elements as well; the nuclear technology applications; nuclear reactor types and functioning of thermonuclear power plants; the number of existing nuclear power plants; the nuclear hazards occurred; the national fiscalization of nuclear sector; the Brazilian legislation in effect and the propositions under proceduring at House of Representatives related to the nuclear energy.

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Humphreys, P.; Davidson, D.F.; Thatcher, G.

    1980-01-01

    The cooling system of a liquid metal cooled fast breeder nuclear reactor of the pool kind is described. It has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump. (author)

  1. Radiation hazard surveillance in spanish uranium mines; Control de los peligros de la radiactividad en las minas de uranio espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Iranzo, E; Liarte, J

    1963-07-01

    The regulations applied in the uranium mines which belong to the Junta de Energia Nuclear to control the radioactive hazards, and to get the personal protection avoiding overexposures in the external radiation and inhalation of radioactive dust and gases are given. The Radon daughters concentration in the atmosphere of Avery one of the mines and the external radiation exposure and uranium excretion in urine of the miners during 1962 are specified. (Author) 9 refs.

  2. Presiones medidas en la base de una losa de fondo con juntas paralelas al flujo en un canal

    Directory of Open Access Journals (Sweden)

    Edwin Hurtado Orobio

    2009-01-01

    Full Text Available Se estudió si las aristas traseras de las juntas longitudinales de una losa de piso, fija al fondo de un canal con flujo supercrítico, convierten energía cinética en energía de presión en el rango de números de Froude de 2,84 a 10,12. En cada prueba, se midió la presión en 16 puntos de su cara inferior, con transductores piezoresistivos en tres líneas longitudinales: una central con 8 sensores y dos laterales, a lado y lado de la primera, con cuatro sensores cada una. De esta forma, se determinó la distribución de las presiones medias debajo de la losa ensayada, similar a las usadas en obras civiles para evitar la acción erosiva de la turbulencia de un flujo supercrítico. El análisis de las presiones medidas muestra que, aún cuando las caras superiores del piso del canal y del bloque protector estén en el mismo plano horizontal, las aristas traseras de las juntas longitudinales transforman energía de velocidad en energía de presión. Así, se ha detectado un factor que interviene en la generación de la fuerza hidrodinámica que levanta revestimientos de diverso tipos de estructuras, hasta ahora ignorado en el estudio de este problema.

  3. Energy from nuclear reactors

    International Nuclear Information System (INIS)

    Hospe, J.

    1977-01-01

    This VDI-Nachrichten series has the target to provide a technical-objective basis for the discussion of the pros and cons of nuclear power. The first part deals with LWR-type reactors which so far have prevailed in nuclear power generation. (orig.) [de

  4. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  6. Application of a Russian nuclear reactor simulator VVER-1000; Aplicacion de un simulador de reactor nuclear ruso VVER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Lopez-Peniche S, A. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04360 Mexico D. F. (Mexico); Salazar S, E., E-mail: alpsordo@hotmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2012-10-15

    The objective of the present work is to give to know the most important characteristics in the Russian nuclear reactor of pressurized light water VVER-1000, doing emphasis in the differences that has with the western equivalent the reactor PWR in the design and the safety systems. Therefore, a description of the computerized simulation of the reactor VVER-1000 developed by the company Eniko TSO that the International Atomic of Energy Agency distributes to the states members with academic purposes will take place. The simulator includes mathematical models that represent to the essential systems in the real nuclear power plant, for what is possible to reproduce common faults and transitory characteristic of the nuclear industry with a behavior sufficiently attached to the reality. In this work is analyzed the response of the system before a turbine shot. After the accident in the nuclear power plant of Three Mile Island (US) they have been carried out improvements in the design of the reactor PWR and their safety systems. To know the reach and the limitations of the program, the events that gave place to this accident will be reproduced in the simulator VVER-1000. With base to the results of the simulation we will conclude that so reliable is the response of the safety system of this reactor. (Author)

  7. The Nuclear Energy Agency of the OECD through its history; La Agencia de Energia Nuclear de la OCDE, a traves de su historia

    Energy Technology Data Exchange (ETDEWEB)

    Echavarri, L.

    2008-07-01

    This year, 2008, marks the 50th Anniversary of the OECD Nuclear Energy Agency (NEA). During these years the Agency has adapted to the evolution of the world energy situation. At the beginning the Agency launches international collaboration projects to establish the technological bases required for nuclear energy, then helps member countries in the construction of nuclear power plants and later analyzes the safety criteria as a consequence of the Three Miles Island and Chernobyl accidents. Based on this experience, the NEA faces the X XI Century prepared to contribute, even more, to a better international collaboration for a safe, environmentally friendly and economical use of the nuclear energy. (Author)

  8. Regulations of local choices for installation of power reactors

    International Nuclear Information System (INIS)

    1969-09-01

    The present regulations specify the criteria under which the Comissao Nacional de Energia Nuclear will approve the local proposed for the installation of power reactors, according to his attributions established in the Law 4118, dated of August 27, 1962

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

    Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

    A nuclear reactor has an upper and a lower grid plate. Protrusions project from the upper grid plate. Fuel assemblies having end fittings fit between the grid plates. An arrangement is provided for accepting axial forces generated during the operation of the nuclear reactor by the flow of the cooling medium and thermal expansion and irradiation-induced growth of the fuel assembly, which comprises rods. Each fuel assembly rests on the lower grid plate and its upper end is elastically supported against the upper grid plate by the above-mentioned arrangement. The arrangement comprises four (for example) torsion springs each having a torsion tube and a torsion bar nested within the torsion tube and connected at one end thereto. The other end of the torsion bar is connected to an associated one of four lever arms. The torsion tube is rigidly connected to the other end fitting and the springs are disposed such that the lever arms are biassed against the protrusions. (author)

  11. GESTIÓN POR COMPETENCIAS PARA LOS DIRIGENTES DE LA JUNTA DE VECINOS: Experiencia de practica profesional

    Directory of Open Access Journals (Sweden)

    Carolina González Urrutia

    2007-01-01

    Full Text Available El presente trabajo se basa en una sistematización de la experiencia de práctica profesional, en la cu al se realizó la aplicación de un modelo nacido desde la Psicología Organizacional a un contexto netamente comunitario. Además, se proyectó desde la Dirección de Desarrollo Comunitario de la Municipalidad de Pelarco, la que se caracteriza por representar a una población altamente rural. Esta actividad se realizó con el fin de promover la part icipación de las personas en sus organizaciones, privilegiando que ésta sea de carácter más activo e involucrándose en sus problemáticas más inmediatas. Para esto, se realizó una adaptación de l procedimiento propuesto por Llopart & Redondo (1997, en base a lo cual se elaboró primeramente u n perfil por competencias contextualizado a la realidad de los dirigentes de las Juntas Vecinales de Pelarco. Posteriormente, se elaboró un sistema para evaluarlas con el que se identificó la compete ncia que presentaba un nivel más bajo. En base a esta, se elaboró una intervención que fue ejecutada satisfactoriamente y además evaluada en varios niveles.

  12. The ‘Junta de Dependencias de Extranjeros’ (1714-1800: The socio-political background of a historical institution

    Directory of Open Access Journals (Sweden)

    Ana Crespo Solana

    2009-08-01

    Full Text Available This paper sets out to analyze the Junta de Dependencia de Extranjeros, an institution that was created within the framework of the government reforms that characterized the reign of Phillip V after the war of Spanish succession in order to monitor and control the activity of foreign merchants settled in numerous Spanish cities. During its operative period this institution developed a strong links and effective lines of communication with foreign merchant communities resident in Spain. This study is based on primary sources such as the documentation generated by the Junta, which included requests and complaints lodged by merchants and merchant communities as well as reports on the appointment of foreign consuls. These sources are preserved in the State sections of the Archivo Histórico Nacional de Madrid and the Archivo General de Simancas. The correspondence of the representatives of merchant communities in Spain has also been used, as well as affidavits and population censuses preserved in the Provincial Archives of Madrid, Cadiz and Murcia. These sources have been interrogated in order to establish the stances and discourses adopted by both the Spanish government and the foreign merchants settled in those cities that sent representatives to the offices of Spain’s central government. The requests and complaints filed by foreign merchants and consuls in this context demonstrate the strength of their communities, which had been granted substantial privileges during the second half of the seventeenth century, and to which the Junta responded with a high degree of understanding. The Junta’s conciliatory stance was linked not only to pressure exerted by foreign ambassadors, but also to limitations established by the peace treaties signed by Spain. The Junta de Dependencia de Extranjeros clearly adopted a radically different position to that of Charles II’s fiercely protectionist government, and generally responded favourably to requests from

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

    The support grid for the fuel rods of a liquid metal cooled fast breeder reactor has a regular hexagonal contour and contains a large number of unit cells arranged honeycomb fashion. The totality of these cells make up a hexagonal shape. The grid contains a number of strips of material, and there is a window in each of three sidewalls staggered by one sidewall. The other sidewalls have embossed protrusions, thus generating a guide lining or guide bead. The windows reduce the rigidity of the areas in the middle between the ends of the cells. (DG) [de

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

    Between a PWR's reactor pressure vessel made of steel and the biological shield made of concrete there is a gap. This gap is filled up with a heat insulation facting the reactor pressure vessel, for example with insulating concrete segments jacketed with sheet steel and with an additional layer. This layer serves for smooth absorption of compressive forces originating in radial direction from the reactor pressure vessel. It consists of cylinder-segment shaped bricks made of on situ concrete, for instance. The bricks have cooling agent ports in one or several rows which run parallel to the wall of the pressure vessel and in alignment with superposed bricks. Between the layer of bricks and the biological shield or rather the heat insulation, there are joints which are filled, however, with injected mortar. That guarantees a smooth series of connected components resistant tom compression. Besides, a slip foil can be set between the heat insulation and the joining joint filled with mortar for the reduction of the friction at thermal expansions. (TK) [de

  15. Production and sharing of the nuclear knowledge: knowledge management at the Radiopharmaceutical Division of the Instituto de Engenharia Nuclear of Brazilian CNEN; Produção e compartilhamento do conhecimento nuclear: a gestão do conhecimento na Divisão de Radiofármacos do Instituto de Engenharia Nuclear da Comissão Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bettencourt, Marcia Pires da Luz

    2011-07-01

    The Brazilian nuclear area made great progress in recent years, bringing many benefits to society, not only in producing electric power, but also in agriculture, industry and medicine. One of the problems in this area, nowadays, is the risk losing nuclear knowledge. Although it is difficult to understand how knowledge is created and used, can be seen that the sharing and production are influenced by some factors that provide favorable conditions. This research focused its attention on identifying actions that contribute to the production and sharing of knowledge and information at the Divisão de Radiofármacos of Instituto de Engenharia Nuclear of Comissão Nacional de Energia Nuclear (IEN/CNEN). Knowledge management was chosen as a tool to study the problem identified, because it has methodologies aimed at stimulating the knowledge production process and knowledge and information sharing, both in private companies and public institutions, such as IEN/CNEN. Knowledge management is an interdisciplinary relatively new discipline, and although it had not been born in Information Science, there has been seeking theoretical support and legitimacy at this interdisciplinary science. This research conceptualizes, historically contextualizes and analyzes developments and trends in knowledge management. The study discourses on the peculiarities and aspects in common between the knowledge management and information management and identifies factors that influence the sharing of information and knowledge such as: social networks, communities of practice, collaborative spaces, organizational culture, organizational learning, and storytelling. In reviewing the literature and after data analysis of interviews, some actions have been identified, and it was possible to make some suggestions. It is concluded that institutional incentive for collaboration and knowledge sharing can influence positive results and increase the production of new knowledge. (author)

  16. Behavior of the Energy Secretary in working matter: the case of workers exposed to nuclear energy (ionizing radiations); Actuacion de la Secretaria de Energia en materia laboral: el caso de los trabajadores expuestos a energia nuclear (radiaciones ionizantes)

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, G

    2006-07-01

    Mexico, as many other countries, it gives to this energy resource multiple uses in such activities as: the electric power generation in nuclear central, the industry, the medicine and the research. In the one acting of the referred activities intervenes individuals that, in reason of their work, they have contact with this energy type, which is potentially dangerous for the health in reason of the radioactivity flight. Although those workers are 'aided' for a series of relative standards to the observance of safety, hygiene and protection measures in the event of work risks, the technicity that is required to determine the potential risk that it is generated with the handling of radioactive products it makes that single specialized in the matter authorities can evaluate and, therefore, to watch over the safety conditions in those that work is developed. In that virtue, with this investigation it is sought to demonstrate that the Secretary of Energy, through a dis concentrated specialized organ and endowed with technical autonomy denominated National Commission of Nuclear Safety and Safeguards, it is a dependence that in their performance like Regulator Organ in the matter, intervenes in the labor relationships circles, being, therefore, an authority in work matter. By this way, the development of the present study is made in the following manner: In the first chapter indispensable aspects are approached to locate to the authorities inside the mark of the power exercise by the part of the State through their diverse organs; topics like jurisdiction and competition are treated for later to analyze the structure, according to the Mexican Administrative Law, of the Federal Executive Organ, referring a brief analysis of the application of work standards for diverse administrative authorities to determine of their multiple intervention and important performance in the labor relationships. In the second it is analyzed the structure of the National Commission of

  17. Safety Harmonization of Nuclear Reactors in Europe; La armonizacion de la seguridad de los reactores nucleares en Europa

    Energy Technology Data Exchange (ETDEWEB)

    Estevan Bolea, M. T.

    2006-07-01

    Dialogue and common tasks over the past few years have intensified among high level figures responsible for regulation organizations involved in nuclear installations from European countries as well as others. The best indicator of this is the harmonization of safety levels for european nuclear reactors. The CSN increasingly participates more intensely in three relevant international associations on these matters: INRA, FORO IBEROAMERICANO and WENDA. A detail study has been carried out by a WENRA work group whose results represent a large contribution made toward harmonization at reference levels on reactor safety issues, both from a legal viewpoint, and for their implantation in nuclear power plants. The President of the CSN explains in detail the most relevant aspects of this Final Report from WENRA. (Author)

  18. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  19. Nuclear research reactors in Brazil

    International Nuclear Information System (INIS)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias

    2011-01-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  1. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1979-01-01

    In a nuclear reactor (e.g. one having coolant down-flow through a core to a hearth below) thermal insulation (e.g. of a floor of the hearth) comprises a layer of bricks and a layer of tiles thereon, with smaller clearances between the tiles than between the bricks but with the bricks being of reduced cross-section immediately adjacent the tiles so as to be surrounded by interconnected passages, of relatively large dimensions, constituting a continuous chamber extending behind the layer of tiles. By this arrangement, lateral coolant flow in the inter-brick clearances is much reduced. The reactor core is preferably formed of hexagonal columns, supported on diamond-shaped plates each supported on a pillar resting on one of the hearth-floor tiles. Each plate has an internal duct, four upper channels connecting the duct with coolant ducts in four core columns supported by the plate, and lower channels connecting the duct to a downwardly-open recess common to three plates, grouped to form a hexagon, at their mutually-adjacent corners. This provides mixing, and temperature-averaging, of coolant from twelve columns

  2. Neutron analysis of the fuel of high temperature nuclear reactors; Analisis neutronico del combustible de reactores nucleares de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2014-10-15

    In this work a neutron analysis of the fuel of some high temperature nuclear reactors is presented, studying its main features, besides some alternatives of compound fuel by uranium and plutonium, and of coolant: sodium and helium. For this study was necessary the use of a code able to carry out a reliable calculation of the main parameters of the fuel. The use of the Monte Carlo method was convenient to simulate the neutrons transport in the reactor core, which is the base of the Serpent code, with which the calculations will be made for the analysis. (Author)

  3. Vida a la fatiga de juntas soldadas del acero inoxidable AISI 316L obtenidas mediante el proceso GMAW

    Directory of Open Access Journals (Sweden)

    Puchi-Cabrera, E. S.

    2007-06-01

    Full Text Available An investigation has been conducted in order to determine the effect of both the metallic transfer mode (pulsed arc or short circuit and the O2 content in the Ar/O2 gas mixture, of the gas-metal arc welding process (GMAW, on the fatigue life under uniaxial conditions of welded joints of 316L stainless steel. It has been concluded that the mixture of the protective gases employed in the process could have an important influence on the fatigue life of the welded joints of such steel in two different ways. Firstly, through the modification of the radius of curvature at the joint between the welding toe and the base metal and, secondly, through a more pronounced degree of oxidation of the alloying elements induced by a higher O2 content in the mixture. As far as the metallic transfer mode is concerned, it has been determined that the welded joints obtained under a pulsed arc mode show a greater fatigue life in comparison with the joints obtained under short circuit for both gas mixtures.

    Se ha llevado a cabo una investigación con la finalidad de determinar el efecto, tanto del modo de transferencia metálica (arco pulsado o cortocircuito como del contenido de O2 en la mezcla de gases protectores Ar/O2, del proceso de soldadura a tope mediante arco metálico con protección gaseosa (GMAW, sobre la vida a la fatiga en condiciones uniaxiales de juntas soldadas del acero inoxidable AISI 316L. Dicho trabajo ha permitido concluir que la composición de la mezcla de gases protectores del proceso GMAW pudiera tener una influencia importante en la vida a la fatiga de las juntas soldadas de dicho material, a través de dos formas distintas: primero, mediante la modificación del radio de curvatura entre la raíz del cordón de soldadura y el metal base y, en segundo lugar, a través del mayor grado de oxidación de los elementos de aleación. En cuanto al modo de transferencia metálica, se determinó que las juntas soldadas mediante arco pulsado

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Pearson, K.G.

    1977-01-01

    Reference is made to auxiliary means of cooling the nuclear fuel clusters used in light or heavy water cooled nuclear reactors. One method is to provide one or more spray cooling tubes. From holes in the side walls of those tubes coolant water may be sprayed laterally into the cluster against the rods. The flow of main coolant may thus be supplemented or even replaced by the auxiliary coolant. A difficulty, however, is that only those fuel rods close to a spray cooling tube can readily be reached by the auxiliary coolant. In the arrangement described, where the fuel rods are spaced apart by transverse grids, at least one of the interspaces between the grids is provided with an axially extending auxiliary coolant conduit having lateral holes through which an auxiliary coolant is sprayed into the cluster. A deflector is provided that extends from a transverse grid into a position in front of the holes and deflects auxiliary coolant on to parts of the fuel rods otherwise inaccessible to the auxiliary coolant. The construction of the deflector is described. (U.K.)

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  6. Nuclear reactor monitoring system

    International Nuclear Information System (INIS)

    Drummond, C.N.; Bybee, R.T.; Mason, F.L.; Worsham, H.J.

    1976-01-01

    The invention pertains to an improved monitoring system for the neutron flux in a nuclear reactor. It is proposed to combine neutron flux detectors, a thermoelement, and a background radiation detector in one measuring unit. The spatial arrangement of these elements is fixed with great exactness; they are enclosed by an elastic cover and are brought into position in the reactor with the aid of a bent tube. The arrangement has a low failure rate and is easy to maintain. (HP) [de

  7. La Junta de Información en Madrid para las reformas en Las Antillas, 1866

    Directory of Open Access Journals (Sweden)

    M. Dolores Domingo Acebrón

    2002-04-01

    Full Text Available The Junta de Information organised in 1866 by the Spanish authorities brought together in Madrid official representatives and people from the Antilles to discuss an essential topic: the situation of Cuba and Puerto Rico. Their complaints and petitions were specific, leaving no doubt as to what Cubans and Puerto Ricans desired. They wished for, on the one hand, the abolition of slavery, and on the other, greater political freedom: in sum, a series of social, economic and political reforms. In reponse, the Spanish authorities displayed an inflexible and intransigent disposition, which did not help the understanding between Antillas and the Spanish. The Spanish authorities responded by increasing direct taxes and rejecting the abolition of customs. On the political front, Spain maintained its extreme defense of the «statu quo». The commissioners from the Antilles found confirmed in Madrid the metropolis's lack of interest towards Cuban and Puerto Rican problems. The situation became irreversible once the independence movement had begun, wiht the objective of achieving freedom from Spanish colonialism.

  8. Methodology for the integral comparison of nuclear reactors: selecting a reactor for Mexico; Metodologia para la comparacion integral de reactores nucleares: seleccion de un reactor para Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Reyes R, R.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: ricarera@yahoo.com.mx

    2006-07-01

    In this work it was built a methodology to compare nuclear reactors of third generation that can be contemplated for future electric planning in Mexico. This methodology understands the selection of the reactors to evaluate eliminating the reactors that still are not sufficiently mature at this time of the study. A general description of each reactor together with their main ones characteristic is made. It was carried out a study for to select the group of parameters that can serve as evaluation indicators, which are the characteristics of the reactors with specific values for each considered technology, and it was elaborated an evaluation matrix indicators including the reactors in the columns and those indicators in the lines. Since that none reactor is the best in all the indicators were necessary to use a methodology for multi criteria taking decisions that we are presented. It was used the 'Fuzzy Logic' technique, the which is based in those denominated diffuse groups and in a system of diffuse inference based on heuristic rules in the way 'If Then consequence> ', where the linguistic values of the condition and of the consequence is defined by diffuse groups, it is as well as the rules always they transform a diffuse group into another. Later on they combine all the diffuse outputs to create a single output and an inverse transformation is made that it transfers the output from the diffuse domain to the real one. They were carried out two studies one with the entirety of the indicators and another in which the indicators were classified in three approaches: the first one refers to indicators related with the planning of the plants inside the context of the general electric sector, the second approach includes indicators related with the characteristics of the fuel and the third it considers indicators related with the acting of the plant in safety and environmental impact. This second study allowed us to know the qualities of

  9. Online monitoring and diagnostic system on RA-6 nuclear reactor

    International Nuclear Information System (INIS)

    Garcia Peyrano, O. A.; Marticorena, M.; Koch, R. G.; Martinez, J. S; Berruti, G. E.; Nunez, W. M.; Gonzales, L. A.; Tarquini, L. D.; Sotelo, J. P

    2009-01-01

    This paper presents the Online Automatic Monitoring and Diagnostic System for mechanical components, installed on RA-6 Nuclear Reactor (San Carlos de Bariloche, Argentina). This system has been designed, installed and set-up by the Vibrations and Mechatronics Laboratory (Centro Atomico Bariloche, Comision Nacional de Energia Atomica) and Sitrack.com Argentina SA. This system provides an online mechanical diagnostic of the main reactor components, allowing incipient failures to be early detected and identified, avoiding unscheduled shut-downs and reducing maintenance times. The diagnostic is accomplished by an online analysis of the vibratory signature of the mechanical components, obtained by vibrations sensors on the main pump and the decay tank. The mechanical diagnostic and the main operational parameters are displayed on the reactor control room and published on the internet. [es

  10. Standardization for electric energy saving; Normalizacion para el ahorro de energia electrica

    Energy Technology Data Exchange (ETDEWEB)

    Reyes Diaz, Arturo [Fideicomiso de Apoyo al Programa de Ahorro de Energia del Sector Electrico (FIDE), Mexico, D. F. (Mexico)

    1994-12-31

    This work describes shortly the current legislation on the standardization; as well as the participation of the entities Fideicomiso de Apoyo al Programa de Ahorro de Energia del Sector Electrico (FIDE) and Programa de Ahorro de Energia (PAESE) in the consulting committees, for the elaboration of the Mexican official standards focussed to electric power saving. [Espanol] El presente trabajo, describe brevemente la legislacion actual sobre la normalizacion; asi como la participacion de las entidades Fideicomiso de Apoyo al Programa de Ahorro de Energia del Sector Electrico (FIDE) y Programa de ahorro de Energia (PAESE) en los comites consultivos, para la elaboracion de normas oficiales mexicanas enfocadas al ahorro de energia electrica.

  11. Standardization for electric energy saving; Normalizacion para el ahorro de energia electrica

    Energy Technology Data Exchange (ETDEWEB)

    Reyes Diaz, Arturo [Fideicomiso de Apoyo al Programa de Ahorro de Energia del Sector Electrico (FIDE), Mexico, D. F. (Mexico)

    1993-12-31

    This work describes shortly the current legislation on the standardization; as well as the participation of the entities Fideicomiso de Apoyo al Programa de Ahorro de Energia del Sector Electrico (FIDE) and Programa de Ahorro de Energia (PAESE) in the consulting committees, for the elaboration of the Mexican official standards focussed to electric power saving. [Espanol] El presente trabajo, describe brevemente la legislacion actual sobre la normalizacion; asi como la participacion de las entidades Fideicomiso de Apoyo al Programa de Ahorro de Energia del Sector Electrico (FIDE) y Programa de ahorro de Energia (PAESE) en los comites consultivos, para la elaboracion de normas oficiales mexicanas enfocadas al ahorro de energia electrica.

  12. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  14. Mapa de energia baseado em predição para redes de sensores sem fio

    OpenAIRE

    Raquel Aparecida de Freitas Mini

    2004-01-01

    O objetivo deste trabalho é construir o mapa de energia de uma rede de sensores sem fio utilizando técnicas de predição. Em mapas de energia baseados em predição, cada nó sensor utiliza algoritmos de predição para modelar sua dissipação de energia com o objetivo de prever seu consumo de energia no futuro. Nesta situação, ao invés de enviar para o nó sorvedouro apenas sua quantidade de energia disponível, cada sensor envia também os parâmetros do modelo que descreve seu consumo de energia. O n...

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  16. Methods in nuclear reactors calculations; Metodos de calculo en reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Velarde, G

    1966-07-01

    Studies are made of the neutron transport equation corresponding to the the real and virtual reactors, as well as the starting hypotheses. Methods are developed to solve the transport equation in slab geometry, and P{sub l}; B{sub l}; M{sub l}; S{sub n} and discrete ordinates approximations. (Author)

  17. Energia nuclear na mídia: Jornalismo científico em portais de notícias nacionais

    Directory of Open Access Journals (Sweden)

    Ricardo Henrique Almeida Dias

    2017-07-01

    Full Text Available This study seeks to examine how the nuclear energy is conveyed by the news media. We used the newsworthiness criteria in journalistic discourse to analyse some science journalism texts on nuclear energy in Brazilian news websites. We selected some news and classified using news values such as conflict, proximity, novelty and relevance. We concluded that nuclear energy is conveyed by the media in a way that the advantages and disadvantages were discussed, and news values were useful to point how all these arguments worked.

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  19. Crise de energia e governança ambiental

    OpenAIRE

    França, Georgeana Barbosa de

    2013-01-01

    Resumo: Este trabalho analisa os processos de transformação territorial ocasionados pela implantação de instrumentos de gestão ambiental que visam a promoção de energia renovável em pequena escala em meios rurais. Esta investigação, que possui foco interdisciplinar, emprega a perspectiva metodológica da Teoria do Ator-Rede. O estudo de caso desta pesquisa é uma iniciativa local para produção de energia renovável em uma comunidade rural do Oeste do Paraná, Brasil. Conduzida por ...

  20. Portugal.

    Science.gov (United States)

    Eckles, David; Toro, Leonor, Ed.

    Brief information is provided on the region, climate, agriculture and industry of 10 provinces in Portugal: Tras-os-Montes e Alto Douro, located in Portugal's northeastern region; Beira Alta, the province with Portugal's highest elevation point; Beira Baixa, one of Portugal's poorest regions; Beira Litoral, located in central Portugal along the…

  1. Design of the HMI for the operation of a nuclear research reactor; Diseno del HMI para la operacion de un reactor nuclear de investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Bucio V, F. J.; Celis del Angel C, L.; Palacios H, J. C., E-mail: francisco.bucio@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The Instituto Nacional de Investigaciones Nucleares (ININ) participated in an international tender published by the Colombian Geological Service for the modernization of the Nuclear Reactor Control Console Ian-R1, the participating institutions were: General Atomics (USA), INVAP (Argentina) and ININ (Mexico). The proposal made by the ININ had an important characteristic, the independence of the manufacturer, since it was a project based on modular elements. One of the elements was the Human-Machine Interface (HMI), where the development was proposed under the Free Software (Gnu-GLP) scheme. Java was the programming language on which the HMI was developed to operate the nuclear reactor in Bogota, Colombia. The instrumentation that allows the interaction with the sensors and/or actuators is based on the use of PLC's (programmable logic controllers) with which the computers of the HMI communicate through a local network using the Mod bus protocol over Ethernet. (Author)

  2. Clean generation of electric energy; Generacion limpia de energia electrica

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez, Juan M.; Torres, Emmanuel [Centro de Investigacion y de Estudios Avanzados (CINVESTAV), Unidad Guadalajara (Mexico)

    2006-10-15

    This article deals on the existing alternatives of renewable energy for generation of electricity free from polluting sequels within the Mexican territory and presents a global overview on the electricity generation in Mexico. Wind power, hydraulic energy, biomass, photovoltaic and fuel cells are sources of renewable energy that could contribute to Mexico's sustainable development, for this reason it is discussed on the main sources of renewable energy in Mexico - solar and wind energy, mini-hydraulic, biomass and geothermal -, on their development and evolution, cost, insertion projects and obstacles for their correct development in this country. [Spanish] Este articulo versa sobre las alternativas de energia renovable existentes para una generacion de electricidad libre de secuelas contaminantes dentro del territorio mexicano y presenta un panorama global sobre la generacion de electricidad en Mexico. La energia eolica, hidraulica, biomasa, fotovoltaica y las celdas de combustible son fuentes de energia renovable que podrian contribuir al desarrollo sustentable de Mexico, por esto se arguye sobre las principales fuentes de energia renovable en Mexico -energia solar, eolica, minihidraulica, biomasa y geotermia-, sobre su desarrollo y evolucion, costo, proyectos de insercion y obstaculos para su correcto desarrollo en ese pais.

  3. 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

  4. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  5. Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '

    Energy Technology Data Exchange (ETDEWEB)

    Pereira Sanchez, G.; Uriarte Hueda, A. [Junta de Energia Nuclear, Division de Materiales Madrid (Spain)

    1966-05-15

    A number of theoretical studies on nuclear safety have been carried out in a pilot plant being constructed at the Junta de Energia Nuclear in Madrid for processing irradiated fuels from the MTR-type experimental reactor JEN-1. The study was carried out working with aqueous and organic solutions at two levels of {sup 235}U enrichment - 20% and 93%. The paper is divided into two main parts: the first deals with the individual items of equipment, and the interactions between these are studied in the second part. The calculations in this second part have been made using three different methods to make it more certain that the system as a whole can never be critical. The first method employed is based on the solid angle concept and makes it possible to fix the maximum {sup 235}U concentrations within the system. The second method, based on the albedo, supplies the value of the multiplication factor K of the whole assembly as a function of the concentration of {sup 235}U. In the last part, the distribution of the equipment is compared with other similar systems and experimental tests from other sources. Finally, the paper specifies the conditions for working the installation which ensure that a nuclear accident can never occur. (author) [Spanish] Se ha efectuado una serie de estudios teoricos sobre la seguridad nuclear de una planta piloto, que se encuentra en construccion en la Junta de Energfa Nuclear situada en Madrid, para el tratamiento de combustibles irradiados procedentes del reactor experimental JEN-1 del tipo MTR. El estudio se ha realizado utilizando disoluciones, tanto acuosas como organicas, con dos grados de enriquecimiento, 20% y 93% en {sup 235}U. Este trabajo comprende dos partes principales: en la primera se han considerado las distintas unidades del equipo individualmente y en la segunda se han estudiado las interacciones entre ellas. El calculo de esta segunda parte se ha hecho por tres metodos diferentes para tener una mayor seguridad de que el

  6. Inspection of nuclear power plants under construction in Spain

    International Nuclear Information System (INIS)

    Santoma, L.

    1977-01-01

    Brief summary of the situation of the nuclear industry in Spain, in order to better understand the questions involved in the inspection of the Spanish nuclear power plants, as well as the experience acquired, followed by a description of some of the problems which have arisen during the construction phase. Also the problems faced by the Inspection of the Junta de Energia Nuclear are described in order to fulfill the missions entrusted to it. Finally, some recommendations are made in light of the experience had by Spain.(author) [es

  7. The Instituto de Energia Atomica (Brazil) in the context of the research and development nuclear centers conjunture

    International Nuclear Information System (INIS)

    1977-05-01

    Aiming to situate the present development of IEA relatively to similar foreign institutions, a survey was made of the functions and activities of the relevant centers in different countries. Those institutions were selected in view of their importance in the respective countries, and of the information on them available at IEA. Among them are especially included nuclear centers of countries with economical and social development levels similar to Brazilian ones, like Argentina, Australia, India and Spain [pt

  8. Sites for locations of nuclear reactors; Sitios para emplazamientos de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Balcazar, M.; Huerta, M.; Lopez, A., E-mail: miguel.balcazar@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    A restriction on sites of nuclear energy is the history of seismic activity, in its magnitude (Richter) and intensity (Mercalli). This article delimits the areas of greatest magnitude and national seismic intensity, with restrictions of ground acceleration; the supplement areas with a low magnitude of seismic activity are shown. Potential sites for the location of these sites are introduced into a geographic information system. The set of geo-referenced data contains the location of the active volcanic manifestations; the historical record of earthquake epicenters, magnitudes and intensities; major geological faults; surface hydrology and water bodies; location of population density; protected areas; contour lines; the rock type or geology. The geographic information system allows entering normative criteria and environmental restrictions that correlate with geo-referenced data described above, forms both probable and exclusion areas for the installation of nuclear sites. (Author)

  9. Analysis of opinion about nuclear energy and sustainability in a graduate level population; Analisis de opinion sobre la energia nuclear y sustentabilidad en una poblacion de nivel superior

    Energy Technology Data Exchange (ETDEWEB)

    Meza L, C.D.; Arredondo S, C. [IPN, ESFM, 07738 Mexico D.F. (Mexico)]. e-mail: angie2esa@hotmail.com

    2007-07-01

    The Mexican society has a modest knowledge of the nuclear energy, even at the participant students of superior education level in this survey is finds a scarce compression with regard to their obtaining, use and manage. As a result of the lack of interest of the same society and at the problems that know each other like they are: the pollutants that it produces those nuclear waste and the possible use or warlike end, a fear is believed about this energy type. In the Superior School of Physics and Mathematics there is the possibility to make studies so much at master degree level in the one fear of the nuclear energy and the applications of the same one in peaceful uses. However, particularly the studies at master level seem to be immersed in a crisis that requires of different supports to be resolved. For all it previous was thought in carrying out a survey inside a student population with superior level to know the opinion and the knowledge on the nuclear energy in Mexico. In this work the results of the survey are analyzed with the purpose of to determine which is the knowledge of the community mentioned regarding the other energy types, the impact that they have these in the environment, the sustenance of the same ones and in particular on knowledge about the nuclear energy considering the aspects before mentioned. With base had said analysis settles down that the interviewed community knows very little about the nuclear energy but they show interest to study and to obtain bigger information about the same one, for what is very important to diffuse but and better information on the nuclear energy to the population's strata, because it is of supposing that the rest of the population has erroneous information on the nuclear energy. In particular for the community of the Superior School of Physics and Mathematics the diffusion of all the benefits of the peaceful applications of the nuclear energy, including the capacity to generate enormous quantities and

  10. Energia Renovable para Centros de Salud Rurales (Renewable Energy for Rural Health Clinics)

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, T.; Olson, K.

    1999-07-28

    Esta es la primera de una serie de guias de aplicaciones que el Programa de Energia de Villas de NREL esta comisionando para acoplar sistemas comerciales renovables con aplicaciones rurales, incluyendo agua, escuelas rurales y micro empresas. La guia esta complementada por las actividades de desarrollo del Programa de Energia de Villas de NREL, proyectos pilotos internacionales y programas de visitas profesionales.

  11. Germany: of the nuclear energy expansion to the structure for their gradual abandonment; Alemania: de la expansion de la energia nuclear a la estructura para su abandono gradual

    Energy Technology Data Exchange (ETDEWEB)

    Mez, L. [Frei Universitat Berlin, Environmental Policy Research Centre, Thielallee 47, 14195 Berlin (Germany)

    2009-07-01

    This work exposes a panorama of the German nuclear industry, where the investment in this sector began around the fifty, having great peak during the period 1968 at 1989. Causes like a poor electricity demand, the over capacity and a persistent controversy among the public opinion for the nuclear energy use, stop the expansion from this industry to the little time of established. In contrast with the legal situation in most of the countries, in Germany the operation licences were granted without it limits of time. Nevertheless, the operation expectation was estimated inside a range of 20 to 40 years, depending in particular on the service life of the renovation parts. Taking into account these data, seven nuclear power plants of those that have already operated for 20 years or more, are about to confront expensive reconstructions or the closing in the following five years; while other seven will be closed in the subsequent 10 or 15 years. While the federal politicians and their directive went favorable until recent time in general to the extended use of nuclear energy, some authorities of the states became more restrictive when interpreting the allowed forecasts, what has generated continuous differences and regulatory uncertainty. In consequence, the facilities in operation gradually have shown interest in reaching agreements with the government about the nuclear politics, by means of the regulations reestablishment and one calculus linked at the costs. In spite of the many and constant judgments of the public opinion, the federal nuclear politics was up to 1998 on the side of the alliance pro nuclear and back to the industry by means of multiple fiscal and regulatory privileges. This official position was reverted by first time after the federal elections of that year, when a new red-green federal government announcement the gradual retirement of the nuclear energy of Germany. That coalition pact among the Democratic Social parties (red) and green

  12. The Junta de Andalucia’s External Action in Morocco: the Case of International Cooperation for Development

    Directory of Open Access Journals (Sweden)

    Thierry Desrues

    2007-12-01

    Full Text Available After 25 years of experience, International Cooperation for Development has become an important instrument for external action among many of Spain’s autonomous communities. This is not only a result of the accompanying ethical and humanitarian dimension, but also of the social legitimacy that it provides in an area of external influence, where action has traditionally been monopolised by the State Government. This article analyses the Junta de Andalucia’s external action toward Morocco through the case of the policy of International Cooperation for Development.

  13. Development of a model for strategic evaluation of the global performance of the Brazilian Nuclear Energy Commission; Desenvolvimento de um modelo para avaliacao estrategica do desempenho global da Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio

    2003-07-01

    A conscious, effective course of action, now essential to several areas and organizations, has become a must in the public administration. In this sense, modem managerial practices may contribute significantly for governmental organism to take up an attitude shifted to results in the society, without losing its eminently public function. In order to measure the social impact of the activities of the State as a whole, institutions must use mechanisms that allow self-evaluations of their performance, so as to verify the return obtained as a result of their efforts. However, most institutions do not have structured tools for such evaluation. The present study proposes to the Comissao Nacional de Energia Nuclear a model to measure its global performance, offering a proposed architecture for the measurement system in accordance with the results of the planning process of the Institution. The methodology presented also comprises the definition of cause-and-effect critical models between the strategic objectives of the organization and its respective factors critic ai for success, as well as related performance indicators. This work also includes the breakdown of the measurement system for the macro processes of the organization, optimizing resource sharing and the flow of information, avoiding redundant efforts and bringing forth further advantages aiming at creating a organizational 'unit'. Within this context, the developed model may offer substantial help for the improvement of the maturity of the organization in goal-oriented management, considering that the proposed global performance measurement follows a planned structure, with a systemic approach of the organization, allowing that the process be carried out in a way that is transparent and objective. (author)

  14. Development of a model for strategic evaluation of the global performance of the Brazilian Nuclear Energy Commission; Desenvolvimento de um modelo para avaliacao estrategica do desempenho global da Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio

    2003-07-01

    A conscious, effective course of action, now essential to several areas and organizations, has become a must in the public administration. In this sense, modem managerial practices may contribute significantly for governmental organism to take up an attitude shifted to results in the society, without losing its eminently public function. In order to measure the social impact of the activities of the State as a whole, institutions must use mechanisms that allow self-evaluations of their performance, so as to verify the return obtained as a result of their efforts. However, most institutions do not have structured tools for such evaluation. The present study proposes to the Comissao Nacional de Energia Nuclear a model to measure its global performance, offering a proposed architecture for the measurement system in accordance with the results of the planning process of the Institution. The methodology presented also comprises the definition of cause-and-effect critical models between the strategic objectives of the organization and its respective factors critic ai for success, as well as related performance indicators. This work also includes the breakdown of the measurement system for the macro processes of the organization, optimizing resource sharing and the flow of information, avoiding redundant efforts and bringing forth further advantages aiming at creating a organizational 'unit'. Within this context, the developed model may offer substantial help for the improvement of the maturity of the organization in goal-oriented management, considering that the proposed global performance measurement follows a planned structure, with a systemic approach of the organization, allowing that the process be carried out in a way that is transparent and objective. (author)

  15. Simplified dynamic simulation of a traveling wave nuclear reactor; Simulacion dinamica simplificada de un reactor nuclear de onda viajera

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez M, H.; Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, San Rafael Atlixco No. 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico); Francois, J. L. [UNAM, Facultad de Ingenieria, Paseo Cuauhnahuac 8532, Jiutepec 62550, Morelos (Mexico); Lopez S, R., E-mail: heribertosanchez7@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    In this work the nuclear fuel burn wave in a fast traveling wave reactor (TWR) is presented, using the reduced model of the neutron diffusion equation, considering only the axial component, and the equations of the transuranic dynamics of U-Pu and a radionuclide of Pu. Two critical zones of the reactor are considered, one enriched with U-Pu called ignition zone and the other impoverished zone or of U-238, named breeding zone. Occupying Na as refrigerant within TWR, and Fe as structural material; both are present in the ignition and breeding zones. Considering as a fissile material the Pu, since by neutron capture the U is transformed into Pu, thus increasing the quantity of Pu more than that of U; in this way the fuel burn stability with the wave dynamics is understood. The calculation of the results was approached numerically to determine the temporal space evolution of the neutron flux in this system and of the main isotopes involved in the burning process. (Author)

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  18. Analysis of the participation of nuclear energy in electricity planning in Mexico; Analisis de la participacion de la energia nuclear en la planeacion electrica en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez H, U. A.; Martin del C, C., E-mail: uahh_123@hotmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, Circuito Exterior s/n, 04510 Ciudad de Mexico (Mexico)

    2017-09-15

    In recent years there has been an effort in Mexico and the world to reduce greenhouse gas emissions (GGE) and at the same time supply the increase in energy consumption worldwide. In this context, the electricity sector in Mexico is fundamental in the fulfillment of GGE reduction commitments and goals by contributing more than 20% of these. Nuclear energy must have a fundamental role in the expansion of the National Electric System, since it allows generating large amounts of electricity for long periods of time without emissions of polluting gases. With this background, was determined to investigate the main characteristics that nuclear technology must have in order to be considered as a real solution in guaranteeing the supply of electricity in a continuous, safe and economic manner with the least amount of GGE possible. However, combined cycle power plants are the main option to cover these needs in accordance with the current national policy, so in this work an extensive technical, economic and safety comparison between the combined cycle and nuclear technologies was carried out. In order to know the technology that should have a greater participation in the planning of the National Electric System in the coming decades. Thus, five price scenarios were elaborated for natural gas and liquefied natural gas imports, in order to know the cost that would generate to continue with the current policy of use of combined cycle power plants as a base for electricity generation and if that cost justified in the first instance the increase of nuclear capacity in the country. The results showed that is necessary to change the main source of power generation in Mexico in order to have a reliable, safe, economical and clean electrical system. (Author)

  19. Analysis considerations in the future of the nuclear energy in Mexico; Consideraciones de analisis en el futuro de la energia nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G., E-mail: gustavo.alonso@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    Mexico requires for legal command reducing the participation of fossil energy for the electric power production to not more than 65% for 2024, the other 35% will be covered by sources of clean energy, among which are the renewable sources and the nuclear energy. Inside the National Strategy of Energy 2012-2016 3 possible scenarios are outlined to give execution to this command, in this work is made an analysis of these scenarios and its implications in energy safety. (Author)

  20. Software for the nuclear reactor dynamics study using time series processing; Software para el estudio de la dinamica de reactores nucleares mediante el procesamiento de series temporales

    Energy Technology Data Exchange (ETDEWEB)

    Valero, Esbel T.; Montesino, Maria E. [Instituto Superior de Ciencia y Tecnologia Nuclear (ISCTN), La Habana (Cuba)

    1997-12-01

    The parametric monitoring in Nuclear Power Plant (NPP) permits the operational surveillance of nuclear reactor. The methods employed in order to process this information such as FFT, autoregressive models and other, have some limitations when those regimens in which appear strongly non-linear behaviors are analyzed. In last years the chaos theory has offered new ways in order to explain complex dynamic behaviors. This paper describes a software (ECASET) that allow, by time series processing from NPP`s acquisition system, to characterize the nuclear reactor dynamic as a complex dynamical system. Here we show using ECASET`s results the possibility of classifying the different regimens appearing in nuclear reactors. The results of several temporal series processing from real systems are introduced. This type of analysis complements the results obtained with traditional methods and can constitute a new tool for monitoring nuclear reactors. (author). 13 refs., 3 figs.

  1. The Text of the Agreement of 22 July 1977 between Argentina and the Agency for the Application of Safeguards in connection with a Contract Concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reactor Brennelement Union Gmbh Hanau (Federal Republic Of Germany) for Co-Operation in The Field of Fabrication of Fuel Elements for Peaceful Nuclear Activities

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994 [es

  2. Guidebook to nuclear reactors

    International Nuclear Information System (INIS)

    Nero, A.V. Jr.

    1976-05-01

    A general introduction to reactor physics and theory is followed by descriptions of commercial nuclear reactor types. Future directions for nuclear power are also discussed. The technical level of the material is suitable for laymen

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

    Purpose: To improve the channel stability and the reactor core stability in a spontaneous circulation state of coolants. Constitution: A reactor core stabilizing device comprising a differential pressure automatic ON-OFF valve is disposed between each of a plurality of jet pumps arranged on a pump deck. The stabilizing device comprises a piston exerted with a pressure on the lower side of the pump deck by way of a pipeway and a valve for flowing coolants through the bypass opening disposed to the pump deck by the opening and closure of the valve ON-OFF. In a case where the jet pumps are stopped, since the differential pressure between the upper and the lower sides of the pump deck is removed, the valve lowers gravitationally into an opened state, whereby the coolants flow through the bypass opening to increase the spontaneous circulation amount thereby improve the stability. (Yoshino, Y.)

  4. Implantação de um programa de gerenciamento de resíduos químicos e águas servidas nos laboratórios de ensino e pesquisa no CENA/USP Establishment of a management program for chemical residues and waste water, generated in laboratories of the centro de energia nuclear na agricultura (CENA/USP

    Directory of Open Access Journals (Sweden)

    Glauco Arnold Tavares

    2005-08-01

    Full Text Available The aim of this work is to establish a program for the treatment of chemical residues and waste waters at the Centro de Energia Nuclear na Agricultura (CENA/USP, for environmental preservation and training of staff. Five tons of stored residues and the ones currently generated in the laboratories have to be treated. Rational use of water is also part of the program. The traditional purification by distillation has been replaced by purification with ion exchange resins. Lower energy consumption and better water quality were achieved.

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  6. The nuclear energy and the others sources; La energia nuclear y el resto de las fuentes: el tema de la seguridad

    Energy Technology Data Exchange (ETDEWEB)

    Velasco, E.

    2008-07-01

    Safety is the priority in the nuclear industry actions. For the design and during the construction or the exploitation, including the decommissioning, the fundamental objective is not to produce any damage to the people or the environment. In the same way, the radioactive waste management technologies give the right solution to treatment and storage of them. The Regulatory Organisations of each country warranties with its vigilance the safety objectives. A network of international organisation, public and private, support the experiences exchange, the normative harmonisation and the management, searching the excellence and best practices. (Author)

  7. Análisis económico, financiero y contable de la normativa reguladora de las juntas de obras de puertos en España, siglos XIX y XX

    Directory of Open Access Journals (Sweden)

    Mercedes Calvo Cruz

    2008-12-01

    Full Text Available El presente trabajo se ocupa de aquellas funciones que constituyeron los objetivos centrales de la administración que se encargó de la construcción y explotación de los puertos y, de forma expresa, de la normativa que reguló las tareas de organización y administración a través de la creación de las juntas de obras, y los reglamentos que se emitieron para su funcionamiento. Del análisis de los reglamentos se evidencian dos ámbitos en la organización de la junta de obras, el ámbito económico, contable y financiero, y por otro lado, el ámbito técnico. En nuestro trabajo se desarrolló el primero de los ámbitos señalados, con el fin de plasmar la organización administrativa y destacar las particularidades contables y financieras de las juntas de puertos. Finalmente, este estudio podría dar lugar a posteriores investigaciones como serían, entre otras, verificar la efectiva aplicación de la normativa por parte de una determinada junta de obras del puerto y realizar un análisis empírico con los datos facilitados por la documentación contable que genera la aplicación de los reglamentos.

  8. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

  9. La junta de obras de los puertos: aspectos económicos, financieros y contables de su normativa reguladora. Una aplicación a la junta de obras del Puerto de la Luz y Las Palmas (Islas Canarias a través del estudio del libro diario, 1907-1908

    Directory of Open Access Journals (Sweden)

    Candelaria Castro Pérez

    2008-07-01

    Para la aplicación empírica de este estudio se ha tomado como fuente primaria la contabilidad desarrollada por la Junta de Obras de los Puertos de La Luz y Las Palmas para los años 1907-1908, reflejada en su primer Libro Diario, en el cual se registran todas las operaciones y por tanto constituye el fiel reflejo de la realidad económica del puerto. Dicho análisis nos permite mostrar la diversidad de operaciones económicas realizadas por la Junta en el intervalo temporal objeto de estudio, así como los movimientos de capitales que constituyeron su financiación y la posterior inversión de los mismos. Este estudio será la base para contrastar la realidad económica con las obligaciones impuestas por la normativa vigente en el período analizado.

  10. Fundamentos sobre energia das ondas (e sistemas fotovoltaicos para bombagem de água)

    OpenAIRE

    Carneiro, Joaquim A. O.

    2017-01-01

    Texto de apoio às aulas da UC "Energias Renováveis II" do Mestrado em Ciências e Tecnologias do Ambiente Devido ao crescente aumento do consumo energético, os últimos anos têm sido caracterizados por uma aposta estratégica na procura de fontes de energia alternativas aos combustíveis fósseis tradicionais. Este documento aborda os principais fundamentos adstritos a dois diferentes tipos de fontes alternativas de energia, nomeadamente a energia das ondas do oceano e a energia solar fotovolta...

  11. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

  12. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  13. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  14. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages; Instalacion de un nuevo tipo de reactor nuclear en Mexico: ventajas y desventajas

    Energy Technology Data Exchange (ETDEWEB)

    Jurado P, M.; Martin del Campo M, C. [FI-UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: mjp_green@hotmail.com

    2005-07-01

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  15. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  16. 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)

  17. Propuesta de nuevas opciones de inversión y gestión de la cartera de inversiones de la Junta Administradora de Ahorro y Préstamo de la Universidad de Costa Rica

    OpenAIRE

    López Bogantes, Randy Alberto

    2014-01-01

    Tesis de maestría -- Universidad de Costa Rica. Posgrado en Administración y Dirección de Empresas. Maestría Profesional en Administración y Dirección de Empresas con énfasis en Finanzas, 2014 El objetivo general del proyecto es proponer alternativas adicionales de inversión más rentables que permitan a la Junta Administradora de Ahorro y Préstamo de la Universidad de Costa Rica una estructura óptima del portafolio de acuerdo con la normativa interna, al lograr el mejor rendimiento posible...

  18. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  19. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  20. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

    This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

  1. Evaluation of Sao Paulo population knowledge about nuclear energia and radioactive wastes. Did the Goiania accident rise any interest ?; Avaliacao do conhecimento da populacao paulistana sobre a energia nuclear e os rejeitos radioativos. O acidente de Goiania despertou o interesse?

    Energy Technology Data Exchange (ETDEWEB)

    Rzyski, Barbara M.; Sartori, Carla E. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-12-31

    The results of the inquire collected in 1996, about 10 years after Goiania accident, regarding to the knowledge of nuclear energy and rad wastes are presented. The survey was performed among university students and the population of the Sao Paulo city, of all social levels and different ages. The results show that people between 45 and 55 years are more receptive to the matter. It was observed that the major part of the information absorbed by the public arise form news divulged by newspapers and some spread facts, in cases of incidents or accidents as was Goiania 2 refs., 11 tabs., 1 append.; e-mail: bmrzyski at net.ipen.br

  2. El Cuerpo de Ingenieros Militares y la Real Junta de Fomento de la isla de Cuba. Obras públicas entre 1832 y 1854 = Spanish Military Engineers and the Real Junta de Fomento at the Island of Cuba. Public Works between 1832 and 1834

    Directory of Open Access Journals (Sweden)

    Ignacio José López Hernández

    2016-05-01

    Full Text Available Con este trabajo se pretende abordar la tarea desempeñada por los ingenieros del ejército en las obras públicas de la isla de Cuba como cuerpo facultativo y asistente de la Real Junta de Fomento, corporación encargada entre los años de 1832 y 1854 de articular las infraestructuras y medios necesarios para la promoción de la agricultura y el comercio. Para ello estudiaremos la particularidad de esta labor en el contexto de las atribuciones del Cuerpo de Ingenieros Militares en España, e igualmente veremos, con ejemplos documentales, de qué manera se organizó esta Junta y cómo los ingenieros se integraron en ella, para finalmente tratar las obras más destacadas, producto de esta estrecha colaboración.In this article we will study the task executed by the Spanish military engineers in public works in the island of Cuba. These engineers worked in Cuba as a specialized body in infrastructures and civil buildings, along with the Real Junta de Fomento, the responsible institution for the promotion and development of agriculture and commerce in the island between 1832 and 1854. To that end, we will analyse the particular work tackled by these engineers in the context of their functions in Spain, and how these ones took part in the organization of the Junta. Finally the most important works undertaken by both institutions will be studied.

  3. Applications of the renewable energies; Aplicaciones de las energias renovables

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Rocha, Luis Martin [Comision Nacional para el Ahorro de Energia, Mexico, D.F. (Mexico)

    2001-07-01

    The solar energy manifests itself in different forms and its application has been fundamental for the humankind development. These forms are known as renewable energies, since they are energy forms that are renewed or remade with time or that are so abundant on Earth, that they will last for hundreds or thousands of years, either we use them or not. The main advantage of the utilization of the renewable energies in comparison with hydrocarbons is the one of having smaller impact on the environment, which brings about the conservation of nonrenewable resources, and to postpone its exhaustion. They allow the distributed generation, diminishing the power losses in the transmission and distribution systems, which increases the overall efficiency. In addition they can be the drive for regional development and generation of employment, because when having applications in remote zones and being a field still not completely developed in Mexico, the possibility exists of enabling professionals and technicians. From the point of view of the power sector, the renewable energies extend the supply and availability of energy, making more flexible and independent the operation and reliability of the national power system. [Spanish] La energia solar se manifiesta de diversas formas y su aplicacion ha sido fundamental para el desarrollo de la humanidad. A estas formas se les conoce como energias renovables, ya que son formas de energia que se van renovando o rehaciendo con el tiempo o que son tan abundantes en la tierra, que perduraran por cientos o miles de anos, las usemos o no. La principal ventaja del aprovechamiento de las energias renovables en comparacion con los hidrocarburos es la de tener menor impacto al medio ambiente, lo que trae consigo la conservacion de recursos no renovables, y posponer su termino. Permiten la generacion distribuida, disminuyendo las perdidas energeticas en los sistemas de transmision y distribucion, lo que incrementa la eficiencia general. Ademas

  4. MEDIDA DEL RENDIMIENTO DE LAS JUNTAS DE OBRAS DE LOS PUERTOS ESPAÑOLES DURANTE LA NOVENA LEGISLATURA DE LA DICTADURA FRANQUISTA (1962-1965

    Directory of Open Access Journals (Sweden)

    Isidoro Guzmán Raja

    2016-07-01

    Full Text Available Los enclaves portuarios son importantes centros de desarrollo económico, cuya actuación eficiente es una premisa fundamental de su modelo de negocio para ofrecer adecuadamente los servicios que prestan. En este sentido, el presente trabajo está dedicado al estudio del rendimiento de los puertos españoles durante el periodo 1962-1965, los cuales se encontraban gestionados por las entonces denominadas Juntas de Obras del Puerto (en adelante JOP, que hoy en día conocemos con el apelativo de Autoridades Portuarias (en adelante AP. Sobre un censo de 29 JOP para el periodo objeto de estudio, se aplicó la técnica no paramétrica del Análisis Envolvente de Datos (Data Envelopment Analysis, DEA (Charner et al., 1978; Banker et al., 1984 para determinar las puntuaciones de rendimiento basadas en el trazado de fronteras eficientes por periodos anuales, a partir de la implementación de un modelo de eficiencia en el que se recogen los principales variables en que se basa el servicio portuario. El trabajo se complementa con el cálculo del Índice de Productividad Total de los Factores de Malmquist (Färe et al., 1994, con el fin de conocer la evolución del cambio productivo, junto por el cambio tecnológico y en eficiencia de los puertos evaluados.

  5. Efecto del Gas de Protección, Ángulos de Trabajo y Desplazamiento sobre las Características de Juntas de Filete Obtenidas por GMAW en un Acero Microaleado de Alta Resistencia

    Directory of Open Access Journals (Sweden)

    César Marconi

    Full Text Available Resumen: La junta de filete es una de las más utilizadas en diversas industrias, en particular en la de maquinaria agrícola. Sin embargo, muchas veces, la complejidad de las piezas a unir dificulta la accesibilidad del soldador en este tipo de juntas, siendo los ángulos de trabajo y desplazamiento un aspecto importante a evaluar. Además, en el proceso GMAW el empleo de la mezcla Ar-20%CO2 como gas de protección se ha incrementado en detrimento del 100%CO2, requiriendo en general un ajuste de los parámetros eléctricos. Por otro lado, la incorporación de nuevos materiales de mayor resistencia también requiere la optimización del procedimiento de soldadura. El objetivo de este estudio fue evaluar el efecto de dos gases de protección (Ar-20%CO2 y 100%CO2, de tres ángulos de trabajo (30, 45 y 60º y dos de desplazamiento (45º por empuje y 60º por arrastre sobre los aspectos dimensionales del cordón y la resistencia mecánica de la junta de filete de un acero microaleado de alta resistencia, soldado mediante GMAW. Los mayores niveles de penetración correspondieron a las probetas soldadas por arrastre y con CO2. El sobre espesor fue menor para la condición por empuje y la mezcla de gases. La microdureza del metal de soldadura, para similar ángulo de trabajo, resultó mayor para el gas mezcla en todos los casos. Se desarrollaron índices de aceptabilidad que ponderan los aspectos geométricos y se los relacionaron con las propiedades mecánicas obtenidas sobre las juntas, mostrando una buena correlación.

  6. Geração de energia a partir das ondas do mar

    OpenAIRE

    Grilo, Diogo Dinis

    2013-01-01

    Dado o aumento do consumo de energia e a necessidade de reduzir as emissões de poluentes para a atmosfera, o presente trabalho visa propor uma solução de produção de energia limpa a partir das ondas do mar. O objetivo desta dissertação é criar um sistema alternativo de conversão da energia cinética proveniente das ondas do mar em energia elétrica, tendo como ponto de partida o projeto do sistema pendular SEAREV. Numa primeira fase foi realizada uma análise dos sistemas de co...

  7. Calculation of neutron activation of control rods of a nuclear reactor, using MCNP5; Calculo de activacion neutronica de barras de control de un reactor nuclear, utilizando MCNP5

    Energy Technology Data Exchange (ETDEWEB)

    Pena V, J.D.

    2016-07-01

    The control rods of a nuclear reactor are activated by neutron irradiation. The generated activity produces a dose around the rod which is irrelevant inside the reactor, but significant when the rod is withdrawn and placed in a storage pool, because this dose is a potential risk to the surrounding personnel. On the other hand, most of the activation occurs in the stainless steel components of the rod. The Monte Carlo model can reliably determine the activation produced in a stainless steel part exposed to a neutron flux in a reactor and the dose measurement around this part. This thesis presents the Monte Carlo models developed for the activation of the control rods of the TRIGA Mark III reactor of Instituto Nacional de Investigaciones Nucleares (ININ) when only standard fuel was available. Therefore, the validations of the Monte Carlo models are reliable. (Author)

  8. Los Levantamientos topográficos-parcelarios de la Junta General de Estadística en Cuenca, Huete y Valdeolivas (1867-1869)

    OpenAIRE

    Vidal Domínguez, Mª Jesús; Camarero Bullón, Concepción

    2014-01-01

    Entre 1867 y 1869, en el marco del proyecto topográfico-catastral diseñado por Francisco Coello, la Junta General de Estadística lleva a cabo el levantamiento de cartografía urbana de nueve localidades no madrileñas, entre ellas tres conquenses: Cuenca, Huete y Valdeolivas, cuya cartografía se conserva en el archivo técnico del Instituto Geográfico Nacional. Se trata de un material de gran valor histórico y calidad técnica. El presente trabajo estudia el marco histórico en que se realiza el l...

  9. The youths in the impulse of the nuclear energy in Mexico; Los jovenes en el impulso de la energia nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Contreras R, A. [ININ, Departamento de Tecnologia de Materiales, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Sanchez J, J., E-mail: aida.contreras@inin.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    Around the world the industry and the nuclear development have taken a very important paper in different boundaries like: the medicine, the research, the industry and the electric power generation. However, during the decade of the 90s the technology and the nuclear industry had suffered a decrement in their popularity. After the accident of the nuclear power plant of Chernobyl and the most recent event in the nuclear power plant of Fukushima this popularity has been affected. For all this is that the work of informing to the people on the peaceful uses of the nuclear energy taking relevance. Visualizing this necessity the Young Association for the Nuclear Energy in Mexico, is founded in March 8, 2003 having a mission: To unite the enthusiastic youths professionals and students that believe in the development of the research and that they want to work in a joined way in the problems involved with the technological and scientific development of the country in the nuclear ambit, as well as in their personal achievement. The association has always impelled the related topics with the nuclear development in Mexico and in the world, imparting courses and chats in several universities and institutions, by means of a simple language to be able to go to children and the people in general. In the diffusion work that carries out the association, has an important collaboration and representation with the Mexican Nuclear Society, the North American Young Generation in Nuclear, the International Youth Nuclear Congress and the World Nuclear University. (Author)

  10. The public perception of the nuclear energy in Eastern Europe: past and present; La percepcion publica de la energia nuclear en Europa del Este: pasado y presente

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A.; Jimenez, G.

    2010-07-01

    In Eastern Europe, people associate nuclear energy to the idea of progress, and prestige of the nuclear industry is very high. This article sets the use of nuclear technology to produce energy in a historical context that is particular to these countries. Results of interviews and surveys are analyzed in order to provide an insight on the level of acceptance among population. (Author)

  11. Royal Decree 1899/1984 of 1 August amending Royal Decree 2967/1979 of 7 December on the organisation of activities in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1984-01-01

    Under the Decree of 1979 the ''Empresa Nacional del Uranio SA'' (National Uranium Enterprise - ENUSA) was responsible for spent management while the Junta de Energia Nuclear (JEN) was responsible for the final storage of radioactive waste. However, these provisions do not cover waste resulting from activities outside the fuel cycle or the dismantling of nuclear and radioactive installations, nor do they provide a global solution to the different problems involved in organising the overall management of radioactive waste. Therefore, this Decree authorises the National Enterprise for Radioactive Waste (ENRESA) to perform the tasks prescribed in this field by the 1964 Nuclear Energy Act and the 1979 Decree. (NEA) [fr

  12. Control for nuclear reactor

    International Nuclear Information System (INIS)

    Ash, E.B.; Bernath, L.; Facha, J.V.

    1980-01-01

    A nuclear reactor is provided with several hydraulically-supported spherical bodies having a high neutron absorption cross section, which fall by gravity into the core region of the reactor when the flow of supporting fluid is shut off. (auth)

  13. Technical economic feasibility study for the implementation of a nuclear power plant for the production of electricity in Colombia; Estudio de factibilidad tecnico economica para la implementacion de una central de energia nuclear para la produccion de energia electrica en Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Gonzales, David E.; Bolanos, Hernan G.; Mayorga, Manuel A.; Rodriguez, Edwin A., E-mail: david_egO@yahoo.es, E-mail: hernanbolaos@yahoo.com.ar, E-mail: alejo_mayorga@yahoo.com, E-mail: edwin.rodriguez@distoyota.com.co [Escuela Colombiana de Carreras Industriales (ECCI), Bogota (Colombia). Grupo de Investigacion GIATME

    2013-07-01

    A study on the technical and economic feasibility will be used to implement a nuclear power in Colombia to generate electricity. To this will be searched if there are previous studies on this topic and what they concluded. The manner in which power is supplied will be discussed in a national level nowadays, its strengths and weaknesses. It will be investigated the legal norms that exists in the country on nuclear power and renewable energy sources, the standards established at world level, the nuclear accidents and the great examples. Providers will be sought on the world market nuclear equipment which serve to this purpose and the technical characteristics of these equipment will be discussed. The type of fuel used in nuclear reactors, its origin, method of production, specifications, availability and long-term and safe handling and final disposal are considered. safe handling of this technology and policy or international rules that will studied.

  14. La educación de la tecnología de los reactores nucleares en un programa de postgrado de Ingeniería Multidisciplinar

    OpenAIRE

    Mesquita, Amir Zacarias; Lameiras, Fernando Soares; Martins, Maximiliano Delany

    2016-01-01

    En este artículo se describen las actividades desarrolladas y las innovaciones realizadas en la línea de investigación en los reactores nucleares en un programa de posgrado multidisciplinario, el Posgrado Programa de CDTN/CNEN, en Belo Horizonte. El programa cuenta con maestría y doctorado (stricto sensu), cubriendo las áreas de la ciencia y la ingeniería de materiales, física y química de la materia condensada, la física y la biología de la salud, ciencias de la tierra y la tecnología minera...

  15. Eclesiásticos entre los pensionados y científicos de la junta para ampliación de estudios, II

    Directory of Open Access Journals (Sweden)

    Formentín Ibáñez, Justo

    2003-12-01

    Full Text Available In a previous article (Hispania Sacra, n. 103, we tried to confirm if there was discrimination in favour of the priests of the Junta para Ampliación de Estudios (JPA. We showed that there was no discrimination, but we had only analysed a small number of cases. In this article, we complete the first one bi analysing the case of every priest who asked for a grant from the JPA received it, of those who obtained a grant recognition and of those who worked it, of those who obtained a grant recognition and of those who worked in any center of the JPA. Once again, our conclusion is that there was no discrimination at all.

    En un artículo publicado en el n° 103 de Hispania Sacra nos planteábamos si hubo o no discriminación por parte de la Junta para Ampliación de Estudios hacia los clérigos, por el mero hecho de serlo. Concluíamos entonces que no la hubo, pero el sondeo era pequeño. En el presente artículo, continuación de aquel primero, analizaremos la totalidad de los clérigos que solicitaron pensión y fueron pensionados por la Junta, así como aquellos clérigos que obtuvieron una consideración de pensión y aquellos otros que trabajaron en alguno de los centros de investigación de este organismo, y de nuevo concluiremos que no hubo tal discriminación.

  16. A study on the piston ring wear in automotive engine Seat 1500 CA by means of radioactive tracer technique; Estudio del desgaste de segmentos en motor Seat 1500 CA mediante trazadores radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Val Cob, M del; Chul, Y; Fuentes Figuera de Vargas, J.

    1971-07-01

    The iron side wear in the chromium-plated top compression ring has been a matter of interest for the engine makers and it has been required by them to investigate the wear characteristics of the chromium-plated piston ring. Meanwhile, Bureau of Nuclear Energy in Spain (Junta de Energia Nuclear) and Seat Car Manufacturing Company (Sociedad Espanola de Automoviles de Turismo) agreed to study the wear characteristics of chromium-plated piston ring of type CA gasoline engine for Seat 1500 car by means of radioactive tracer technique. (Author) 9 refs.

  17. Nuclear reactor plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1977-01-01

    The invention is concerned with a quick-closing valve on the main-steam pipe of a nuclear reactor plant. The quick-closing valve serves as isolating valve and as safety valve permitting depressurization in case of an accident. For normal operation a tube-shaped gate valve is provided as valve disc, enclosing an auxiliary valve disc to be used in case of accidents and which is opened at increased pressure to provide a smaller flow cross-section. The design features are described in detail. (RW) [de

  18. Nuclear reactor facility

    International Nuclear Information System (INIS)

    Wampole, N.C.

    1978-01-01

    In order to improve the performance of manitenance and inspections it is proposed for a nuclear reactor facility with a primary circuit containing liquid metal to provide a thermally insulated chamber, within which are placed a number of components of the primary circuit, as e.g. valves, recirculation pump, heat exchangers. The isolated placement permit controlled preheating on one hand, but prevents undesirable heating of adjacent load-bearing elements on the other. The chamber is provided with heating devices and, on the outside, with cooling devices; it is of advantage to fill it with an inert gas. (UWI) 891 HP [de

  19. Energy of our planet; La energia de nuestro planeta

    Energy Technology Data Exchange (ETDEWEB)

    Torres Alvarado, Ignacio; Santoyo Gutierrez, Edgar [Centro de Investigacion en Energia (CIE) de la UNAM, Temixco, Morelos (Mexico)

    2010-07-01

    The total heat flowing from the Earth's interior to the surface is estimated at {approx}42 TW (1012 watts) of which 19% comes from the crust, the 76% comes from the mantle and the 5% comes from the nucleus. The ability to drive the heat of the rocks is very low, causing the need of hundreds of millions of years to exhaust this energy resource. Based on the properties of the renewable heat flow and the long geological times required for its exhaustion, the Earth energy is considered by many scientists as a source of inexhaustible renewable energy, and by its natural availability in all parts of our planet, perhaps the best distributed, together with solar energy. One of the most important advantages of geothermal energy is that its energy can be used not only to generate electric power, but in a large number of applications or direct uses: the heating of buildings, greenhouses or incubators; aquaculture; in various industrial processes (drying products, food packaging, paper manufacturing, chemicals, etc.); balneology for recreational purposes and medicines, and many other applications. In fact, geothermal applications can be integrally one after another or in processes in cascade to fully utilize its energy content. [Spanish] El calor total que fluye del interior de la Tierra hacia la superficie se estima en {approx}42 TW (1012 watts) del cual 19% proviene de la corteza, el 76% proviene del manto y el 5% proviene del nucleo. La capacidad para conducir el calor de las rocas es muy baja, lo que ocasiona que se necesiten cientos de millones de anos para agotar este recurso energetico. Basado en las propiedades renovables del flujo de calor y los largos tiempos geologicos requeridos para su agotamiento, la energia de la Tierra es considerada por muchos cientificos como una fuente de energia renovable, practicamente inagotable, y por su disponibilidad natural en todo nuestro planeta, quizas la mejor distribuida, junto con la energia solar. Una de las ventajas mas

  20. Energia eólica

    OpenAIRE

    Carneiro, Joaquim A. O.

    2013-01-01

    O vento (massas de ar em movimento) é utilizado há milhares de anos para suprir as necessidades energéticas que decorrem de um vasto conjunto de actividades humanas. Por exemplo, o vento foi muito utilizado para propulsar alguns meios de transporte (barcos a vela), bombear água ou permitir o funcionamento de actividades industriais, como foi o caso dos moinhos de vento que ainda hoje existem em muitas regiões de Portugal. Como a maior parte das fontes de energia renováveis (excepto a ener...

  1. The United States Atomic Energy Commission Programme of Nuclear Materials Management; Le Programme de Gestion des Matieres Nucleaires Applique par L'USAEC; Programma komissii po atomnoj ehnergii ssha v oblasti obrashcheniya s yadernymi materialami; El Programa de Administracion de Materiales Nucleares de la Comision de Energia Atomica de los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    George, D. E. [United States Atomic Energy Commission, Washington, DC (United States)

    1966-02-15

    facon dont les donnees concernant les transferts sont enregistrees et traitees a l'USAEC, ainsi que les procedes utilises pour presenter la comptabilite matieres sous forme de rapports periodiques recapitulant les transactions et les resultats des operations. Il decrit egalement les moyens employes par l'USAEC pour determiner l'efficacite des programmes de gestion des matieres nucleaires appliques par les entreprises travaillant pour son compte. En plus des matieres detenues par les entrepreneurs qui dirigent les usines et laboratoires de l'USAEC, il y a de grandes quantites de matieres nucleaires speciales qui sont detenues selon des arrangements varies, par exemple location, propriete privee, contrats passes avec l'USAEC en vertu desquels l'utilisateur est financierement responsable des pertes ou, inverse Tient, prevoyant que l'USAEC assume les risques de perte. Du fait de cette diversite de conditions, l'USAEC prend des dispositions dont l'optique varie selon les elements de chaque cas. L'auteur fait etat de ces variations. Pour conclure, il note succinctement les domaines comportant des problemes encore a resoudre. (author) [Spanish] El autor expone los principios adoptados por la Comision de Energia Atomica de los Estados Unidos para la administracion de materiales nucleares y sigue la evolucion de esos principios desde 1943 hasta el momento actual. Describe el programa general y analiza sus principales caracteristicas, insistiendo especialmente en aquellas partes de dicho programa que se refieren a la obtencion y al registro de datos cuantitativos, al establecimiento de un control interno y a la evaluacion de los rendimientos. Explica con cierto detalle las tecnicas empleadas por la AEC para registrar y sistematizar los datos referentes a las transferencias, asf como las tecnicas de presentacion de informes sobre el balance de materiales en los que se resumen periodicamente las transacciones y los resultados de las operaciones. Trata tambien de los metodos

  2. Neutronic study of a nuclear reactor of fused salts; Estudio neutronico de un reactor nuclear de sales fundidas

    Energy Technology Data Exchange (ETDEWEB)

    Garcia B, F. B.; Francois L, J. L., E-mail: faviolabelen@gmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2012-10-15

    The reactors of fused salts called Molten Salt Reactor have presented a resurgence of interest in the last decade, due to they have a versatility in particular to operate, either with a thermal or fast neutrons spectrum. The most active development was by the middle of 1950 and principles of 1970 in the Oak Ridge National Laboratory. In this work some developed models are presented particularly and studied with the help of the MCNPX code, for the development of the neutronic study of this reactor, starting of proposed models and from a simple and homogeneous geometry until other more complex models and approximate to more real cases. In particular the geometry conditions and criticality of each model were analyzed, the isotopic balance, as well as the concentrations of the salts and different assigned fuel types. (Author)

  3. Ilustración y reforma de la teología en Portugal en el siglo XVIII

    Directory of Open Access Journals (Sweden)

    Ana Cristina ARAÚJO

    2009-11-01

    Full Text Available RESUMEN: El debate sobre la racionalidad intemporal de la verdad compromete, en el siglo XVIII, la unidad del campo teológico. Al margen de la Escolástica, la renovación de esta área del saber supone valorar la Exégesis bíblica, la Historia Eclesiástica y la razón crítica.En Portugal, fray Manuel del Cenáculo Vilas Boas, Luís António Verney y los miembros de la Junta da Providência Literária, contribuyen, con sus ideas y proyectos de reforma, a modernizar la enseñanza conventual y universitaria de los estudios de Teología.En este proceso, la reforma de la Universidad de Coimbra (1772 señala también el triunfo del regalismo de la época del marqués de Pombal.ABSTRACT: In the 18th century the discussion around truth’s timeless rationality compromises the theological field’s unity. Aside scholasticism, this knowledge area’s renewing goes through biblical Exegesis, ecclesiastical history’s and critical reason’s valorization.In Portugal, Frei Manuel do Cenáculo Vilas Boas, Luis Antonio Verney and the member of the Junta da Providência Literária contribute, with their reformist ideas and projects, to the modernization of Theology’s conventual and universitarian teaching.In this process, the University of Coimbra’s reform (1772 also marks the Pombalist regalism’s triumph.

  4. Análisis de la estructura financiera para la toma de decisiones gerenciales en la Junta Administradora del Fondo de Ahorro y Préstamo de la Universidad de Costa Rica

    OpenAIRE

    Rojas González, Catalina

    2012-01-01

    Tesis de maestría -- Universidad de Costa Rica. Posgrado en Administración y Dirección de Empresas. Maestría Profesional en Administración y Dirección de Empresas con énfasis en Finanzas, 2012 El objetivo general del trabajo es elaborar un análisis detallado de los estados financieros de la Junta Administradora del Fondo de Ahorro y Préstamo (JAFAP) de la Universidad de Costa Rica para el período comprendido entre el 31 de diciembre de 2009 y el 31 de diciembre de 2010, con el objetivo de ...

  5. Direccionar la sostenibilidad desde la junta directiva: un imperativo estratégico de empresas líderes en el mundo

    OpenAIRE

    Rodado Grijalba, Beatríz

    2015-01-01

    El propósito de esta investigación es demostrar la importancia de direccionar la sostenibilidad desde la Junta Directiva, dado el impacto que esta tiene en la materialización de la estrategia del largo plazo y en el modelo de negocio de las compañías -- Con base en el estudio teórico y de las prácticas que existen en empresas del mundo, se propone la generación de un modelo de gobierno corporativo que proporcione la arquitectura necesaria para lograr un adecuado direccionamiento de la sosteni...

  6. Reactor inventory monitoring system for Angra-1 reactor; Sistema de monitoracao de inventario do reator para usina nuclear Angra I

    Energy Technology Data Exchange (ETDEWEB)

    S Neto, Joaquim A.; Silva, Marcos C.; Pinheiro, Ronaldo F.M. [Furnas Centrais Eletricas S.A., Rio de Janeiro, RJ (Brazil); Soares, Milton [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Martinez, Aquilino; Comerlato, Cesar A.; Oliveira, Eugenio A. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Monitoracao de Processos

    1996-07-01

    This work describes the project of Reactor Inventory Monitoring System, which will be installed in Angra I Nuclear Power Plant. The inventory information is important to the operators take corrective actions in case of an incident that may cause a failure in the core cooling. (author)

  7. Preliminary analysis of an hydrogen generator system based on nuclear energy in the Laguna Verde site; Analisis preliminar de un sistema generador de hidrogeno basado en energia nuclear en el sitio de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Flores y Flores, A [FI-UNAM, 04500 Mexico D.F. (Mexico); Francois L, J L [FI-UNAM, Jiutepec, Morelos (Mexico)

    2003-07-01

    The shortage of fossil fuels in the next future, as well as the growing one demand of energetics and the high cost of the production of alternating fuels, it forces us to take advantage of to the maximum the fossil fuel with the one which we count and to look for the form of producing alternating fuels at a low cost and better even if these supply sources are reliable and non pollutants. It is intended a solution to the shortage of fuel; to use the thermal energy liberated of some appropriate nuclear reactor to be able to obtain a fuel but clean and relatively cheap as it is the hydrogen. In the first place the methods were looked for to produce hydrogen using thermal energy, later it was analyzed the temperature liberated by the existent nuclear reactors as well as the advanced designs, according to this liberated temperature settled down that the methods but feasible to produce hydrogen its were the one of reformed with water stream of the natural gas (methane) and the other one of the S-I thermochemical cycle, and the nuclear reactors that give the thermal energy for this production they are those of gas of high temperature. Once established the processes and the appropriate reactors, it was analyzed the site of Laguna Verde, with relationship to the free space to be able to place the reactor and the plant producer of hydrogen, as well as the direction in which blow the dominant winds and the near towns to the place, it was carried out an analysis of some explosion of tanks that could store hydrogen and the damage that its could to cause depending from the distance to which its were of the fire. Finally it was carried out an evaluation of capital and of operation costs for those two methods of hydrogen production. (Author)

  8. Acerca de la contribución militar de la Junta General de la provincia de Guipúzcoa a la Guerra de Granada en 1484

    Directory of Open Access Journals (Sweden)

    García Fernández, Ernesto

    2010-12-01

    Full Text Available The Guipuzcoans participated with their militias and their armed men in the war against Granada waged by the Catholic Monarchs Isabella and Ferdinand, from their ascension to the throne of the Crown of Castile to the conquest of the Muslim kingdom of Granada in 1492. In this paper we look into how several requests were made from the Province of Guipuzcoa for several ships with their respective armed crews in order to control the different points of access to the Strait of Gibraltar, on the one hand, and, on the other hand, we examine the replies given by the representatives of the Province councils after the Board Meeting at Usarraga.

    Los guipuzcoanos participaron con sus milicias y hombres armados en la Guerra de Granada auspiciada por los Reyes Católicos, Isabel y Fernando, desde su ascenso al trono de la Corona de Castilla hasta la conquista del reino nazarí en 1492. En este artículo se estudian por una parte las demandas a la Provincia Guipúzcoa de varias embarcaciones con sus respectivas tripulaciones armadas para controlar los accesos a Granada a través del Estrecho de Gibraltar y por otra las diversas respuestas dadas por los procuradores generales de los concejos de la Provincia, reunidos en la Junta General de Usarraga.

  9. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    matieres nucleaires ne se limite pas S de simples travaux d'inventaire mais sert de base a beaucoup d'autres activites qui font partie integrante du programme d'operations de tout reacteur, par exemple les expeditions de combustible irradie, le traitement chimique du combustible epuise et la comptabilite du combustible recupere et des matieres produites au cours du fonctionnement du reacteur, et l'institution et l'application d'un regime d'assurance satisfaisant. (author) [Spanish] Combustible relativamente nuevo y sumamente valioso para la produccion de energia electrica, el uranio requiere un control muy minucioso desde el momento en que la direccion de una central asume la responsabilidad financiera inherente a su posesion hasta que como combustible parcialmente agotado se transfiere a otra instalacion en la que se recupera la parte que no se ha consumido. Antes de que se descubriera la posibilidad de emplear la energia nuclear para producir electricidad, la mayor parte de las empresas que actualmente explotan centrales nucleares explotaban centrales alimentadas con combustibles fosiles y hablan establecido sistemas de control relativamente completos y adecuados para los combustibles de ese tipo. Los responsables de las centrales nucleoelectricas deben disponer de sistemas no menos adecuados para controlar los materiales nucleares especiales que utilizan. La explotacion de los reactores de potencia no es una ciencia antigua, pero durante el tiempo relativamente corto que ha transcurrido desde que se inicio su empleo los ingenieros y hombres de ciencia han mejorado continuamente el diseflo del equipo y los metodos de trabajo con objeto de disminuir los costos de produccion y de lograr que las centrales nucleares puedan competir en el plano economico con las centrales clasicas. La administracion de los materiales nucleares debe efectuarse con metodos modernos y eficientes a fin de que los adelantos tecnologicos que han permitido reducir los costos no resulten inutiles

  10. Nuclear reactor theory

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi

    2007-09-01

    This textbook is composed of two parts. Part 1 'Elements of Nuclear Reactor Theory' is composed of only elements but the main resource for the lecture of nuclear reactor theory, and should be studied as common knowledge. Much space is therefore devoted to the history of nuclear energy production and to nuclear physics, and the material focuses on the principles of energy production in nuclear reactors. However, considering the heavy workload of students, these subjects are presented concisely, allowing students to read quickly through this textbook. (J.P.N.)

  11. Interview in Radio Educacion on the applications of nuclear energy; Entrevista en Radio Educacion sobre las aplicaciones de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Balcazar G, M

    1991-01-15

    The objective that presides over this interview, is to show before the public the diverse applications that can have the nuclear energy, apart from the warlike aspect and the electric power generation. (Author)

  12. The waste originating from nuclear energy peaceful applications and its management; Os rejeitos provenientes de aplicacoes pacificas da energia nuclear e o seu gerenciamento

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Jair Albo Marques de [E-mail: jairalbo at ax.apc.org (Brazil)] [and others

    1997-05-01

    This work presents the waste originating from nuclear energy and its management. It approaches the following main topics: nature and classification of the wastes; security requirements to the waste management; state of the art related to the wastes derivates of the uses of the nuclear energy; wastes in the fuel cycle; wastes of the industrial, medical and research and development applications; costs of the waste management.

  13. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  14. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

    1981-01-01

    An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

  15. A digital method for period measurements in a nuclear reactor

    International Nuclear Information System (INIS)

    Mundim, Sergio Gorretta

    1971-02-01

    The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

  16. Noticias de la Academia de Medicina del Valle, Nueva Junta Directiva 2008-2010.

    Directory of Open Access Journals (Sweden)

    Antonio José Montoya Casella

    2008-06-01

    Con frecuencia la atención médica está acompañada de una tutela, que en muchas oportunidades se responde tardíamente. El mecanismo de la tutela ya hace parte del armamentario médico. El sistema nos ha llevado tanto a enfermos como a doctores a un triste pero real acuerdo “Las EPS no pueden perder, son un negocio que debe fortalecerse económicamente a base del trabajo mal remunerado del médico y de la reiterada insatisfacción del paciente”.

  17. CONSUMO DE ENERGIA ELÉTRICA: UMA ANÁLISE DE FONTE ALTERNATIVA DE COLETOR SOLAR DE BAIXO CUSTO

    OpenAIRE

    Ramon Alves de Oliveira; Murillo Ribeiro de Moura

    2015-01-01

    Com o aumento do consumo de energia elétrica e tarifas, a procura por geração de energias alternativas vem crescendo gradativamente, principalmente que sejam de baixo custo, assim possibilitando uma maior inclusão social beneficiando também as residências de baixa renda. Com o espírito de inovação a pesquisa buscou ideias simples que possam contribuir para a sociedade buscando alternativas sustentáveis e de baixo custo para a economia de energia elétrica Esse artigo teve como obje...

  18. Dynamics of TRIGA-3 Salazar Reactor.; Dinamica del Reactor TRIGA Mark III del Centro Nuclear de Mexico.

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo S, L F

    1991-12-31

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author).

  19. Triennial technical report - 1986, 1987, 1988 - Instituto de Engenharia Nuclear (IEN) -Dept. of Reactors (DERE)

    International Nuclear Information System (INIS)

    1989-01-01

    The research activities developed during the period 1986, 1987 and 1988 by the Reactor Department of Brazilian Nuclear Energy Commission (CNEN-DERE) are summarized. The principal aim of the Department of Reactors is concerned to the study and development of fast reactors and research thermal reactors. The DERE also assists the CNEN in the areas related to analysis of power reactor structure; to teach Reactor Physics and Engineering at the University, and professional training to the Nuclear Engineering Institute. To develop its research activity the DERE has three big facilities: Argonauta reactor, CTS-1 sodium circuit, and water circuit. (M.I.)

  20. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  1. UNIDADES GEOMORFOLÓGICAS DE PORTUGAL CONTINENTAL

    Directory of Open Access Journals (Sweden)

    Diamantino Insua Pereira

    2014-12-01

    Full Text Available São representadas cartograficamente as unidades geomorfológicas identificadas para os 89015 km2 do território de Portugal Continental. A delimitação das unidades teve por base a análise dos padrões da textura fornecida por imagens SRTM, com revisão e adaptação posterior à altimetria e à geologia, para os quais foram usadas bases cartográficas digitais. Foram considerados três níveis taxionómicos que permitem descrever e caracterizar áreas homogéneas do ponto de vista geomorfológico. As três unidades de 1º nível baseiam-se nas unidades morfostruturais clássicas consideradas para a Península Ibérica. As dez unidades de 2º nível constituem, na sua maioria, divisões clássicas do relevo de Portugal Continental, agora agrupadas de acordo com a metodologia adoptada e designadas como unidades morfosculturais. As 56 unidades de 3º nível, ou subunidades morfosculturais, foram individualizadas com base nos padrões de relevo identificados nas imagens SRTM e na observação de campo e adquiriram uma designação baseada essencialmente nas geoformas que as individualizam e na toponímia local. As unidades geomorfológicas identificadas são descritas através de características do relevo, dissecação fluvial, estruturas, tipo de drenagem e base geológica, bem como de parâmetros numéricos gerados de forma automática, como classes de altitude e de declividade. Pretende-se que o mapa elaborado possa contribuir para a gestão territorial, em especial na tomada de decisões em conservação da natureza.

  2. EL ALTO MAGDALENA- COLOMBIA DE LA MANO CON ENERGIAS ALTERNATIVAS

    Directory of Open Access Journals (Sweden)

    Barragán-Alturo, Ancízar

    2013-12-01

    Full Text Available El afán por destruir un paradigma, que mantiene encadenados a los habitantes de Girardot y la región, a una compañía de distribución de la energía eléctrica con sus altos precios para el kilowatt-hora, ha inspirado la investigación CUNDINAMARCA DE LA MANO DE LAS ENERGIAS ALTERNATIVAS, demostrando por diversos caminos que el montaje de paneles solares para generación de energía eléctrica en las cubiertas de las casas es la energía alternativa para la solución de diversos problemas, entre ellos: los costos elevados, las fluctuaciones de voltaje, los cortes de energía, los daños en los electrodomésticos

  3. Energy saving in the pumping of drinking water, Municipality of San Felipe, Guanajuato; Ahorro de energia electrica en bombeo de agua potable, en el municipio de San Felipe, Gto.

    Energy Technology Data Exchange (ETDEWEB)

    Gamiz Sanchez, Lorenzo [Applied Technology Center de Mexico, S.A. de C.V. (Mexico)

    2006-01-15

    This paper shows the results attained in energy saving through a project of potable water pumping, which took an investment of $433,043.00 and an internal rate of return of 126%. This project puts into evidence that it is possible to reduce between 15 and 30% of the total invoicing for energy consumption in potable water pumping if an equipment of poor efficiency is replaced by another of high efficiency. The project was requested by the Guanajuato's State Water Comision and the Municipal Bureau of Sewage and Potable Water, with the double intention of reducing the energy consumption along with the corresponding invoicing and incrementing the output of the wells in order to improve the potable water supply. In the site two high efficiency submersible motor-pumps were installed previously to the energy diagnosis that triggered profitable operation results and a convenient invoicing. [Spanish] Se documentan los resultados obtenidos en un proyecto de ahorro de energia en el bombeo de agua potable realizado con una inversion de $433,043.00 y con una tasa interna de retorno de 126%. Este proyecto pone en evidencia que es posible reducir entre el 15 y 30% de la facturacion total por consumo de energia electrica en el bombeo de agua potable si se sustituye un equipo poco eficiente por otro de alta eficiencia. El proyecto fue solicitado por la Comision Estatal del Agua de Guanajuato y la Junta Municipal de Agua Potable y Alcantarillado del municipio, con un doble proposito, reducir el consumo de energia junto con la facturacion correspondiente e incrementar la capacidad de produccion de los pozos con la intencion de mejorar el abasto de agua potable. En el lugar se instalaron dos motobombas sumergibles de alta eficiencia previo diagnostico energetico que desencadenaron rentables resultados operativos y de facturacion.

  4. La Actividad Económica de la Junta de Obras del Puerto de Cartagena: Análisis de su Política de Gestión al Inicio del Siglo XX (1900-1905). PARTE 1

    OpenAIRE

    Manuela Guzmán Raja; Isidoro Guzmán Raja

    2015-01-01

    El presente trabajo examina el contenido de las Memorias Económico-Administrativas de la Junta de Obras del Puerto de Cartagena (en adelante JOP) al comienzo del siglo XX, con el fin de analizar en la esfera de la contabilidad pública sus prácticas administrativas y contables para el reflejo de su actividad económica durante el periodo 1900-1905, espacio temporal que estuvo claramente marcado por la publicación de legislación de índole administrativa y contable (Reales Decreto de 1901 y 1903)...

  5. La actividad económica de la Junta de Obras del Puerto de Cartagena: análisis de su política de gestión al inicio del siglo XX (1900-1905)

    OpenAIRE

    Guzmán Raja, Isidoro; Guzmán Raja, Manuela

    2015-01-01

    [ESP] El presente trabajo examina el contenido de las Memorias Económico-Administrativas de la Junta de Obras del Puerto de Cartagena (en adelante JOP) al comienzo del siglo XX, con el fin de analizar en la esfera de la contabilidad pública sus prácticas administrativas y contables para el reflejo de su actividad económica durante el periodo 1900-1905, espacio temporal que estuvo claramente marcado por la publicación de legislación de índole administrativa y contable (Reales Decreto de 1901 y...

  6. La Actividad Económica de la Junta de Obras del Puerto de Cartagena: Análisis de su Política de Gestión al Inicio del Siglo XX (1900-1905). PARTE 2

    OpenAIRE

    Manuela Guzmán Raja; Isidoro Guzmán Raja

    2015-01-01

    El presente trabajo examina el contenido de las Memorias Económico-Administrativas de la Junta de Obras del Puerto de Cartagena (en adelante JOP) al comienzo del siglo XX, con el fin de analizar en la esfera de la contabilidad pública sus prácticas administrativas y contables para el reflejo de su actividad económica durante el periodo 1900-1905, espacio temporal que estuvo claramente marcado por la publicación de legislación de índole administrativa y contable (Reales Decreto de 1901 y 1903)...

  7. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    An improvement is proposed concerning the easier disengagement of the coupling at the reactor coolant pump for a nuclear reactor transporting a pressurized coolant. According to the invention the disengaging coupling consists of two parts separated by screws. At least one of the screws contains a propellent charge ananged within a bore and provided with a speed-dependent ignition device in such a way that by separation of the screws at overspeeds the coupling is disengaged. The sub-claims are concerned with the kind of ignition ot the propellent charge. (UWI) [de

  8. Nuclear research center transformation experience

    International Nuclear Information System (INIS)

    Diaz, J. L.; Jimenez, J. M.

    2001-01-01

    As consequence of the changes in the energy polities of each countries in the 80th. many of the Nuclear Research Centres suffered a transformation (more of less deep) in other Research and Development Centres with a wider spectrum that the exclusively nuclear one. This year is the 50 anniversary of the Spanish Centre of Nuclear Research-Junta de Energia Nuclear.The JEN the same as other suffered a deep renovation to become the CIEMAT Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (Research Centre for Energy, Environment and Technology). This paper is focussed on the evolution of JEN to CIEMAT besides analysing the reach of this re-foundation considering the political reasons and technical aspect that justified it and the laws in those it is based on. (Author)

  9. Development of the user interface for visualization of the auxiliary systems of the TRIGA Mark III nuclear reactor; Desarrollo de la interface de usuario para la visualizacion de los sistemas auxiliares del reactor nuclear Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Merced D, J. E.

    2016-07-01

    The Instituto Nacional de Investigaciones Nucleares (ININ) has a nuclear research reactor type swimming pool with movable core cooled and moderate with light water. The nominal maximum power of the reactor is 1 MW in steady-state operation and can be pulsed at a maximum power of 2,000 MW for approximately 10 milliseconds. This reactor is mainly used to study the effects of radiation on various materials and substances. In 2001 the new control console of the nuclear reactor was installed which was based on two digital computers, one computer controls the bar management mechanisms and the other the systems to the reactor operator. In 2004, the control computer was replaced and the software was updated. Within the modernization and/or updating of the TRIGA Mark III reactor of ININ, is intended (theme of this work) to develop the user interface for the visualization of the auxiliary systems, through a Man-Machine Interface module for the renewal process of the control console. The man-machine interface system to be developed will have communication with the programmable logic controllers that will be constantly monitored and controlled to obtain real-time variables of the reactor behavior. (Author)

  10. Calculation of reactivity for safety in nuclear reactors; Calculo de la reactividad para seguridad en reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Suescun D, D. [Universidad Surcolombiana, Av. Pastrana Borrero - Carrera 1, Neiva, Huila (Colombia); Rojas A, O., E-mail: daniel.suescun@usco.edu.co [Universidad Popular Autonoma del Estado de Puebla, Av. 9 Pte 1908, Barrio de Santiago, 72410 Puebla (Mexico)

    2017-09-15

    The measurement of reactivity is a function of time and its calculation results from the variation in nuclear power from the inverse equation of punctual kinetics. This equation is a differential integral, where the term of the integral conserves the historical power and the differential part is directly related to the period of the reactor. In practice, in a nuclear plant, sensors are required to record the signals. For example, the movements of the control rods that cause the fluctuations of nuclear power over time commonly generate signals with noise, an event that makes difficult to estimate the reactivity. Thus is necessary and very useful to build digital reactivity meters in real time, since allows a reactor to be operated with greater security. The calculation of the reactivity is carried out using punctual kinetics, especially the concentration of delayed neutron precursors. In this work we present a new way to reduce the fluctuations in the calculation of the reactivity, for the high precision we propose the generalization of the predictor and corrector of the Adams-Bashforth-Moulton (ABM) method of order 4 to solve numerically the equations of the point kinetics for the calculation of the reactivity, without using the power history, due to the nature of the equations of the punctual kinetics, the modifiers of the different predictors are used to increase the accuracy in the approximation obtained accompanied by the filter known as Savitzky-Golay (Sg), allow to reduce the fluctuations of reactivity. It is known that the Sg filter softens and does not attenuate the nuclear power regardless of its shape, guarantees to reduce noise levels up to σ = 0.01, with a calculation time step of σ = 0.01, s. This formulation uses a polynomial approximation of Gram, with a degree d = 2, to calculate the convolution coefficients by means of an analytical formula that is implemented computationally and avoids problems of bad conditioning, caused by the inversion of a

  11. Sodium-cooled nuclear reactor

    International Nuclear Information System (INIS)

    Hammers, H.W.

    1982-01-01

    The invention concerns a sodium-cooled nuclear reactor, whose reactor tank contains the primary circuit, shielding surrounding the reactor core and a primary/secondary heat exchanger, particularly a fast breeder reactor on the module principle. In order to achieve this module principle it is proposed to have electromagnetic circulating pumps outside the reactor tank, where the heat exchanger is accomodated in an annular case above the pumps. This case has several openings at the top end to the space above the reactor core, some smaller openings in the middle to the same space and is connected at the bottom to an annular space between the tank wall and the reactor core. As a favoured variant, it is proposed that the annular electromagnetic pumps should be arranged concentrically to the reactor tank, where there is an annual duct on the inside of the reactor tank. In this way the sodium-cooled nuclear reactor is made suitable as a module with a large number of such elements. (orig.) [de

  12. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  13. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  14. De "átomos para la paz" a los reactores de potencia: Tecnología y política nuclear en la Argentina (1955-1976)

    OpenAIRE

    Hurtado de Mendoza, Diego

    2005-01-01

    Durante el período 1955-76, el programa nuclear argentino se integró a la arena internacional; su Comisión Nacional de Energía Atómica construyó cuatro reactores de investigación, adquirió a una empresa alemana y puso en marcha el primer reactor de potencia Atucha I, y compró a una empresa canadiense un segundo reactor de potencia. En este artículo se examinan estos desarrollos en relación con el contexto político local y con el panorama nuclear internacional. En particular, se analizan la po...

  15. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde; Cuestionamientos al aumento de potencia de los reactores de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B., E-mail: salasmarb@yahoo.com.mx [UNAM, Facultad de Ciencias, Departamento de Fisica, Circuito exterior s/n, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2014-08-15

    The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

  16. Study of essential safety features of a three-loop 1,000 MWe light water reactor (PWR) and a corresponding heavy water reactor (HWR) on the basis of the IAEA nuclear safety standards

    International Nuclear Information System (INIS)

    1989-02-01

    Based on the IAEA Standards, essential safety aspects of a three-loop pressurized water reactor (1,000 MWe) and a corresponding heavy water reactor were studied by the TUeV Baden e.V. in cooperation with the Gabinete de Proteccao e Seguranca Nuclear, a department of the Ministry which is responsible for Nuclear power plants in Portugal. As the fundamental principles of this study the design data for the light water reactor and the heavy water reactor provided in the safety analysis reports (KWU-SSAR for the 1,000 MWe PWR, KWU-PSAR Nuclear Power Plant ATUCHA II) are used. The assessment of the two different reactor types based on the IAEA Nuclear Safety Standards shows that the reactor plants designed according to the data given in the safety analysis reports of the plant manufacturer meet the design requirements laid down in the pertinent IAEA Standards. (orig.) [de

  17. Reactors. Nuclear propulsion ships

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2001-01-01

    This article has for object the development of nuclear-powered ships and the conception of the nuclear-powered ship. The technology of the naval propulsion P.W.R. type reactor is described in the article B.N.3 141 'Nuclear Boilers ships'. (N.C.)

  18. The Text of the Agreement between Belgium, Denmark, the Federal Republic of Germany, Ireland, Italy, Luxembourg, The Netherlands, the European Atomic Energy Community and the Agency in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons; Texto del Acuerdo Concertado Entre Belgica, Dinamarca, La Republica Federal De Alemania, Irlanda, Italia, Luxemburgo, Los Paises Bajos, La Comunidad Europea De Energia Ato Mica Y El Organismo En Relacion Con El Tratado Sobre La No Proliferacion De Las Armas Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-09-14

    The text of the Agreement, and of the Protocol thereto, between Belgium, Denmark, the Federal Republic of Germany, Ireland, Italy, Luxembourg, The Netherlands, the European Atomic Energy Community and the Agency in implementation of Article III (1) and (4) of the Treaty on the Non-Proliferation of Nuclear Weapons (reproduced in document INFCIRC/140) is reproduced in this document for the information of all Members [Spanish] Para informacion de todos los Estados Miembros, en el presente documento se transcribe el texto del Acuerdo concertado entre Belgica, Dinamarca, la Republica Federal de Alemania, Irlanda, Italia, Luxemburgo, los Paises Bajos, la Comunidad Europea de Energia Atomica y el Organismo en ejecucion de lo dispuesto en los parrafos 1 y 4 del articulo III del Tratado sobre la no proliferacion de las armas nucleares, asi como el del Protocolo que acompana a dicho Acuerdo.

  19. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  20. Rol gerencial en las juntas parroquiales rurales del Ecuador en la implementación de políticas públicas

    Directory of Open Access Journals (Sweden)

    Baly Ilovasky Vera Montenegro

    2017-07-01

    Full Text Available Este artículo tiene como objetivo determinar el rol gerencial de las autoridades seccionales en las juntas parroquiales rurales, relacionada con la implementación de políticas públicas, para lo cual se explora diversos conceptos sobre organización, su tipología, la gerencia, la interrelación de la gerencia en la implementación de política pública, también se analiza la toma de decisiones.   Palabras clave: implementacion, políticas públicas, rol, organizacion.

  1. Hydrogen production through nuclear energy, a sustainable scenario in Mexico; Produccion de hidrogeno mediante energia nuclear, un escenario sostenible en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ortega V, E.; Francois L, J.L. [Departamento de Sistemas Energeticos, Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)]. e-mail: iqoren@gmail.com

    2007-07-01

    The energy is a key point in the social and economic development of a country, for such motive to assure the energy supply in Mexico it is of vital importance. The hydrogen it is without a doubt some one of the alternating promising fuels before the visible one necessity to decentralize the energy production based on hydrocarbons. The versatility of their applications, it high heating power and having with the more clean fuel cycle of the energy basket with which count at the moment, they are only some examples of their development potential. However the more abundant element of the universe it is not in their elementary form in our planet, it forms molecules like in the hydrocarbons or water and it stops their use it should be extracted. At the present time different methods are known for the extraction of hydrogen, there is thermal, electric, chemical, photovoltaic among others. The election of the extraction method and the primary energy source to carry out it are decisive to judge the sustainability of the hydrogen production. The sustainable development is defined as development that covers the present necessities without committing the necessity to cover the necessities of the future generations, and in the mark of this definition four indicators of the sustainable development of the different cycles of fuel were evaluated in the hydrogen production in Mexico. These indicators take in consideration the emissions of carbon dioxide in the atmosphere (environment), the readiness of the energy resources (technology), the impacts in the floor use (social) and the production costs of the cycles (economy). In this work the processes were studied at the moment available for the generation of hydrogen, those that use coal, natural gas, hydraulic, eolic energy, biomass and nuclear, as primary energy sources. These processes were evaluated with energy references of Mexico to obtain the best alternative for hydrogen production. (Author)

  2. Analytical study of the prospectives published by the Secretaria de Energia; Estudio analitico de las prospectivas publicadas por la Secretaria de Energia

    Energy Technology Data Exchange (ETDEWEB)

    Beltran Mora, Hector Alejandro; Urias Romero, Francisco [Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico, Mexico, D.F. (Mexico)

    2004-06-15

    Since 1997 the Secretaria de Energia (SENER) publishes an annual report named Prospectiva del Sector Electrico, in which detailed information on the situation of the Mexican electrical sector is included, the information is related to the technological, economic and environmental aspects of all the organisms involved in the matter of electrical energy, within which stand out the Comision Federal de Electricidad (CFE), Luz y Fuerza del Centro (LyFC), the Comision Reguladora de Energia (CRE) and the Comision Nacional para el Ahorro de Energia (CONAE). In the prospectives the tendency of the modifications that will undergo the sector in a period of 10 years is analyzed. All the prospectives of the electrical sector, agree in that the growth of this sector is determined by the construction of power stations that use natural gas as primary energy, reason why we made an analysis of the prospectives of the natural gas market, with the purpose of observing the interaction between both sectors. At the moment seven prospectives of each sector have been published, given the conditions at the moment of their publication, they present differences and agreements between each other for periods of intersection. The present work shows the comparison between the expectations of growth reported by each one of the Prospectives. [Spanish] Desde 1997 la Secretaria de Energia (SENER) publica un reporte anual llamado Prospectiva del Sector Electrico, en el que se incluye informacion detallada sobre la situacion del sector electrico mexicano, la informacion esta relacionada con los aspectos tecnologicos, economicos y medioambientales de todos los organismos involucrados en materia de energia electrica, dentro de los cuales destacan la Comision Federal de Electricidad (CFE), Luz y Fuerza del Centro (LyFC), la Comision Reguladora de Energia (CRE) y la Comision Nacional para el Ahorro de Energia (CONAE). En las prospectivas se analiza la tendencia de las modificaciones que sufrira el sector

  3. Dispositivo de posicionamiento de muestras biológicas para su irradiación en un canal radial de un reactor nuclear // Biological samples positioning device for irradiations on a radial channel at the nuclear research reactor

    Directory of Open Access Journals (Sweden)

    Maritza Rodríguez - Gual

    2010-05-01

    Full Text Available ResumenPor la demanda de un dispositivo experimental para el posicionamiento de las muestras biológicaspara su irradiación en un canal radial de un reactor nuclear de investigaciones en funcionamiento, seconstruyó y se puso en marcha un dispositivo para la colocación y retirada de las muestras en laposición de irradiación de dicho canal. Se efectuaron las valoraciones económicas comparando conotro tipo de dispositivo con las mismas funciones. Este trabajo formó parte de un proyectointernacional entre Cuba y Brasil que abarcó el estudio de los daños inducidos por diferentes tipos deradiación ionizante en moléculas de ADN. La solución propuesta es comprobada experimentalmente,lo que demuestra la validez práctica del dispositivo. Como resultado del trabajo, el dispositivoexperimental para la irradiación de las muestras biológicas se encuentra instalado y funcionando yapor 5 años en el canal radial # 3(BH#3 Palabras claves: reactor nuclear de investigaciones, dispositivo para posicionamiento de muestras,___________________________________________________________________________AbstractFor the demand of an experimental device for biological samples positioning system for irradiationson a radial channel at the nuclear research reactor in operation was constructed and started up adevice for the place and remove of the biological samples from the irradiation channels withoutinterrupting the operation of the reactor. The economical valuations are effected comparing withanother type of device with the same functions. This work formed part of an international projectbetween Cuba and Brazil that undertook the study of the induced damages by various types ofionizing radiation in DNA molecules. Was experimentally tested the proposed solution, whichdemonstrates the practical validity of the device. As a result of the work, the experimental device forbiological samples irradiations are installed and operating in the radial beam hole #3(BH#3

  4. Desalination of seawater with nuclear power reactors in cogeneration; Desalacion de agua de mar con reactores nucleares de potencia en cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Flores E, R M

    2004-07-01

    The growing demand for energy and hydraulic resources for satisfy the domestic, industrial, agricultural activities, etc. has wakened up the interest to carry out concerning investigations to study the diverse technologies guided to increase the available hydraulic resources, as well as to the search of alternatives of electric power generation, economic and socially profitable. In this sense the possible use of the nuclear energy is examined in cogeneration to obtain electricity and drinkable water for desalination of seawater. The technologies are analysed involved in the nuclear cogeneration (desalination technology, nuclear and desalination-nuclear joining) available in the world. At the same time it is exemplified the coupling of a nuclear reactor and a process of hybrid desalination that today in day the adult offers and economic advantages. Finally, the nuclear desalination is presented as a technical and economically viable solution in regions where necessities of drinkable water are had for the urban, agricultural consumption and industrial in great scale and that for local situations it is possible to satisfy it desalinating seawater. (Author)

  5. Nuclear reactor control apparatus

    International Nuclear Information System (INIS)

    Sridhar, B.N.

    1983-01-01

    Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod

  6. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1981-01-01

    An array of rods comprising zirconium alloy sheathed nuclear fuel pellets assembled to form a fuel element for a pressurised water reactor is claimed. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  7. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1984-01-01

    The fuel elements for a pressurised water reactor comprise arrays of rods of zirconium alloy sheathed nuclear fuel pellets. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  8. Nuclear reactor core catcher

    International Nuclear Information System (INIS)

    1977-01-01

    A nuclear reactor core catcher is described for containing debris resulting from an accident causing core meltdown and which incorporates a method of cooling the debris by the circulation of a liquid coolant. (U.K.)

  9. Modelamiento y simulación del efecto de la entrada de calor en la penetración de una junta soldada

    Directory of Open Access Journals (Sweden)

    Lina Gómez

    2003-01-01

    Full Text Available En esta investigación se realizó el simulador SimVol, en el cual se experimentó con el fin de encontrar una relación entre la entrada de calor y la penetración de la junta soldada. SimVol se basó en un modelo en 2D, que describe el flujo de calor y el flujo de metal líquido en el charco de una soldadura realizada con el proceso GTAW (Gas Tungsten Arc Welding. En el modelo matemático se incluyen las ecuaciones de Navier-Stokes y la ecuación de energía, las cuales constituyen un sistema de ecuaciones diferenciales parciales de segundo orden, no-lineales, no homogéneas y transitorias. El modelo numérico se desarrolla en Volúmenes Finitos en un esquema totalmente implícito, con malla regular y escalonada; además, debido al desconocimiento del campo de presión es necesario utilizar el algoritmo SIMPLE (Semi-Implicit Method for Pressure-Linked Equations. La investigación también incluye una serie de experimentos que permitieron validar el modelo planteados.

  10. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  11. Resistência à corrosão de junta dissimilar soldada pelo processo TIG composta pelos aços inoxidáveis AISI 316L e AISI 444

    Directory of Open Access Journals (Sweden)

    Luis Henrique Guilherme

    2014-03-01

    Full Text Available O aço inoxidável AISI 444 tornou-se uma opção para substituir a liga AISI 316L devido ao seu menor custo e satisfatória resistência à corrosão. Entretanto, o uso da liga AISI 444 no feixe tubular de trocadores de calor acarreta na soldagem de uma junta dissimilar. O presente estudo teve por objetivo avaliar a resistência à corrosão da junta tubo-espelho soldada pelo processo TIG composta pelas ligas AISI 316L e AISI 444. A manufatura das amostras consistiu em replicar o projeto da junta tubo-espelho de trocadores de calor. Realizou-se em juntas soldadas ensaios de sensitização, perda de massa por imersão desde a temperatura ambiente até 90 ºC, e ensaios eletroquímicos de polarização potenciodinâmica nos eletrólitos 0,5 mol/L de HCl e 0,5 mol/L de H2SO4. Os resultados mostraram que a junta dissimilar sofreu corrosão galvânica com maior degradação na zona afetada pelo calor (ZAC do tubo AISI 444. Porém, os mecanismos de corrosão localizada (pite e intergranular demonstraram ser mais ativos para a liga AISI 316L. Conclui-se que a junta dissimilar apresentou melhor resistência à corrosão do que a junta soldada composta unicamente pela liga AISI 316L em temperaturas de até 70 ºC, conforme as condições observadas neste trabalho.

  12. Nuclear reactor simulator

    International Nuclear Information System (INIS)

    Baptista, Vinicius Damas

    1996-01-01

    The Nuclear Reactor Simulator was projected to help the basic training in the formation of the Nuclear Power Plants operators. It gives the trainee the opportunity to see the nuclear reactor dynamics. It's specially indicated to be used as the support tool to NPPT (Nuclear Power Preparatory Training) from NUS Corporation. The software was developed to Intel platform (80 x 86, Pentium and compatible ones) working under the Windows operational system from Microsoft. The program language used in development was Object Pascal and the compiler used was Delphi from Borland. During the development, computer algorithms were used, based in numeric methods, to the resolution of the differential equations involved in the process. (author)

  13. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-06

    We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

  14. Spanish regulatory perspective for the decommissioning of an old civilian nuclear research centre (CIEMAT)

    International Nuclear Information System (INIS)

    Gil, E.; Revilla, J.L.; Rodrigo, F.; Ortiz, J.

    1999-01-01

    The Center for Energy-related, Environmental and Technical Research (CIEMAT) is the main Spanish energy research center. CIEMAT is the heir of the former Nuclear Energy Board (Junta de Energia Nuclear - JEN), which was created in 1951 with a view to promoting the development and use of nuclear energy in Spain. Most of the centres for civilian nuclear research created in the fifties, like the JEN, had among their basic objectives to carry out investigations guided to the industrial development of the nuclear fuel cycle. The majority of them were endowed with experimental facilities that reproduced in a pilot scale the different stages of the full nuclear cycle facilities. The JEN main experimental facilities were: Plants for the treatment of uranium ores and for the concentration process; The manufacturing of fuel elements for research reactors; The JEN-1 thermal neutron experimental reactor, and CORAL fast reactor; The pilot plant for the treatment of irradiated fuel (M-1); The metallurgical hot cells for research relating to irradiated fuel; and Plants for the treatment and storage of liquid radioactive wastes. It should be pointed out that most of these installations were designed, built, operated, and even definitively shut down, prior a regulatory system as currently conceived is in force. The Science Act was passed in 1986, transforming the JEN into CIEMAT, and assigning to the latter a series of new functions, while making it the direct heir of the assets and strategic functions of its predecessor. The CIEMAT continued the process of 'denuclearization' of the installations inherited from the JEN, and used certain of them for the performance of research projects oriented towards the development of decontamination and dismantling techniques. (author)

  15. Nuclear energy + solar energy, why not?; Energia nuclear + energia solar, por que no?

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez C, I.; Nelson E, P., E-mail: ihernandezc91@hotmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2016-09-15

    Clean energies such as nuclear and solar are part of the solution to the energy dependence that we face today and also help us to reduce the greenhouse gas emissions, thus avoiding a global average temperature increase that is irreversible and harmful to all living beings on the planet. Independently the nuclear and solar energies have had a great development in recent years, so in this work we set ourselves the task of creating a synergy between them. First, we conducted a survey of different people involved in the area of energy (energy efficiency, clean energy and renewable sources) in order to know if the area of which they are part influences with respect to the impression that they have of safety in terms of supply, return on investment and safety to the health and environment of another energy source for which we use a correlation analysis. With the results obtained we propose to use photo thermic solar energy as a support to reduce the frequency of accidents by station blackout and we perform the analysis of the combination using the methodology of Probabilistic Analysis of Security with the help of SAPHIRE 7 software to realize the event trees by station blackout of a nuclear power plant and faults for a photo-thermal solar plant. Finally, the decrease in the probability of station blackout from the proposed combination is quantified. The results were favorable to indicate that the probability of station blackout is reduced in half and that is why is suggested to continue studying the combination. (Author)

  16. Las juntas de administración de servicios de saneamiento básico para una gestión sostenible en el distrito de Kimbiri - La Convención - Cusco

    OpenAIRE

    Palomino Figueroa, Luis Ángel

    2015-01-01

    El presente trabajo se realiza en el distrito de Kimbiri, provincia de La Convención, Región Cusco con el objetivo de determinar los factores que afectan la gestión sostenible de las Juntas de Administración de Servicios de Saneamiento Básico (JASS) del distrito de Kimbiri y proponer los instrumentos de gestión para su desarrollo sostenible, para ello, es necesario determinar y evaluar el presupuesto, el personal capacitado para la gestión sostenible, la percepción de la población sobre la ge...

  17. Avaliação económica de um investimento em geração de energia das ondas e energia solar térmica

    OpenAIRE

    Nunes, Ruben Fernando Lopes

    2012-01-01

    O presente trabalho tem como objectivo efectuar a avaliação económica e determinar a viabilidade com e sem os incentivos fiscais de duas tecnologias de conversão de duas fontes distinta e emergentes de energia renovável, o Concentrador Cilindro-parabólico e a Torre Solar para a energia solar termoeléctrica e a Coluna de Água Oscilante e o Pelamis para a energia das ondas. Realiza-se uma curta abordagem à energia Solar e à energia dos Oceanos, e às tecnologias existentes para estes tipos de en...

  18. Analysis and application of a simulator of a nuclear reactor AP-600; Analisis y aplicacion de un simulador de un reactor nuclear AP-600

    Energy Technology Data Exchange (ETDEWEB)

    Medina S, V. S. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: medina_victor@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Division de Ingenieria Electrica, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (MX)

    2011-11-15

    In front of the resurgence of interest in the nuclear power production, several national organizations have considered convenient to have highly specialized human resources in the technologies of nuclear reactors of III + and IV generation. For this task, the intensive and extensive applications of the computation should been considered, as the virtual instrumentation. The present work analyzes the possible applications of a nuclear simulator provided by the IAEA with base in the design of the reactor AP-600, using a focusing of modular model developed in FORTRAN. One part of the work that was made with the simulator includes the evaluation of 21 transitory events of operation, including the recreation of the accident happened in the nuclear power plant of Three Mile Island in 1979, comparing the actions flow and the answer of the systems under the intrinsic security of a III + generation reactor. The impact that had the mentioned accident was analyzed in the growing of the nuclear energy sector and in the public image with regard to the nuclear power plants. An application for this simulator was proposed, its use as tool for the instruction in the nuclear engineering courses using it to observe the operation of the different security systems and its interrelation inside the power plant as well as a theoretical/practical approach for the student. (Author)

  19. Estudo Experimental e Numérico de Tensões Residuais em Juntas Soldadas com e sem Restrição

    Directory of Open Access Journals (Sweden)

    Daniel Casassola Gonçalves

    Full Text Available Resumo O conhecimento das tensões residuais geradas nos processos de soldagem apresenta especial importância no desempenho das estruturas e componentes soldados, pois durante a vida em serviço eles estarão sujeitos a diferentes níveis de carregamentos, que associados aos campos de tensões residuais pré-existentes podem levar à ruptura inesperada. Neste contexto, o presente trabalho tem como objetivo estudar o nível das tensões residuais geradas em juntas soldadas, pelo processo arame tubular (FCAW - Flux Cored Arc Welding, de aço ASTM A 131 Grau A, usadas na construção naval, por difração de raios-X, usando a técnica do sen2ψ. Foi realizado um estudo comparativo das mudanças nos campos de tensões quando adotadas restrições para manter a geometria de projeto da junta, bem como uma análise numérica computacional pelo método de elementos finitos, com os resultados obtidos pelo método experimental. A maioria dos resultados das tensões residuais mostrou que houve similaridade qualitativa, na sua natureza, entre o modelo e os experimentos nas regiões da zona termicamente afetada e do metal de solda. As análises de microdureza Vickers e a caracterização microestrutural por microscopia óptica das juntas soldadas complementaram o presente estudo.

  20. Energia solar no tratamento de corante têxtil

    Directory of Open Access Journals (Sweden)

    Viviane Farias Silva

    2014-10-01

    Full Text Available As indústrias utilizam a água em todo o seu processo, desperdiçando enormes volumes de água gerando efluentes com altos índices de produtos químicos, precisando de tratamento para ser reutilizado ou lançado no meio ambiente. Nesse contexto, o presente trabalho foi realizado no Laboratório de Engenharia Ambiental e de Qualidade na Universidade Federal de Pernambuco objetivando-se a degradação de corante utilizados nas indústrias têxtis através do uso da energia solar como alternativa de tratamento de efluente. Nesta pesquisa os testes fotocatalíticos foram realizados com o catalisador em pó (TiO2 - P25, contendo o corante têxtil Remazol Amarelo Ouro RNL (RGY ou sem catalisador nos testes de fotólise. Foram testados dois tipos de radiação, a artificial e a energia solar (natural. Para avaliar a descoloração e a degradação das amostras, a Espectroscopia UV-visível foi a principal técnica analítica empregada como também realizadas análises de Carbono Orgânico Total (COT e Demanda Química de Oxigênio (DQO. Nas 6 (seis analises realizadas obteve-se um elevado índice de remoção da cor do corante, superior a 97%, com alta eficiência do processo com uma significativa redução da COT e da DQO. Os métodos utilizados foram eficientes na descoloração do RGY, como também na sua degradação, tornando-se uma técnica inovadora com o uso da energia solar para o tratamento de efluentes têxteis.Palavras-chave: efluente industrial, alternativa sustentável, degradação do remazol amarelo ouro, descoloração de efluente

  1. Identificación metalográfica de fases en una junta soldada de acero estructural microaleado y su influencia en el mecanismo de fractura

    Directory of Open Access Journals (Sweden)

    Porras-Arévalo, G. O.

    2005-12-01

    Full Text Available This study seeks to characterize the present phases through welded joint zones of structural steel and to describe the fracture mechanism, offering a support to the metallic construction industry. In most cases, structural designers associate weldments in this construction type with the brittleness in its structure, with the drop toughness and with a high collapse risk for the ductile-brittle transition.

    Este estudio pretende caracterizar las fases presentes a través de las zonas de una junta soldada de acero estructural y describir el mecanismo de fractura, ofreciendo un soporte a la industria de la construcción metálica. En la mayoría de los casos, la utilización de la soldadura en este tipo de construcción se asocia, por los diseñadores estructurales, con la fragilidad de su estructura, con la baja tenacidad y con un alto riesgo de colapso por la transición dúctil-frágil.

  2. Energy saving plan: use of solar energy in the university of Valencia (Spain); Uso de la energia solar en la universidad de Valencia (Espana) para ahorrar energia electrica

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Gomez Amo, J.L.; Tena, F.; Martinez Lozano, J.A.; Utrillas, M.P. [Grupo de Radiacion Solar, Universidad de Valencia (Spain)

    2005-07-15

    The University of Valencia financed a pilot project that would study the installation's feasibility of a generating station with photovoltaic energy, solar type, in order to replace or complement conventional sources of energy. This paper presents some of the preliminary results of the study's application in an University building, along with the analysis of the initial situation and the proposals for the handling of reactive energy and the outer and inner lighting as solutions for energy saving. This experimental project entitled Study of the Energy Saving Strategies and the Viability of Installing Solar Energy equipment in the Buildings of the University of Valencia throws preliminary data specifying the amount of investment necessary to obtain real annual benefits, as well as the recovery time of the investment and the beneficial ecological impact in quantitative terms of a measurable CO{sub 2} reduction. [Spanish] La Universidad de Valencia financio un proyecto piloto que estudiaria la factibilidad de instalacion de una estacion generadora de energia fotovoltaica de tipo solar para sustituir o complementar fuentes convencionales de energia. Este trabajo presenta algunos de los resultados preliminares de la aplicacion del estudio en un edificio de la Universidad junto con el analisis de la situacion inicial y las propuestas del manejo de energia reactiva, de iluminacion exterior e interior como soluciones para el ahorro de energia. Este proyecto experimental titulado Estudio de las estrategias del ahorro de la energia y de la viabilidad de instalar energia solar en los edificios de la Universidad de Valencia arroja datos preliminares que especifican el monto de la inversion necesaria para obtener beneficios anuales reales, asi como el tiempo de recuperacion de la inversion y el impacto ecologico benefico en terminos cuantitativos de una reduccion cuantificable de CO{sub 2}.

  3. Nuclear energy, energy for the present and the future; Energia nuclear, una energia para el presente y el futuro

    Energy Technology Data Exchange (ETDEWEB)

    Arredondo S, C. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: cas@nuclear.inin.mx

    2008-07-01

    In this work we will try to show that nuclear energy can contribute to the generation energy in the present and the future, considering that its effect on the climatic change is relatively low and that the fuels that uses are available a large scale. At the moment it is had already commercial thermal fission reactors , there are also them of fast fission that allow the fuel rearing, although these last ones in much smaller number, with both types of fission nuclear reactors can be obtained a very important contribution to the generation of energy at world-wide level during the time that is necessary so that it is developed, constructs and operates the first commercial fusion reactor. The energy that is generated in the present and future must come from different sources, which require to be reliable, to have little effect on the environment, to have wide reserves of fuels and to be viable from an economic and social point of view, they must be viable and safe. Between possible alternative energies it is counted on the lot, the wind one, the geothermal one, originating of the tides and some others. An energy that must be considered so that it has arrived at his maturity and he is already able to contribute widely to cover the present needs and future it is nuclear energy, as much the originating one of the fission of a heavy centre like obtained when fusing two light centers. On base in the nuclear fuel reserves at world-wide level a simple calculation takes control of the lapse in which energy by means of the nuclear fission in rearing can be generated reactors expresses demonstrating that the time sufficient to finish to the investigation and development of fusion reactors which they generate energy in economic, safe and reliable form. Combining these two options the nuclear energy can be considered the future like for the present and the future with practically null effects in the climatic change. (Author)

  4. HOMOGENEOUS NUCLEAR POWER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  5. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  6. Energy saving programs and renewable energies in Chihuahua, Mexico; Programas de ahorro de energia y energias renovables en Chihuahua, Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ibarra Noris, Jose Luis [Gobierno del Estado de Chihuahua (Mexico)

    2005-07-01

    The high index of economic and technological growth registered in the border zone of northern Mexico in the last years, has simultaneously caused an annual growth in the electrical energy demand in a percentage higher than 6%. In this document are included the economic and environmental impacts caused by the projects developed in the Chihuahua State on energy efficiency and on the available potential of renewable energies. In order to evaluate the environmental impact that is caused when saving electrical energy in the diverse projects in process, the emission of CO{sub 2} is the only emission taken into account (even though also emissions of SO{sub 2}, NO{sub 2} and Hg exist) for being this polluting agent the one that contributes in greater amount to the global warming and the greenhouse effect. The emission index of CO{sub 2} that we considered in this presentation is of 600 kg/mwh, on the basis of the type of fuel and volume of generation of the plants in operation of the Comision Federal de Electricidad (CFE) in the Chihuahua State. [Spanish] El alto indice de crecimiento economico y tecnologico registrado en la zona fronteriza del norte de Mexico en los ultimos anos, ha ocasionado paralelamente un crecimiento en la demanda de energia electrica superior al 6% anual. En este documento se incluyen los impactos economicos y ambientales de los proyectos que se desarrollan en el estado de Chihuahua en eficiencia energetica y en el potencial que se tiene de energias renovables. Para evaluar el impacto ambiental que se obtiene al ahorrar energia electrica en los diversos proyectos en proceso, se toma en cuenta unicamente emisiones de CO{sub 2} (aun cuando tambien existen emisiones de SO{sub 2}, NO{sub 2} y Hg) por ser este el contaminante que en mayor cantidad afecta al calentamiento global y al efecto invernadero. El indice de emisiones de CO{sub 2} que consideramos en esta presentacion es de 600 kg/mwh, en base al tipo de combustible y volumen de generacion de las

  7. El legado de la Real Expedición Filantrópica de la Vacuna (1803-1810: las juntas de vacuna

    Directory of Open Access Journals (Sweden)

    Ramírez Martín, Susana María

    2004-06-01

    Full Text Available The Royal Vaccination Expedition, directed by the physicians Francisco Xavier Balmis and José Salvany, was the most important scientific and medical achievement of the Spanish colonial era. It took place at a time of political restlessness, and its achievements were thus conditioned by each of the cultures into which the vaccine was introduced. As its legacy, the philantropic expedition left the Vaccination Boards, established in the Americas as centers of medical expertise to sustain the expedition´s principal objetive: the battle against the smallpox epidemics in pursuit of public health.

    La Expedición de la Vacuna, dirigida por los médicos Francisco Xavier Balmis y José Salvany, es la gesta científica y sanitaria más importante de época colonial. Su desarrollo tuvo lugar en un momento político convulso y los resultados estuvieron condicionados por las sociedades donde la vacuna se estableció. El legado de esta expedición filantrópica fue la creación de las Juntas de Vacuna. Estas instituciones se erigieron como centros creadores de saber médico en América y consolidaron el objetivo primario de la expedición: la búsqueda de la salud pública luchando contra las epidemias de viruela.

  8. Development of technologies for nuclear reactors of small and medium sized

    International Nuclear Information System (INIS)

    2011-08-01

    This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

  9. Risk control in energy saving projects; Control de riesgo en los proyectos de ahorro de energia

    Energy Technology Data Exchange (ETDEWEB)

    Mills, Evan [Lawrence Berkeley National Laboratory, CA (United States)

    2005-10-15

    Since one of the restrictive problems when investing in energy saving is the uncertainty of obtaining the planed savings, a technique in the risk handling for energy efficiency projects, called Insurance for the Energy Saving (IES) is presented. IES economically stimulates those who implement projects for energy saving so they go beyond the normal measures and really obtain significant saving levels, thus contributing to the fulfillment of national objectives in energy saving. In order to reduce the risk of low performance in energy caused by saving projects there exist the international performance measurement and the protocol of investment (IMPVP) as well as diagnoses and starting processes, whereas in order to transfer the financial risk that a saving project represents, mechanisms such as FDIC insurance, conversion of the debt in values, Saving's Guarantees, Performance Bonuses or Guarantee Bonuses and Insurances for Energy Saving can be of great help. This article deals on the IES insurance policies, their loss control management, successful cases, benefits, particular advantages, place in the market and refers argued insurance exceptions and perception surveys. [Spanish] Dado que uno de los problemas restrictivos a la hora de invertir en el ahorro de energia es la incertidumbre de obtener los ahorros proyectados, se presenta una tecnica en el manejo del riesgo para proyectos de eficiencia energetica llamada Seguro para el Ahorro de Energia (SAE). SAE estimula financieramente a quienes implementan proyectos para el ahorro de energia con el fin de que vayan mas alla de las medidas normales y consigan niveles significativos de ahorro, contribuyendo asi al cumplimiento de objetivos nacionales de ahorro energetico. Para reducir el riesgo de bajo desempeno de energia provocados por proyectos de ahorro existe la medicion del desempeno internacional y el protocolo de inversion (IMPVP) asi como diagnosticos y procesos de arranque, mientras que para transferir el

  10. Determination of the energy spectrum of the neutrons in the central thimble of the reactor core TRIGA Mark III; Determinacion del espectro de energia de los neutrones en el dedal central del nucleo del reactor Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Parra M, M. A.

    2014-07-01

    This thesis presents the neutron spectrum measurements inside the core of the TRIGA Mark III reactor at 1 MW power in steady-state, with the bridge placed in the center of the swimming pool, using several metallic threshold foils. The activation detectors are inserted in the Central Thimble of the reactor core, all the foils are irradiated in the same position and irradiation conditions (one by one). The threshold detectors are made of different materials such as: Au{sup 197}, Ni{sup 58}, In{sup 115}, Mg{sup 24}, Al{sup 27}, Fe{sup 58}, Co{sup 59} and Cu{sup 63}, they were selected to cover the full range the energies (10{sup -10} to 20 MeV) of the neutron spectrum in the reactor core. After the irradiation, the activation detectors were measured by means of spectrometry gamma, using a high resolution counting system with a hyper pure Germanium crystal, in order to obtain the saturation activity per target nuclide. The saturation activity is one of the main input data together with the initial spectrum, for the computational code SANDBP (hungarian version of the code SAND-II), which through an iterative adjustment, gives the calculated spectrum. The different saturation activities are necessary for the unfolding method, used by the computational code SANDBP. This research work is very important, since the knowledge of the energetic and spatial distribution of the neutron flux in the irradiation facilities, allows to characterize properly the irradiation facilities, just like, to estimate with a good precision various physics parameters of the reactor such as: neutron fluxes (thermal, intermediate and fast), neutronic dose, neutron activation analysis (NAA), spectral indices (cadmium ratio), buckling, fuel burnup, safety parameters (reactivity, temperature distribution, peak factors). In addition, the knowledge of the already mentioned parameters can give a best use of reactor, optimizing the irradiations requested by the users for their production process or

  11. Nuclear energy and environment: abstracts; Energia nuclear y medio ambiente: resumenes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    In this meeting on nuclear energy and environment, abstracts on the following subjects were presented: nuclear fuels; materials; radioisotopes and its applications; reactors and nuclear power plants; regulations, energy and environment; radioactive wastes; and analytical techniques.

  12. Decree No. 126/78 integrating the suppressed services of the Ministry for Industry and Technology into bodies created by Decree-Law No. 548/77 of 31 December 1977

    International Nuclear Information System (INIS)

    1978-01-01

    This Decree which came into force on 1 June 1978 was made in implementation of Decree-Law No. 548/77 of 31 December 1977 deciding the creation of new departments in the Ministry for Industry and Technology in Portugal and the abolition of others, including the Junta de Energia Nuclear. The Decree divides up the Junta's activities among several administrative departments pending its actual abolition to be fixed by a subsequent Decree. (NEA) [fr

  13. Portugal

    International Nuclear Information System (INIS)

    2001-03-01

    This short report summarizes the main lines of the energy policy of Portugal. It presents the main energy companies and utilities (EDP, CPPE, REN, Petrogal, GDP, Galp SGPS) of the country, the energy supplies (resources, electricity, petroleum, coal, natural gas), the prices and pricing policy, the global energy consumption per sector, the stakes and perspectives of the energy market (forecasts, contracts). (J.S.)

  14. The text of the agreement of 15 July 1981 between Argentina and the Agency for the application of Safeguards in connection with contracts concluded between the Comision Nacional de Energia Atomica Argentina and the Kraftwerk Union AG (Federal Republic of Germany) for the supply of the Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 15 July 1981 between Argentina and the IAEA for the application of safeguards in connection with contracts concluded between the Comision Nacional de Energia Atomic Argentina and the Kraftwerk Union AG (Federal Republic of Germany) for the supply of the Atucha II Nuclear Power Plant has been suspended

  15. Availability analysis of the nuclear instrumentation of a research reactor; Analise da disponibilidade da instrumentacao nuclear de um reator de pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Vianna Filho, Alfredo Marques

    2016-07-01

    The maintenance of systems and equipment is a central question related to Production Engineering. Although systems are not fully reliable, it is often necessary to minimize the failure occurrence likelihood. The failures occurrences can have disastrous consequences during a plane flight or operation of a nuclear power plant. The elaboration of a maintenance plan has as objective the prevention and recovery from system failures, increasing reliability and reducing the cost of unplanned shutdowns. It is also important to consider the issues related to organizations safety, especially those dealing with dangerous technologies. The objective of this thesis is to propose a method for maintenance analysis of a nuclear research reactor, using a socio-technical approach, and focused on existing conditions in Brazil. The research reactor studied belongs to the federal government and it is located in the city of Rio de Janeiro. The specific objective of this thesis is to develop the availability analysis of one of the principal systems of the research reactor, the nuclear instrumentation system. In this analysis, were taken into account not only the technical aspects of the modules related to nuclear instrumentation system, but also the human and organizational factors that could affect the availability of the nuclear instrumentation system. The results showed the influence of these factors on the availability of the nuclear instrumentation system. (author)

  16. Dimensionamento de juntas soldadas de filete: uma revisão crítica Design of fillet welded joints: a critical review

    Directory of Open Access Journals (Sweden)

    Ivan Guerra Machad

    2011-06-01

    Full Text Available O principal objetivo deste trabalho, é mostrar para os engenheiros(as de soldagem e/ou projetistas de estruturas soldadas, as muitas opções existentes no projeto de juntas soldadas de filete, quando carregadas transversalmente, inclinada, ou paralelamente ao eixo do cordão de solda. Isto é feito através da discussão dos aspectos fundamentais deste tipo de junta, uma série de equações (desde normas e Código que permitem o dimensionamento da garganta, e exemplos utilizando metais base e consumíveis reais. É também propósito deste trabalho alertar estes profissionais, pois cada uma destas normas (tais como AISC e Eurocode 3, Códigos (tal como AWS, ou mesmo organizações reconhecidamente competentes (tal como IIW, têm características específicas (ou "filosofias", algumas delas muito distintas. Finalmente, mas não menos importante, este trabalho encerra analisando juntas soldadas de filete sob conceitos da teoria da elasticidade e plasticidade localizada.The main aim of this work, is to show for the welding engineers and/or designers of welded structures, the many existing options in the design of fillet welded joints, when loaded transverse, inclined, or parallel to the axis of the weld bead. This is done through a discussion on the very fundamental aspects of this kind of joint, a series of equations (from standards or Code that allow the throat dimensioning, and examples using actual base metals and consumables. It is also a purpose of this paper to caution those professionals, for each one of the standards (such as AISC and Eurocode 3, or Codes (such as AWS, or even authoritative organizations (such as IIW, have specific characteristics (or "philosophies", some of them very distinct. Finally, but not less important, this paper closes analysing fillet welded joints under concepts of the theory of elasticity and local plasticity.

  17. Nuclear reactors to come

    International Nuclear Information System (INIS)

    Lung, M.

    2002-01-01

    The demand for nuclear energy will continue to grow at least till 2050 because of mainly 6 reasons: 1) the steady increase of the world population, 2) China, India and Indonesia will reach higher social standard and their energy consumption will consequently grow, 3) fossil energy resources are dwindling, 4) coal will be little by little banned because of its major contribution to the emission of green house effect gas, 5) renewable energies need important technological jumps to be really efficient and to take the lead, and 6) fusion energy is not yet ready to take over. All these reasons draw a promising future for nuclear energy. Today 450 nuclear reactors are operating throughout the world producing 17% of the total electrical power demand. In order to benefit fully of this future, nuclear industry has to improve some characteristics of reactors: 1) a more efficient use of uranium (it means higher burnups), 2) a simplification and automation of reprocessing-recycling chain of processes, 3) efficient measures against proliferation and against any misuse for terrorist purposes, and 4) an enhancement of safety for the next generation of reactors. The characteristics of fast reactors and of high-temperature reactors will likely make these kinds of reactors the best tools for energy production in the second half of this century. (A.C.)

  18. Avaliação das Tensões Residuais em Juntas Soldadas de Inconel 625 Obtidas Através da Soldagem por Fricção e Mistura Mecânica

    Directory of Open Access Journals (Sweden)

    Guilherme Vieira Braga Lemos

    Full Text Available Resumo A utilização de materiais nobres é requisito básico em aplicações onde existe um ambiente agressivo como na indústria do petróleo e nuclear. Neste panorama, a liga Inconel 625 é frequentemente utilizada como material de cladeamento no revestimento interno de dutos rígidos. Assim, as superligas de níquel exercem papel fundamental nos campos de exploração de águas profundas e, por isso, o conhecimento de métodos modernos de soldagem aplicados a estas ligas e suas consequências nos estados de tensões residuais é importante. Portanto, o presente trabalho faz uma avaliação das tensões residuais após a Soldagem por Fricção e Mistura Mecânica (SFMM em chapas soldadas de Inconel 625. A união das chapas foi realizada com rotação da ferramenta 200 e 1200 rpm e velocidade de soldagem constante (1mm/s. As medições de tensões residuais na superfície das juntas soldadas foram investigadas através da técnica de difração de raios-X. Além disso, foram avaliadas as macroestruturas e o aporte térmico de acordo com os parâmetros de soldagem empregados. Embora não existam muitos trabalhos relacionados ao processo SFMM para ligas de Inconel, provavelmente devido à sua dificuldade de soldagem, tem sido percebido um aumento na aplicação da soldagem no estado sólido como excelente alternativa para as superligas à base de níquel. Os resultados mostraram que diferentes parâmetros de processo produziram juntas soldadas distintas e, consequentemente, variações na distribuição de tensões residuais. Por fim, um aumento na velocidade de rotação da ferramenta ocasionou um aumento nas tensões residuais na zona de mistura.

  19. Act No. 15 of 22 April 1980 setting up the Nuclear Safety Council

    International Nuclear Information System (INIS)

    1980-01-01

    The Spanish authorities are in the process or reorganising the public nuclear sector in order to separate the promotional and research aspects of the uses of nuclear energy for peaceful purposes from the regulation and control of such activities. To this effect this Act sets up a Nuclear Safety Council which takes over part of the duties and the personnel of the Junta de Energia Nuclear provided for by the Act of 29th April 1964 on Nuclear Energy. The new Nuclear Safety Council is a body which is independent of the State central administration and has legal personality as well as its own financial resources required to carry out its duties. The latter comprise, inter alia, proposing to the Government the regulations required in matters of nuclear safety and radiation protection; this includes the setting-up of standards and criteria for the selection of nuclear installation sites, in consultation with the local competent bodies. (NEA) [fr

  20. Economic analysis of the hydrogen production by means of the thermo-chemistry process iodine-sulfur with nuclear energy; Analisis economico de la produccion de hidrogeno mediante el proceso termoquimico yodo-azufre con energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Solorzano S, C.; Francois L, J. L., E-mail: cuausos@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac No. 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)

    2011-11-15

    In this work an economic study was realized about a centralized plant of hydrogen production that works by means of a thermo-chemistry cycle of sulfur-iodine and uses heat coming from a nuclear power plant of IV generation, with base in the software -Hydrogen Economic Evaluation Programme- obtained through the IAEA. The sustainable technology that is glimpsed next for the generation of hydrogen is to great scale and based on processes of high temperature coupled to nuclear power plants, being the most important the cycle S-I and the electrolysis to high temperature, for what objective references are presented that can serve as base for the taking of decisions for its introduction in Mexico. After detailing the economic models that uses the software for the calculation of the even cost of hydrogen production and the characteristics, so much of the nuclear plant constituted by fourth generation reactors, as of the plant of hydrogen production, is proposed a -base- case, obtaining a preliminary even cost of hydrogen production with this process; subsequently different cases are studied starting from which are carried out sensibility analysis in several parameters that could rebound in this cost, taking into account that these reactors are still in design and planning stages. (Author)

  1. Nuclear energy and climate change; Energia nuclear y cambio climatico

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Jimenez, A.

    2002-07-01

    Energy is one of the essential motives for social and economic development of the humanity. Nuclear energy is a feasible option to stand up to a larger demand of energy, and it is playing, and will continue playing in the future, a decisive role in the debate about climate change and sustainable development, and in the efforts to reduce the CO{sub 2} emissions. (Author)

  2. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Butterfield, C.E.; Waite, E.

    1982-01-01

    A nuclear reactor fuel element comprising a column of vibration compacted fuel which is retained in consolidated condition by a thimble shaped plug. The plug is wedged into gripping engagement with the wall of the sheath by a wedge. The wedge material has a lower coefficient of expansion than the sheath material so that at reactor operating temperature the retainer can relax sufficient to accommodate thermal expansion of the column of fuel. (author)

  3. Nuclear reactor container

    International Nuclear Information System (INIS)

    Hosaka, Seiichi.

    1988-01-01

    Cables coverd with non-halogen covering material are used as electric wire cables wired for supplying electric power to a reactor recycling pump. Silicone rubber having specified molecular formula is used for the non-halogen covering material. As a result, formation of chlorine in a nuclear reactor container can be eliminated and increase in the deposited salts to SUS pipeways, etc. can be prevented, to avoid the occurrence of stress corrosion cracks. (H.T.)

  4. Technology of nuclear reactors

    International Nuclear Information System (INIS)

    Ravelet, F.

    2016-01-01

    This academic report for graduation in engineering first presents operation principles of a nuclear reactor core. It presents core components, atomic nuclei, the notions of transmutation and radioactivity, quantities used to characterize ionizing radiations, the nuclear fission, statistical aspects of fission and differences between fast and slow neutrons, a comparison between various heat transfer fluids, the uranium enrichment process, and different types of reactor (boiling water, natural uranium and heavy water, pressurized water, and fourth generation). Then, after having recalled the French installed power, the author proposes an analysis of a typical 900 MWe nuclear power plant: primary circuit, reactor, fuel, spent fuel, pressurizer and primary pump, secondary circuit, aspects related to control-command, regulation, safety and exploitation. The last part proposes a modelling of the thermodynamic cycle of a pressurized water plant by using an equivalent Carnot cycle, a Rankine cycle, and a two-phase expansion cycle with drying-overheating

  5. Determination of the neutrons energy spectrum in the central thimble of the reactor core TRIGA Mark III; Determinacion del espectro de energia de los neutrones en el dedal central del nucleo del reactor TRIGA Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Parra M, M. A.; Luis L, M. A. [Universidad Autonoma Metropolitana, Unidad Azcapotzalco, Division de Ciencias Basicas, Av. San Pablo No. 180, Col. Reynosa Tamaulipas, 02200 Mexico D. F. (Mexico); Raya A, R.; Cruz G, H. S., E-mail: roberto.raya@inin.gob.mx [ININ, Departamento del Reactor, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    This work presents the measurement of the neutrons spectrum in energies in the central thimble of the reactor TRIGA Mark III to a power of 1 MW in stationary state, with the core in the center of the pool. To achieve this objective, several thin sheets were irradiated (one at the time) in the same position of the core. The activation probes were selected in such a way that covered the energy range (1 x 10{sup -10} to 20 MeV) of the neutrons spectrum in the reactor core, for this purpose thin sheets were used of {sup 197}Au, {sup 58}Ni, {sup 115}In, {sup 24}Mg, {sup 27}Al, {sup 58}Fe, {sup 59}Co and {sup 63}Cu. After the irradiation, the high energy gamma emissions of the activated thin sheets were measured by means of gamma spectrometry, in a counting system of high resolution, with a Hyper pure Germanium detector, obtaining this way the activity induced in the thin sheets whose magnitude is proportional to the intensity of the neutrons flow, this activity together to a theoretical initial spectrum are the main entrance data of the computational code SANDBP (Hungarian version of the code Sand-II) that uses the unfolding method for the calculation of the spectrum. (Author)

  6. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  7. Nuclear reactor buildings

    International Nuclear Information System (INIS)

    Nagashima, Shoji; Kato, Ryoichi.

    1985-01-01

    Purpose: To reduce the cost of reactor buildings and satisfy the severe seismic demands in tank type FBR type reactors. Constitution: In usual nuclear reactor buildings of a flat bottom embedding structure, the flat bottom is entirely embedded into the rock below the soils down to the deck level of the nuclear reactor. As a result, although the weight of the seismic structure can be decreased, the amount of excavating the cavity is significantly increased to inevitably increase the plant construction cost. Cross-like intersecting foundation mats are embedded to the building rock into a thickness capable withstanding to earthquakes while maintaining the arrangement of equipments around the reactor core in the nuclear buildings required by the system design, such as vertical relationship between the equipments, fuel exchange systems and sponteneous drainings. Since the rock is hard and less deformable, the rigidity of the walls and the support structures of the reactor buildings can be increased by the embedding into the rock substrate and floor responsivity can be reduced. This enables to reduce the cost and increasing the seismic proofness. (Kamimura, M.)

  8. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  9. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    Jaouen, C.; Beroux, P.

    2012-01-01

    From Zoe, the first nuclear reactor, till the current EPR, the French nuclear industry has always advanced by profiting from the feedback from dozens of years of experience and operations, in particular by drawing lessons from the most significant events in its history, such as the Fukushima accident. The new generations of reactors must improve safety and economic performance so that the industry maintain its legitimacy and its share in the production of electricity. This article draws the history of nuclear power in France, gives a brief description of the pressurized water reactor design, lists the technical features of the different versions of PWR that operate in France and compares them with other types of reactors. The feedback experience concerning safety, learnt from the major nuclear accidents Three Miles Island (1979), Chernobyl (1986) and Fukushima (2011) is also detailed. Today there are 26 third generation reactors being built in the world: 4 EPR (1 in Finland, 1 in France and 2 in China); 2 VVER-1200 in Russia, 8 AP-1000 (4 in China and 4 in the Usa), 8 APR-1400 (4 in Korea and 4 in UAE), and 4 ABWR (2 in Japan and 2 in Taiwan)

  10. Communications received from Member States regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material; Comunicaciones Recibidas De Estados Miembros Relativas A La Exportacion De Materiales Nucleares Y De Determinadas Categorias De Equipo Y Otros Materiales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-08-15

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania [Spanish] El Director General recibio cartas relativas a la exportacion de materiales nucleares y de determinadas categorias de equipo y otros materiales de los siguientes Representantes Permanentes ante el Organismo Internacional de Energia Atomica: una carta fechada el 28 de febrero de 1994 del Representante Permanente de Francia; cartas fechadas el 1 de marzo de 1994 de los Representantes Permanentes de Alemania, Australia, Austria, Bulgaria, Canada, Dinamarca, Espana, Estados Unidos de America, Finlandia, Grecia, Hungria, Irlanda, Japon, Luxemburgo, Noruega, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa y Suecia,- una carta fechada el 22 de marzo de 1994 del Representante Permanente de Rumania.

  11. Nuclear reactor control column

    International Nuclear Information System (INIS)

    Bachovchin, D.M.

    1982-01-01

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor

  12. Agreement of 30 January 1992 between the Government of the Democratic People's Republic of Korea and the International Atomic Energy Agency for the Application of Safeguards in connection with the Treaty on the Nonproliferation of Nuclear Weapons; Acuerdo De 30 De Enero De 1992 Entre El Gobierno De La Republica Popular Democratica De Corea Y El Organismo Internacional De Enercia Atomica Para La Aplicacion De Salvaguardias En Relacion Con El Tratado Sobre La No Proliferacion De Las Armas Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-05-15

    The text of the Agreement between the Government of the Democratic People's Republic of Korea and the International Atomic Energy Agency for the application of safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons is reproduced in this document for the information of all Members. The Agreement was approved by the Agency's Board of Governors on 12 September 1991 and signed in Vienna on 30 January 1992. The Agreement entered into force, pursuant to Article 25, on 10 April 1992 [Spanish] El texto del Acuerdo entre el Gobierno de la Republica Popular Democratic-a de Corea y el Organismo Internacional de Energia Atomica para la aplica cion de salvaguardias en relacion con el Tratado sobre la no proliferacion de las armas nuclearese reproduce en este documento para informacion de to dos los Estados Miembros. El Acuerdo fue aprobado por la Junta de Gobernado res del Organismo el 12 de septiembre de 1991 y firmado en Viena el 30 de ene ro de 1992.

  13. Nuclear energy: a necessary option; Energia nuclear: una opcion necesaria

    Energy Technology Data Exchange (ETDEWEB)

    Robles N, A. G. [Comision Federal de Electricidad, Periferico Sur No. 4156, Col. Jardines del Pedregal, 01900 Ciudad de Mexico (Mexico); Ramirez S, J. R.; Esquivel E, J., E-mail: ambar.robles@cfe.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    With the decree of the Energy Reform and with the creation of the Electricity Industry and Energy Transition Laws; nuclear energy is incorporated into these as a source of clean energy. Currently, the share of electricity generation using conventional technologies is 80% and clean technologies of 20% of which hydroelectric plants represent 50% of these. While the operation of hydroelectric, wind, solar plants, etc. have contributed to reduce greenhouse gas emissions (GGE), the global effort to mitigate climate change has not observed the expected results, according to the meeting of COP 21 in Paris, where 196 countries agreed, unanimously, to limit the increase of the temperature at 2 degrees Celsius or less for before the year 2100. In Paris, Mexico voluntarily submitted its national mitigation and adaptation contribution to climate change by issuing 162 M ton of CO{sub 2eq} as a goal to 2030, that is a ΔGGE of -22%. This means that the electricity sector should contribute to the reduction of 139 M ton of CO{sub 2eq} and a ΔGGE of -31%. According to some experts, the goal of reducing gases for the sector could be achieved during the period defined in the Agreement, provided that the share of clean energies is added as established in the Energy Reform and the Development Program of the National Electric System 2016-2030, which establishes the addition of 35,532 MW (62%) of installed capacity in clean technologies, where nuclear energy participates with 4,191 MW (7%) that is, 2,651 MW more. Thus, this article aims to show the importance of the use of nuclear energy in the electricity sector to reduce GGE, achieve international commitments and combat climate change. (Author)

  14. Nuclear energy in Mexico as alternative for the reduction of CO{sub 2} emissions; Energia nuclear en Mexico, como alternativa para la reduccion de emisiones de CO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, G.; Ramirez, J. R.; Palacios, J. C., E-mail: gustavo.alonso@inin.gob.m [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-07-01

    One of the main concerns related with global warming is the reduction of the green house emissions. Mexico is taking steps to solve this problem, in its recent National Energy Strategy has considered to increase the use of clean electricity sources up to a 35% the share to be meat at 2024, currently this participation in electricity generation is 23.9%. In 2008 the Mexican Electrical Network produced 0.466 tons of CO{sub 2}/MWh, this index is above the OECD 0.45 CO{sub 2}/MWh average value. The current study considers the use of nuclear energy as part of the addition of clean energy to the Electrical grid; it proposes the capacity and the numbers of nuclear reactors to be used and it provides the emissions scenario generated with this proposal. (Author)

  15. Radioisotope Power Sources; Sources d'energie utilisant les radiobotopes; Radioizotopnye istochniki ehnergii; Fuentes radio isotopicas de energia

    Energy Technology Data Exchange (ETDEWEB)

    Culwell, J. P. [USAEC, Washington, D.C (United States)

    1963-11-15

    satellite TRANSIT, place sur orbite par la Marine americaine, est equipe d'un generateur thermoelectrique au plutonium-238 comme source d'energie electrique. Des generateurs sont a l'etude pour les projets spatiaux du Bureau de l'Aeronautique et de l'Administration de l'espace americains. En raison des grandes quantites de radioactivite que comportent les sources d'energie utilisant des radioisotopes, il faut accorder une grande attention a la securite de ces appareils. Pour s'assurer que l'on peut les utiliser sans creer de risques inutiles, on a etabli des normes de securite rigoureuses et procede a des essais tres pousses. (author) [Spanish] El programa de la Comision de Energia Atomica de los Estados Unidos en materia de energia electrica generada por radioisotopos ha dado origen a toda una nueva tecnologia cuyo objeto es el empleo de radioisotopos como fuentes de energia en los generadores de electricidad. Las fuentes radioisotopicas se prestan en particular para aplicaciones a distancia en las que se necesita una fuente de energia duradera, poco voluminosa y de funcionamiento seguro. Capaces de funcionar satisfactoriamente en las condiciones mas extremas de temperatura y exposicion a la luz solar y radiaciones electromagneticas, estas ''baterias nucleares'' constituyen fuentes interesantes de energia para dispositivos de acopio de datos controlados a distancia, sistemas de vigilancia, satelites y otros vehiculos espaciales. Los radioisotopos utilizados como fuente de energia son habitualmente emisores alfa o beta. Los emisores alfa son preferibles, pero tambien mas caros y menos abundantes que los emisores beta y se reservan por lo general para usos espaciales. En la actualidad los emisores beta obtenidos de los productos de fision procedentes de los reactores se utilizan exclusivamente para aplicaciones terrestres y maritimas. No obstante, es de esperar que con el transcurso del tiempo los emisores beta tales como el estroncio-90 se emplearan en el espacio. Se estan

  16. Nuclear reactors in de-regulated markets: Integration between providers and customers?

    International Nuclear Information System (INIS)

    Girard, Philippe

    2006-01-01

    The deregulation of electricity markets has in most cases coincided with the end of state monopolies, where financial risks were borne by customers/citizens. Today, despite an economic advantage, nuclear power development faces two main problems: public acceptance and reticence of investors (banks, utilities shareholders). The development of electricity markets provides different financial instruments in order to hedge financial risks, but it is currently difficult to fix forward contracts for more than three to four years, and this period is insufficient for the financing of a nuclear reactor. A solution could be the evolution of nuclear providers into nuclear operators selling electricity (MWh) rather than selling nuclear capacity (MW), nuclear fuel and services. In this case, their customers would be utilities and big customers aiming to hedge a part of their supplies with long-term contracts or stakes in nuclear reactors without some nuclear constraints. (author)

  17. PERSPECTIVAS DE INSERÇÃO DA ENERGIA SOLAR FOTOVOLTAICA NA GERAÇÃO DE ENERGIA ELÉTRICA NO RIO GRANDE DO NORTE

    Directory of Open Access Journals (Sweden)

    Augusto César Fialho Wanderley

    2013-08-01

    Full Text Available A geração de energia elétrica no Brasil é predominantemente renovável, com a geração interna hidráulica sendo superior a 74% do total de sua matriz energética. O racionamento de energia elétrica ocorrido em 2001, devido à falta de chuvas, levou o país a incrementar a participação de fontes alternativas de energia. Esta necessidade por novas fontes de energia faz com que as potencialidades regionais sejam aproveitadas, o que configura a mudança do modelo de geração, passando de geração centralizada para geração distribuída. Dentre as fontes alternativas de energia, a solar apresenta-se como uma fonte bastante promissora para o Brasil, tendo em vista que a maior parte do seu território está localizada próximo à linha do equador, o que acarreta em um dia de maior duração solar. O Rio Grande do Norte (RN tem um dos maiores índices de incidência solar do território brasileiro, o que o torna apto a receber investimentos para a instalação de usinas solares fotovoltaicas. Este artigo analisará o potencial de geração da energia solar fotovoltaica no RN através de medições solarimétricas realizadas em Natal, capital do estado.

  18. Pointing Out Main Factors from Design, Construction and Operating Experience of Existing Nuclear Plants for Assisting in Shaping Future Nuclear Power Programmes; Les principaux criteres degages de l'etude, de la construction et de l'exploitation des centrales nucleaires existantes et leur interet pour l'elaboration des futurs programmes d'energie d'origine nucleaire; Ukazanie osnovnykh faktorov proektirovaniya, stroitel'stva i opyta ehkspluatatsii sushchestvuyutsikh atomnykh ehlektrostantsij, chto dolzhno pomoch' pri sostavlenii budushchikh programm atomnoj ehnergetiki; Principales consideraciones relativas al diseno, construccion y explotacion de centrales nucleares, encaminadas a facilitar la preparacion de programas futuros de energia nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Dalla Volta, F. [Comitato Nazionale per l' Energia Nucleare, Rome (Italy)

    1963-10-15

    incessamment entrer en service en Italie, aideraient a etablir les plans des installations futures. Il suggere la possibilite de prevoir des maintenant des cycles de combustible pour une plus longue periode. (author) [Spanish] En la memoria se examinan las principales consideraciones de caracter tecnico y eco nomico relativas al diseno, construccion y explotacion de las primeras centrales nucleoelectricas a plena escala, y que mas pueden ayudar a preparar los planes futuros de expansion nuclear, con especial referencia a las condiciones que reinan en Italia. El estado actual de la tecnologia de los reactores y su evolucion continua en la ejecucion de los proyectos hasta ahora realizados, muestra una neta tendencia hacia la reduccion de los costos del ciclo de combustible y de los elementos componentes de las centrales. Contribuye a esta evolucion la tendencia cada vez mas acusada a construir centrales de mayores dimensiones, y el hecho de que las previsiones acerca de las condiciones futuras de la red electrica sugieren la conveniencia de instalar centrales nucleares de mayor capacidad que las centrales clasicas, en razon de la disminucion que experimentaran los gastos de produccion gracias a la puesta en servicio de esas nuevas unidades. En lo que se refiere a la experiencia adquirida en e l diseno, construccion y pruebas de las centrales en funcionamiento, la memoria estudia los principales factores que han de tenerse en cuenta en la preparacion de planes para el futuro, tambien desde e l punto de vista de los programas de construccion y de pruebas. El autor insiste en el problema del confinamiento, en razon de la favorable influencia que sobre la elecion del emplazamiento de las centrales puede ejercer el perfeccionamiento de blindajes muy seguros, que podrian construirse sin aumento sensible del costo, teniendo en cuenta la especial situacion de Italia en lo que se refiere a ciertos aspectos del problema. En cuanto a la experiencia adquirida en la explotacion de centrales

  19. Analysis of the scenarios with the participation of nuclear energy in the Mexican electric sector using the Decades program; Analisis de escenarios con la participacion de la energia nuclear en el sector electrico mexicano utilizando el programa DECADES

    Energy Technology Data Exchange (ETDEWEB)

    Sosa P, E.; Trejo G, M.G.; Martin del Campo M, C.; Francois L, J.L. [FI-UNAM, 04500 Mexico D.F. (Mexico)] e-mail: edithsosa@hotmail.com

    2003-07-01

    At the moment the energetic planning demands a technical, economic and environmental analysis of the different options of electric generation to be able to find the best solution of supply and energy readiness, already that it is indispensable for the development of the productive activities and to assure the competitiveness of the economy of a country. The expansion analyses of the Mexican Electric Sector its are carried out daily in the Federal Commission of Electricity (CFE) with some programs, among them Decades. However, up to where we have information only there is been considering a type of reactor like candidate being that exist several options that show promising characteristics for what its should be considered in the analyses. With this work its got rich the Decades database of the nuclear power stations that can be used as candidates to consider in the variable system of the expansion studies. Its have been carried out some comparative analysis between two types of nuclear centrals that at the moment offer in the market, specifically the AP600 type PWR reactor of 600 M We and the one BWR with capacity of 1300 M We. Later on it is sought to analyze two or three scenarios of the system of electric generation in Mexico to a term of twenty or twenty-five years. (Author)

  20. CONSUMO DE ENERGIA ELÉTRICA: UMA ANÁLISE DE FONTE ALTERNATIVA DE COLETOR SOLAR DE BAIXO CUSTO

    Directory of Open Access Journals (Sweden)

    Ramon Alves de Oliveira

    2015-08-01

    Full Text Available Com o aumento do consumo de energia elétrica e tarifas, a procura por geração de energias alternativas vem crescendo gradativamente, principalmente que sejam de baixo custo, assim possibilitando uma maior inclusão social beneficiando também as residências de baixa renda. Com o espírito de inovação a pesquisa buscou ideias simples que possam contribuir para a sociedade buscando alternativas sustentáveis e de baixo custo para a economia de energia elétrica Esse artigo teve como objetivo desenvolver um Coletor Solar de baixo custo. A metodologia utilizada foi quantitativa descritiva de caráter exploratório. Os procedimentos adotados foram uma pesquisa bibliográfica e desenvolvimento de um protótipo como procedimento experimental para coleta de dados. Dados os resultados nota-se que os testes realizados com o coletor solar de baixo custo, obteve um resultado com a temperatura da água para o banho de 37,1°C superior ao do chuveiro elétrico de 35,5°C. Com esse resultado o coletor solar se mostra, eficiente no quesito temperatura de banho e uma alternativa eficiente para a geração de energia térmica para aquecimento da água, além de reduzir a energia elétrica consumida em uma residência ao substituir o chuveiro tradicional que tem mais de 5000W , que é considerado um vilão para o consumo de energia elétrica.

  1. JPRS Report, Science & Technology, Europe & Latin America, Argentina: Specifications of ARGOS 380 MW Reactor.

    Science.gov (United States)

    1988-02-18

    and economy in operation. ENACE is an acronym for Empresa Nuclear Argentina de Centrales Electricas, or Argentine Nuclear Power Plant Corporation...products. The fuel transport system can be used during full reactor power operation to remove specially de - signed fuel assemblies containing rods for...SPECIFICATIONS OF ARGOS 380 MW REACTOR [Buenos Aires COMISION NACIONAL DE ENERGIA ATOMICA: INFORME in English 1987 pp 1-93] CONTENTS Argentine Offer of

  2. Nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatoly

    2013-07-01

    Covers a new technology of nuclear reactors and the related materials aspects. Integrates physics, materials science and engineering Serves as a basic book for nuclear engineers and nuclear physicists. The development of a nuclear rocket engine reactor (NRER) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  3. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    Sasaki, Y.; Tashima, J.

    1975-01-01

    A description is given of nuclear reactor fuel assemblies arranged in the form of a lattice wherein there is attached to the interface of one of two adjacent fuel assemblies a plate spring having a concave portion curved toward said interface and to the interface of the other fuel assembly a plate spring having a convex portion curved away from said interface

  4. Influência da Velocidade de Rotação do Rebite na Microestrutura e no Desempenho Mecânico de Juntas de Compósito Termofixo Rebitadas por Fricção

    Directory of Open Access Journals (Sweden)

    Natascha Zocoller Borba

    2016-03-01

    Full Text Available Resumo A Rebitagem por Fricção tem se demonstrado como alternativa para união de perfis de compósito termofixo aplicados na construção civil, frente às necessidades atuais por tecnologias eficientes de união de estruturas multimateriais. Nesse processo, a extremidade de um rebite metálico é plastificada e forjada dentro de um componente polimérico, via calor friccional. Sua viabilidade técnica já foi demonstrada para juntas de Ti-6Al-4V/poliéster termofixo reforçado com fibra de vidro. Este artigo tem como objetivo complementar esse estudo através da análise do efeito da velocidade de rotação do rebite na temperatura do processo, microestrutura e propriedades mecânicas locais e globais das juntas. Foram fabricadas juntas com dois níveis de velocidade de rotação: 9000 rpm e 10000 rpm (os demais parâmetros foram mantidos constantes. Temperaturas do processo (655-765 °C superiores em 96% da temperatura de início de decomposição da matriz de poliéster (370 °C foram atingidas, desencadeando degradação polimérica acentuada na região de união. O aumento da velocidade de rotação e, portanto, do aporte térmico, não contribuiu estatisticamente para o aumento na profundidade de penetração e na largura da extremidade deformada do rebite. Porém, a extensão da área polimérica degradada aumentou em 47%, a qual resultou em redução proporcional de 50% da resistência à tração das juntas (de 4,0 ± 1,2 kN para 2,0 ± 0,7 kN. Adicionalmente, mapas de microdureza no rebite evidenciaram possíveis transformações de fase da liga que favoreceram seu endurecimento, com o aumento da velocidade de rotação. Contudo, nenhuma correlação pôde ser evidenciada entre a dureza e o desempenho mecânico das juntas sob tração, já que as amostras falharam majoritariamente por arrancamento completo do rebite da placa de compósito. Portanto, no desenvolvimento de juntas rebitadas por fricção de Ti-6Al-4V/ poli

  5. Familia y Escuela, juntas construyendo convivencia y paz. Evaluación de una experiencia de intervención en Pasto, Colombia.

    Directory of Open Access Journals (Sweden)

    Carlos Eduardo Contreras Grijalba

    2017-10-01

    Full Text Available La investigación tuvo como objetivo describir el impacto de la réplica del programa FAST (Familia y escuelas juntas desarrollado con estudiantes, docentes y padres de familia del Jardín Infantil Piloto de la ciudad de Pasto (Colombia. Método: La reconstrucción de la experiencia vivida se realizó desde el enfoque cualitativo constructivista, utilizando un método histórico hermenéutico a través de entrevistas en profundidad. Resultados: Mejoró el funcionamiento familiar, se fortaleció la resiliencia infantil y se mitigaron los factores de riesgo desde los aportes de las teorías ecológica, sistémica y del desarrollo emocional de los niños y niñas. Conclusión: Se evidencia la gestación de una nueva convivencia desde la escuela para la familia.

  6. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    Banerjee, S.; Kamath, H.S.

    2005-01-01

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

  7. La Consolidación de Estados Contables en el Sector Público Empresarial. Aplicación al Grupo de Empresas de la Junta de Andalucía

    Directory of Open Access Journals (Sweden)

    Antonio Manuel López Hernández

    2003-06-01

    Full Text Available The decentralisation of services brings about the fragmentation of accounting information about public sector economic activity. There is a need, therefore, to establish consolidated balance sheets, since they provide more relevant information than that obtained by merely aggregating the data contained in individual financial statements. At the local level, many studies have been written about the problem of consolidation, however, much less attention has been paid to the autonomous level. Given the experience gained after consolidating the statements of the Junta de Andalusia, this paper deals with two main issues. First, it examines the problems this process poses in the scope of public firms in the autonomous regions. Second, it explains the peculiarities that arose for the specific case of the corporate public sector of the Junta de Andalucía (Andalusian regional government.

  8. Nuclear reactor assembly

    International Nuclear Information System (INIS)

    Dorner, H.; Scholz, M.; Jungmann, A.

    1975-01-01

    A nuclear reactor assembly includes a reactor pressure tank having a substantially cylindrical side wall surrounded by the wall of a cylindrical cavity formed by a biological shield. A rotative cylindrical wall is interposed between the walls and has means for rotating it from outside of the shield, and a probe is carried by the rotative wall for monitoring the pressure tank's wall. The probe is vertically movable relative to the rotative cylindrical wall, so that by the probe's vertical movement and rotation of the rotative cylinder, the reactor's wall can be very extensively monitored. If the reactor pressure tank's wall fails, it is contained by the rotative wall which is backed-up by the shield cavity wall. (Official Gazette)

  9. Simulation of a nuclear accident by an academic simulator of a VVER-1000 reactor; Simulacion de un accidente nuclear, mediante un simulador academico de un reactor VVER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez G, L. [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: laurahg42@gmail.com [UNAM, Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2014-10-15

    This work is planned to simulate a scenario in which the same conditions that caused the accident at the Fukushima Daichi nuclear power plant are present, using a simulator of a nuclear power plant with VVER-1000 reactor, a different type of technology to the NPP where the accident occurred, which used BWR reactors. The software where it will take place the simulation was created and distributed by the IAEA for academic purposes, which contains the essential systems that characterize this type of NPP. The simulator has tools for the analysis of the characteristic phenomena of a VVER-1000 reactor in the different systems together and planned training tasks. This makes possible to identify the function of each component and how connects to other systems, thus facilitating the visualization of possible failures and the consequences that they have on the general behavior of the reactor. To program the conditions in the simulator, is necessary to know and synthesize a series of events occurred in Fukushima in 2011 and the realized maneuvers to reduce the effects of the system failures. Being different technologies interpretation of the changes that would suffer the VVER systems in the scenario in question will be developed. The Fukushima accident was characterized by the power loss of regular supply and emergency of the cooling systems which resulted in an increase in reactor temperature and subsequent fusion of their nuclei. Is interesting to reproduce this type of failure in a VVER, and extrapolate the lack of power supply in the systems that comprise, as well as pumping systems for cooling, has a pressure regulating system which involves more variables in the balance of the system. (Author)

  10. CANDU nuclear reactor technology

    International Nuclear Information System (INIS)

    Kakaria, B. K.

    1994-01-01

    AECL has over 40 years of experience in the nuclear field. Over the past 20 years, this unique Canadian nuclear technology has made a worldwide presence, In addition to 22 CANDU reactors in Canada, there are also two in India, one in Pakistan, one in Argentina, four in Korea and five in Romania. CANDU advancements are based on evolutionary plant improvements. They consist of system performance improvements, design technology improvements and research and development in support of advanced nuclear power. Given the good performance of CANOU plants, it is important that this CANDU operating experience be incorporated into new and repeat designs

  11. Eficiência energética em residências de estudantes da Universidade do Algarve. O caso de estudo da Residência Masculina Ferragial

    OpenAIRE

    Faustino, Iara

    2011-01-01

    Dissertação de mest. em energias renováveis e Gestão da Energia. Instituto Superior de Engenharia,Univ. do Algarve, 2011 O sector dos edifícios representa cerca de 40% do consumo final de energia na União Europeia. Em Portugal este valor é de aproximadamente 30%, oferecendo assim uma grande oportunidade de redução dos consumos de energia, através da implementação de medidas de racionalização. Neste trabalho é efectuado um estudo visando medidas de utilização racional de energia nas resi...

  12. Moderator for nuclear reactor

    International Nuclear Information System (INIS)

    Milgram, M.S.; Dunn, J.T.; Hart, R.S.

    1995-01-01

    This invention relates to a moderator for a nuclear reactor and more specifically, to a composite moderator. A moderator is designed to slow down, or thermalize, neutrons which are released during nuclear reactions in the reactor fuel. Pure or almost pure materials like light water, heavy water, beryllium or graphite are used singly as moderators at present. All these materials, are used widely. Graphite has a good mechanical strength at high temperatures encountered in the nuclear core and therefore is used as both the moderator and core structural material. It also exhibits a low neutron-capture cross section and high neutron scattering cross section. However, graphite is susceptible to attach by carbon dioxide and/or oxygen where applicable, and releases stress energy under certain circumstances, although under normal operating conditions these reactions can be controlled. (author). 1 tab

  13. Electric power conservation while using pumping systems; Conservacion de Energia Electrica en Sistemas de Bombeo

    Energy Technology Data Exchange (ETDEWEB)

    Nambiar, P

    2007-01-15

    The pumping systems provide about 20 to 25 percent of energy which is necessary worldwide: it is fruitful to understand how to use electric power efficiently, to achieve the reduction regarding expenses a pumping system implies.It is essential to possess a better knowledge about the pumping system and its applications, in order to be able to use energy responsibly. If people do not how to operate this kind of systems properly, they will use inadequate equipment that will cause an energy waste. In addition it is important to know: alternative methods to meet variable demands, an adapted system to pump water requirements in order to ensure the pump work in its pumping point, and the life cycle system cost for the energy saving in the long term. [Spanish] En promedio del 20 al 25% de la energia necesaria en el mundo proviene de los sistemas de bombeo, por tal razon es importante saber como utilizar la energia electrica con eficiencia para asi lograr reducir los gastos que este tipo de sistemas implican. Para poder hacer un buen uso de la energia, es necesario que se tenga un conocimiento mayor del sistema de bombeo y aplicacion, ya que la ignorancia sobre esto exige el uso de aparatos que contribuyen al desperdicio de la energia; por otro lado tambien es esencial conocer metodos alternos para demandas variables, tener un sistema que se adapte a las necesidades de bombeo del agua para asegurarse de que cada bomba trabaje cerca de su punto de bombeo y finalmente conocer el costo del ciclo de vida del sistema para el ahorro de energia a largo plazo.

  14. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  15. Um estudo da viabilidade de pequenos aerogeradores na produção de energia elétrica

    OpenAIRE

    Martins de Melo, Gilberto

    2009-01-01

    Este trabalho propõe o desenvolvimento de um aplicativo e discute ambos os resultados econômicos e técnicos obtidos com um procedimento chamado PEL - perfil de energia local. Esta ferramenta é a elaboração de metodologia alternativa para a estimativa de energia elétrica obtida a partir de energia eólica disponível usando turbinas de pequeno eixo horizontal. Os dados necessários para este procedimento são registrados como série simultânea anual da temperatura de ar e velocidade ...

  16. The Text of the Agreement of 22 July 1977 between Argentina and the Agency for the Application of Safeguards in Connection with a Contract Concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union Gmbh Hanau (Federal Republic of Germany) for Co-Operation in the Field of Fabrication of Fuel Elements for Peaceful Nuclear Activities

    International Nuclear Information System (INIS)

    1977-01-01

    The text of the Agreement of 22 July 1977 between Argentina and the Agency for the application of safeguards in connection with the Contract of 13 August 1976 concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union GmbH (Federal Republic of Germany) for co-operation in the field of fabrication of fuel elements for peaceful nuclear activities is reproduced in this document for the information of all Members. The Agreement entered into force, pursuant to Section 26, on 22 July 1977.

  17. The Text of the Agreement of 22 July 1977 between Argentina and the Agency for the Application of Safeguards in Connection with a Contract Concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union Gmbh Hanau (Federal Republic of Germany) for Co-Operation in the Field of Fabrication of Fuel Elements for Peaceful Nuclear Activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-11-30

    The text of the Agreement of 22 July 1977 between Argentina and the Agency for the application of safeguards in connection with the Contract of 13 August 1976 concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union GmbH (Federal Republic of Germany) for co-operation in the field of fabrication of fuel elements for peaceful nuclear activities is reproduced in this document for the information of all Members. The Agreement entered into force, pursuant to Section 26, on 22 July 1977.

  18. Interactive applications for energy saving; Aplicaciones interactivas para ahorro de energia

    Energy Technology Data Exchange (ETDEWEB)

    Adame Gonzalez, Alejandro; Ramirez Anaya, Cesar; Gutierrez, Hector; Dominguez Ojeda, Xerxes; Aguilar Galvan, Alfredo [Ingenieria Energetica Integral S. A. de C. V., Mexico, D. F. (Mexico)

    1998-12-31

    A series of ideas are presented that can help in the development of interactive applications for energy saving. Emphasis is made on the Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE)`s Interactive Course on Demand Management and Power Factor Compensation, in order to demonstrate how far one can go with the multimedia development. [Espanol] Se presenta un conjunto de ideas que pueden auxiliar en la elaboracion de aplicaciones interactivas para ahorro de energia. Se hace principal enfasis sobre el curso interactivo Administracion de la Demanda y Compensacion del Factor de Potencia del Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE) con la finalidad de mostrar hasta donde puede llegarse con un desarrollo multimedia.

  19. Interactive applications for energy saving; Aplicaciones interactivas para ahorro de energia

    Energy Technology Data Exchange (ETDEWEB)

    Adame Gonzalez, Alejandro; Ramirez Anaya, Cesar; Gutierrez, Hector; Dominguez Ojeda, Xerxes; Aguilar Galvan, Alfredo [Ingenieria Energetica Integral S. A. de C. V., Mexico, D. F. (Mexico)

    1999-12-31

    A series of ideas are presented that can help in the development of interactive applications for energy saving. Emphasis is made on the Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE)`s Interactive Course on Demand Management and Power Factor Compensation, in order to demonstrate how far one can go with the multimedia development. [Espanol] Se presenta un conjunto de ideas que pueden auxiliar en la elaboracion de aplicaciones interactivas para ahorro de energia. Se hace principal enfasis sobre el curso interactivo Administracion de la Demanda y Compensacion del Factor de Potencia del Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE) con la finalidad de mostrar hasta donde puede llegarse con un desarrollo multimedia.

  20. Efeito de impactos repetidos de baixa energia em compósitos pultrudados

    Directory of Open Access Journals (Sweden)

    Morais Willy Ank de

    2001-01-01

    Full Text Available Danos internos podem ser gerados em compósitos de matriz polimérica submetidos a impactos de baixa energia. O efeito repetido de eventos desse tipo pode levar, eventualmente, à falha da estrutura. Neste trabalho dois tipos de perfis pultrudados foram submetidos a impactos por queda livre de peso de 0,5 m e 1,0 m de altura. Os resultados obtidos foram analisados em função da disposição das fibras nos perfis e mostram que a existência de uma camada rica em resina em um dos perfis, contribui para reduzir significativamente o desempenho deste perfil. Este comportamento foi associado à formação prematura de trincas na camada rica em resina. O número de eventos de impacto, o tempo de duração de cada choque e a forma da área danificada foram correlacionados com a presença, ou não, da região rica em resina. Os resultados obtidos indicam ainda que a diferença na microestrutura dos perfis analisados é mais significativa para os ensaios de menor energia (queda de 0,5 m. Para os ensaios de maior energia (queda de 1 m a configuração do material teve apenas uma importância secundária.

  1. Ambiente, paisagem, património e economia: Os conflitos em torno de parques eólicos em Portugal

    Directory of Open Access Journals (Sweden)

    Ana Delicado

    2013-10-01

    Full Text Available Nos últimos anos tem‑se assistido em Portugal ao crescimento exponencial do número de parques eólicos, respondendo às pressões políticas e económicas para atingir metas ambiciosas no que concerne à produção de energia através de fontes renováveis. A nível geral, este desenvolvimento tem‑se pautado por discursos consensuais – mitigação das alterações climáticas, diminuição da dependência energética face ao exterior –, mas ao nível local e situado os conflitos tornam‑se visíveis (destruição visual da paisagem, impactes nocivos nos ecossistemas rurais, nas atividades turísticas, na saúde. Este artigo tem como objetivo explorar os conflitos em torno da energia eólica, com base num estudo de caso exploratório realizado na aldeia histórica de Sortelha, acompanhado da análise de variadas fontes empíricas, tais como dados estatísticos, estudos de impacte ambiental, artigos de imprensa e de blogues.

  2. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Aspden, G.J.

    1980-01-01

    A nuclear reactor construction comprising a reactor core submerged in a pool of liquid metal coolant in a primary vessel which is suspended from the roof structure of a containment vault. Control rods supported from the roof structure are insertable in the core which is carried on a support structure from the wall of the primary vessel. To prevent excessive relaxation of the support structure whereby the control rods would be displaced relative to the core, the support structure incorporates a normally inactive secondary structure designed to become effective in bracing the primary structure against further relaxation beyond a predetermined limit. (author)

  3. Nuclear reactor installation

    International Nuclear Information System (INIS)

    Keller, W.

    1976-01-01

    A nuclear reactor installation includes a pressurized-water coolant reactor vessel and a concrete biological shield surrounding this vessel. The shield forms a space between it and the vessel large enough to permit rapid escape of the pressurized-water coolant therefrom in the event the vessel ruptures. Struts extend radially between the vessel and shield for a distance permitting normal radial thermal movement of the vessel, while containing the vessel in the event it ruptures, the struts being interspaced from each other to permit rapid escape of the pressurized-water coolant from the space between the shield and the vessel

  4. Australia's new nuclear reactor

    International Nuclear Information System (INIS)

    Kemeny, L.

    2007-01-01

    On 19 and 20 April 2007, the Australian Nuclear Science and Technology Organisation (ANSTO) celebrated the recent commissioning of its new, world-class, OPAL (Open Pool Australian Lightwater) research reactor at the Lucas Heights. On the 19th, scientists, business leaders and academics were introduced to the reactor and its technical capacity for the manufacture of radiopharmaceuticals, its material science applications, its environmental services and its neutron scattering facilities for business applications. The formal OPAL opening function took place that evening and, on the 20th, Prime Minister John Howard visited ANSTO to be briefed about OPAL and to be shown the work being carried out at Lucas Heights

  5. Refueling of nuclear reactor

    International Nuclear Information System (INIS)

    Kaufmann, J.W.; Swidwa, K.J.; Hornak, L.P.

    1989-01-01

    This patent describes an apparatus for refueling a nuclear reactor, the reactor being disposed for refueling under water in a pit in a containment, the apparatus including a bridge to be mounted moveably over the pit on the containment, first means connected to the bridge, for moving the bridge forward and backward on the containment over the pit along a first path, a first pulse generator, connected to the moving means, responsive to the movement of the bridge, for producing pulses, means, connected to the generator,for counting the pulses, the count of the pulses being dependent on the distance of the movement of the bridge

  6. De Centros Cívicos a Juntas de Acción Comunal. El cambio de modelo de gestión y participación barrial en Medellín en la segunda mitad del siglo XX

    Directory of Open Access Journals (Sweden)

    Juan Carlos Moreno Orozco

    2014-12-01

    Full Text Available El crecimiento de la ciudad en el siglo XX en América Latina, supone una serie de retos para los pobladores urbanos y el cuestionamiento sobre sus formas de acción política y reivindicativa frente a problemas relacionados con necesidades primarias como la vivienda y el acceso a los servicios públicos. En Medellín, se crearon los Centros Cívicos en 1938, figura política barrial que tuvo una amplia cobertura e influjo en los pobladores y en las relaciones con las autoridades municipales; sin embargo, la aparición de las Juntas de Acción Comunal (JAC en 1959, bajo preceptos internacionales y del Frente Nacional, instaura la confrontación de liderazgo en algunas zonas de la ciudad y reestructura la forma de comunicación entre la sociedad civil y el Estado. Bajo los enfoques de la historia social se describe el difícil trance de Centros Cívicos a Juntas de Acción Comunal, las posiciones de las autoridades, el discurso procomunitario, su impacto en los barrios y su importancia en la configuración de la ciudad.

  7. De Centros Cívicos a Juntas de Acción Comunal. El cambio de modelo de gestión y participación barrial en Medellín en la segunda mitad del siglo XX

    Directory of Open Access Journals (Sweden)

    Juan Carlos Moreno Orozco

    2014-01-01

    Full Text Available El crecimiento de la ciudad en el siglo xx en América Latina, supone una serie de retos para los pobladores urbanos y el cuestionamiento sobre sus formas de acción política y reivindicativa frente a problemas relacionados con necesidades primarias como la vivienda y el acceso a los servicios públicos. En Medellín, se crearon los Centros Cívicos en 1938, figura política barrial que tuvo una amplia cobertura e influjo en los pobladores y en las relaciones con las autoridades municipales; sin embargo, la aparición de las Juntas de Acción Comunal (JAC en 1959, bajo preceptos internacionales y del Frente Nacional, instaura la confrontación de liderazgo en algunas zonas de la ciudad y reestructura la forma de comunicación entre la sociedad civil y el Estado. Bajo los enfoques de la historia social se describe el difícil trance de Centros Cívicos a Juntas de Acción Comunal, las posiciones de las autoridades, el discurso procomunitario, su impacto en los barrios y su importancia en la configuración de la ciudad.

  8. A stochastic model for neutron simulation considering the spectrum and nuclear properties with continuous dependence of energy; Um modelo estocastico de simulacao neutronica considerando o espectro e propriedades nucleares com dependencia continua de energia

    Energy Technology Data Exchange (ETDEWEB)

    Camargo, Dayana Queiroz de

    2011-01-15

    This thesis has developed a stochastic model to simulate the neutrons transport in a heterogeneous environment, considering continuous neutron spectra and the nuclear properties with its continuous dependence on energy. This model was implemented using Monte Carlo method for the propagation of neutrons in different environment. Due to restrictions with respect to the number of neutrons that can be simulated in reasonable computational processing time introduced the variable control volume along the (pseudo-) periodic boundary conditions in order to overcome this problem. The choice of class physical Monte Carlo is due to the fact that it can decompose into simpler constituents the problem of solve a transport equation. The components may be treated separately, these are the propagation and interaction while respecting the laws of energy conservation and momentum, and the relationships that determine the probability of their interaction. We are aware of the fact that the problem approached in this thesis is far from being comparable to building a nuclear reactor, but this discussion the main target was to develop the Monte Carlo model, implement the code in a computer language that allows extensions of modular way. This study allowed a detailed analysis of the influence of energy on the neutron population and its impact on the life cycle of neutrons. From the results, even for a simple geometrical arrangement, we can conclude the need to consider the energy dependence, i.e. an spectral effective multiplication factor should be introduced each energy group separately. (author)

  9. Contratos bilaterais em mercados de energia elétrica multiagente: protocolo de rede de contratos

    OpenAIRE

    Fragoso, Frederico Parente

    2015-01-01

    O setor elétrico tem assistido a mudanças profundas na sua estrutura e organização, devido à sua liberalização, o que levou a uma maior competitividade nos mercados de energia elétrica. Uma gestão eficiente dos mercados de energia torna-se cada vez mais uma prioridade devido aos riscos que estes podem apresentar, aliado à elevada volatilidade dos preços e volumes nos diferentes períodos horários (incertezas na produção e consumo). A liberalização do setor elétrico levou à criação de sim...

  10. Licensing of nuclear reactor operators

    International Nuclear Information System (INIS)

    1979-09-01

    Recommendations are presented for the licensing of nuclear reactor operators in units licensed according to the legislation in effect. They apply to all physical persons designated by the Operating Organization of the nuclear reactor or reactors to execute any of the following functional activities: a) to manipulate the controls of a definite reactor b) to direct the authorized activities of the reactor operators licesed according to the present recommendations. (F.E.) [pt

  11. Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant. Simulacao do sistema nuclear de geracao de vapor de uma central PWR

    Energy Technology Data Exchange (ETDEWEB)

    Reis Martins Junior, L.L. dos.

    1980-01-01

    The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author).

  12. Immobilization of ion exchange radioactive resins of the TRIGA Mark III nuclear reactor; Inmovilizacion de resinas de intercambio ionico radiactivas del reactor nuclear Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Garcia M, H.; Emeterio H, M.; Canizal S, C. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, C.P. 11801 Mexico D.F. (Mexico)

    2000-07-01

    This work has the objective to develop the process and to define the agglutinating material which allows the immobilization of the ion exchange radioactive resins coming from the TRIGA Mark III nuclear reactor contaminated with Ba-133, Co-60, Cs-137, Eu-152, and Mn-54 through the behavior analysis of different immobilization agents such as: bitumens, cement and polyester resin. According to the International Standardization the archetype samples were observed with the following tests: determination of free liquid, leaching, charge resistance, biodegradation, irradiation, thermal cycle, burned resistance. Generally all the tests were satisfactorily achieved, for each agent. Therefore, the polyester resin could be considered as the main immobilizing. (Author)

  13. Energy from garbage; Energia a partir de la basura

    Energy Technology Data Exchange (ETDEWEB)

    Arvizu Fernandez, Jose Luis [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1997-12-31

    The subject of energy generation from garbage is discussed. A description is made of the sanitary fill, which is a system for the conversion or stabilization of garbage encompassing gas generation and lixiviates, these are collected to be used as fuels or a treatment process is applied to them avoiding this way the soil, water and air pollution; also a description is made of the utilization of a biogas recovery well, which recovers the biogas, cleans it from particles and condensates and afterwards feeds an internal combustion motor coupled to an electric generator. It is concluded that if the biogas generated by the buried garbage in the sanitary refills is utilized, the effects that cause the polluting emissions would be diminished and at the same time an additional energy resource would be on hand [Espanol] Se analiza el caso de la generacion de energia a partir de la basura. Se describe la tecnologia de relleno sanitario, la cual es un sistema de conversion o estabilizacion de la basura en el que existe generacion de biogas y lixiviados, estos se capturan para usarlos como combustibles o se les da un proceso de tratamiento y asi se evita la contaminacion del suelo, agua y aire; tambien se describe la utilizacion de un pozo de recuperacion de biogas, el cual recupera el biogas, lo limpia de particulas y condensados y despues alimenta a un motor de combustion interna acoplado a un generador. Se concluye en que si se aprovecha el biogas generado por la basura enterrada en rellenos sanitarios se diminuiran los efectos que causan las emisiones contaminantes y al mismo tiempo se tendria un recurso energetico adicional

  14. Energy from garbage; Energia a partir de la basura

    Energy Technology Data Exchange (ETDEWEB)

    Arvizu Fernandez, Jose Luis [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1998-12-31

    The subject of energy generation from garbage is discussed. A description is made of the sanitary fill, which is a system for the conversion or stabilization of garbage encompassing gas generation and lixiviates, these are collected to be used as fuels or a treatment process is applied to them avoiding this way the soil, water and air pollution; also a description is made of the utilization of a biogas recovery well, which recovers the biogas, cleans it from particles and condensates and afterwards feeds an internal combustion motor coupled to an electric generator. It is concluded that if the biogas generated by the buried garbage in the sanitary refills is utilized, the effects that cause the polluting emissions would be diminished and at the same time an additional energy resource would be on hand [Espanol] Se analiza el caso de la generacion de energia a partir de la basura. Se describe la tecnologia de relleno sanitario, la cual es un sistema de conversion o estabilizacion de la basura en el que existe generacion de biogas y lixiviados, estos se capturan para usarlos como combustibles o se les da un proceso de tratamiento y asi se evita la contaminacion del suelo, agua y aire; tambien se describe la utilizacion de un pozo de recuperacion de biogas, el cual recupera el biogas, lo limpia de particulas y condensados y despues alimenta a un motor de combustion interna acoplado a un generador. Se concluye en que si se aprovecha el biogas generado por la basura enterrada en rellenos sanitarios se diminuiran los efectos que causan las emisiones contaminantes y al mismo tiempo se tendria un recurso energetico adicional

  15. Gasification with nuclear reactor heat

    International Nuclear Information System (INIS)

    Weisbrodt, I.A.

    1977-01-01

    The energy-political ultimate aims for the introduction of nuclear coal gasification and the present state of technology concerning the HTR reactor, concerning gasification and heat exchanging components are outlined. Presented on the plans a) for hydro-gasification of lignite and for steam gasification of pit coal for the production of synthetic natural gas, and b) for the introduction of a nuclear heat system. The safety and environmental problems to be expected are portrayed. The main points of development, the planned prototype plant and the schedule of the project Pototype plant Nuclear Process heat (PNP) are specified. In a market and economic viability study of nuclear coal gasification, the application potential of SNG, the possible construction programme for the FRG, as well as costs and rentability of SNG production are estimated. (GG) [de

  16. Nuclear reactor containment device

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu.

    1980-01-01

    Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

  17. Nuclear reactor container

    International Nuclear Information System (INIS)

    Ishiyama, Takenori.

    1989-01-01

    This invention concerns a nuclear reactor container in which heat is removed from a container by external water injection. Heat is removed from the container by immersing the lower portion of the container into water and scattering spary water from above. Thus, the container can be cooled by the spray water falling down along the outer wall of the container to condensate and cool vapors filled in the container upon occurrence of accidents. Further, since the inside of the container can be cooled also during usual operation, it can also serve as a dry well cooler. Accordingly, heat is removed from the reactor container upon occurrence of accidents by the automatic operation of a spray device corresponding to the change of the internal temperature and the pressure in the reactor container. Further, since all of these devices are disposed out of container, maintenance is also facilitated. (I.S.)

  18. The nuclear reactor systems

    International Nuclear Information System (INIS)

    Bacher, P.

    2008-01-01

    This paper describes the various nuclear reactor systems, starting with the Generation II, then the present development of the Generation III and the stakes and challenges of the future Generation IV. Some have found appropriate to oppose reactor systems or generations one to another, especially by minimizing the enhancements of generation III compared to generation II or by expecting the earth from generation IV (meaning that generation III is already obsolete). In the first part of the document (chapter 2), some keys are given to the reader to develop its proper opinion. Chapter 3 describes more precisely the various reactor systems and generations. Chapter 4 discusses the large industrial manoeuvres around the generation III, and the last chapter gives some economical references, taking into account, for the various means of power generation, the impediments linked to climate protection

  19. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

    The development of a nuclear rocket engine reactor (NRER ) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  20. Nuclear reactor refueling system

    International Nuclear Information System (INIS)

    Wade, E.E.

    1978-01-01

    A system for transferring fuel assemblies between a nuclear reactor core and a fuel storage area while the fuel assembies remain completely submerged in a continuous body of coolant is described. The system comprises an in-vessel fuel transfer machine located inside the reactor vessel and an ex-vessel fuel transfer machine located in a fuel storage tank. The in-vessel fuel transfer machine comprises two independently rotatable frames with a pivotable fuel transfer apparatus disposed on the lower rotatable frame. The ex-vessel fuel transfer machine comprises one frame with a pivotable fuel transfer apparatus disposed thereon. The pivotable apparatuses are capable of being aligned with each other to transfer a fuel assembly between the reactor vessel and fuel storage tank while the fuel assembly remains completely submerged in a continuous body of coolant. 9 claims, 7 figures

  1. Heat dissipating nuclear reactor

    Science.gov (United States)

    Hunsbedt, A.; Lazarus, J.D.

    1985-11-21

    Disclosed is a nuclear reactor containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the reactor vessel. The reactor vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extend from the metal base plate downwardly and outwardly into the earth.

  2. Decommissioning a nuclear reactor

    International Nuclear Information System (INIS)

    Montoya, G.M.

    1991-01-01

    The process of decommissioning a facility such as a nuclear reactor or reprocessing plant presents many waste management options and concerns. Waste minimization is a primary consideration, along with protecting a personnel and the environment. Waste management is complicated in that both radioactive and chemical hazardous wastes must be dealt with. This paper presents the general decommissioning approach of a recent project at Los Alamos. Included are the following technical objectives: site characterization work that provided a thorough physical, chemical, and radiological assessment of the contamination at the site; demonstration of the safe and cost-effective dismantlement of a highly contaminated and activated nuclear-fuelded reactor; and techniques used in minimizing radioactive and hazardous waste. 12 figs

  3. Autonomía de resistencia. Análisis y caracterización de la Autonomía en las Juntas de Buen Gobierno del Movimiento Zapatista

    OpenAIRE

    Martínez Espinoza, Manuel Ignacio

    2007-01-01

    En agosto de 2003, el Movimiento Zapatista creo a las Juntas de Buen Gobierno (JBG) en sus territorios, ubicados en el sureste de México, para fortalecer la aplicación de su autonomía. El texto analiza en profundidad la autonomía zapatista y concluye que, debido a que funciona como elemento orgánico del proyecto político zapatista, es una “Autonomía de Resistencia”. El argumento se expone en tres partes. En la primera, se revisan las líneas generales del Movimiento Zapatista y de las JBG. ...

  4. Nuclear reactor operator licensing

    International Nuclear Information System (INIS)

    Bursey, R.J.

    1978-01-01

    The Atomic Energy Act of 1954, which was amended in 1974 by the Energy Reorganization Act, established the requirement that individuals who had the responsibility of operating the reactors in nuclear power plants must be licensed. Section 107 of the act states ''the Commission shall (1) prescribe uniform conditions for licensing individuals; (2) determine the qualifications of such individuals; and (3) issue licenses to such individuals in such form as the Commission may prescribe.'' The article discusses the types of licenses, the selection and training of individuals, and the administration of the Nuclear Regulatory Commission licensing examinations

  5. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    Barjon, Robert

    1975-01-01

    The purpose of this book is to explain the physical working conditions of nuclear reactors for the benefit of non-specialized engineers and engineering students. One of the leading ideas of this course is to distinguish between two fundamentally different concepts: - a science which could be called neutrodynamics (as distinct from neutron physics which covers the knowledge of the neutron considered as an elementary particle and the study of its interactions with nuclei); the aim of this science is to study the interaction of the neutron gas with real material media; the introduction will however be restricted to its simplified expression, the theory and equation of diffusion; - a special application: reactor physics, which is introduced when the diffusing and absorbing material medium is also multiplying. For this reason the chapter on fission is used to introduce this section. In practice the section on reactor physics is much longer than that devoted to neutrodynamics and it is developed in what seemed to be the most relevant direction: nuclear power reactors. Every effort was made to meet the following three requirements: to define the physical bases of neutron interaction with different materials, to give a correct mathematical treatment within the limit of necessary simplifying hypotheses clearly explained; to propose, whenever possible, numerical applications in order to fix orders of magnitude [fr

  6. Nuclear reactors transients identification and classification system; Sistema de identificacao e classificacao de transientes em reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Bianchi, Paulo Henrique

    2008-07-01

    This work describes the study and test of a system capable to identify and classify transients in thermo-hydraulic systems, using a neural network technique of the self-organizing maps (SOM) type, with the objective of implanting it on the new generations of nuclear reactors. The technique developed in this work consists on the use of multiple networks to do the classification and identification of the transient states, being each network a specialist at one respective transient of the system, that compete with each other using the quantization error, that is a measure given by this type of neural network. This technique showed very promising characteristics that allow the development of new functionalities in future projects. One of these characteristics consists on the potential of each network, besides responding what transient is in course, could give additional information about that transient. (author)

  7. Shields for nuclear reactors

    International Nuclear Information System (INIS)

    Aspden, G.J.

    1984-01-01

    The patent concerns shields for nuclear reactors. The roof shield comprises a normally fixed radial outer portion, a radial inner portion rotatable about a vertical axis, and a connection between the inner and outer portions. In the event of hypothecal core disruption conditions, a cantilever system on the inner wall allows the upward movement of the inner wall, in order to prevent loss of containment. (UK)

  8. Compact nuclear reactor

    International Nuclear Information System (INIS)

    Juric, S.I.

    1975-01-01

    A compact nuclear reactor of the pressurized-water variety is described which has two separate parts separably engageable for ease of inspection, maintenance and repair. One of the parts is a pressure vessel having an active core and the other of the parts is a closure adapted on its lower surface with an integral steam generator. An integral pump, external pressurizer and control rods are provided which communicate with the active core when engaged to form a total unit. (U.S.)

  9. Nuclear reactor instrumentation

    International Nuclear Information System (INIS)

    Duncombe, E.; McGonigal, G.

    1975-01-01

    A liquid metal cooled nuclear reactor is described which has an equal number of fuel sub-assemblies and sensing instruments. Each instrument senses temperature and rate of coolant flow of a coolant derived from a group of three sub-assemblies so that an abnormal value for one sub-assembly will be indicated on three instruments thereby providing for redundancy of up to two of the three instruments. The abnormal value may be a precurser to unstable boiling of coolant

  10. Space nuclear reactor safety

    International Nuclear Information System (INIS)

    Damon, D.; Temme, M.; Brown, N.

    1990-01-01

    Definition of safety requirements and design features of the SP-100 space reactor power system has been guided by a mission risk analysis. The analysis quantifies risk from accidental radiological consequences for a reference mission. Results show that the radiological risk from a space reactor can be made very low. The total mission risk from radiological consequences for a shuttle-launched, earth orbit SP-100 mission is estimated to be 0.05 Person-REM (expected values) based on a 1 mREM/yr de Minimus dose. Results are given for each mission phase. The safety benefits of specific design features are evaluated through risk sensitivity analyses

  11. Energy saving, social and government communication; Ahorrro de energia, sociedad y comunicacion gubernamental

    Energy Technology Data Exchange (ETDEWEB)

    Morales Camarena, Francisco [Comision Nacional para el Ahorro de Energia, Mexico, D.F. (Mexico)

    2001-07-01

    The actions for the energy efficiency and the utilization of renewable energies are multiple and dispersed, in each one of the energy consumption points of the country. For this reason, two important factors to foment these actions are to promote the social participation and the effective government communication towards the society: energy saving and social participation. One of the main faculties of the National Commission of Energy Saving (CONAE) is to foment the efficiency in the energy use, through actions coordinated with the different agencies and organizations of the Federal Public Administration, with the governments of the federal entities and the municipalities and, through coordinated operations, with the private and social sectors. The CONAE has established mechanisms of coordination and cooperation with the private and social sectors, having fomented programs, projects and actions whose purpose is the energy efficiency, outstanding: 1) Committees and work groups; 2) Cooperation Agreements; 3) the Advisory Council for the Foment of Renewable Energy. [Spanish] Las acciones para la eficiencia energetica y el aprovechamiento de las energias renovables son multiples y dispersas, en cada uno de los puntos de consumo de energia del pais. Por ello, dos factores importantes para fomentar estas acciones son promover la participacion social y la comunicacion gubernamental eficaz hacia la sociedad: Ahorro de energia y participacion social. Una de las principales facultades de la Comision Nacional de Ahorro de Energia es fomentar la eficiencia en el uso de energia, a traves de acciones coordinadas con las diversas dependencias y entidades de la Administracion Publica Federal, con los gobiernos de las entidades federativas y de los municipios y, a traves de acciones concertadas, con los sectores social y privado. La CONAE ha establecido mecanismos de coordinacion y de cooperacion con los sectores privado y social, fomentando programas, proyectos y acciones cuyo

  12. Enoturismo em Portugal: as Rotas de Vinho

    Directory of Open Access Journals (Sweden)

    Simões, Orlando

    2008-04-01

    Full Text Available Since 1993, as supported by the Dyonisios program of the European Union, the wine routes have been the most visible face of the wine tourism practice in Portugal. Since these thematic routes have no specific rules, they usually depend on the initiative of the promoters, namely through the creation of adherent/promoters associations or other institutions, like the Regional Viticulture Commissions, and Tourism Regions. This article aims at analysing the basis for the development of wine tourism in Portugal and its structure around wine routes. The socioeconomics traits of both the vineyards and wine, are analysed. The existing routes in Portugal are presented and their strengths and limitations are identi-fied.

  13. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology; Comunicaciones recibidas de ciertos Estados Miembros relativas a las directrices para la exportacion de materiales, equipos y tecnologia nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-06-12

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Czech Republic, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to the export of nuclear material, equipment and technology [Spanish] El Director General del Organismo Internacional de Energia Atomica ha recibido notas verbales de fecha 1 de diciembre de 2005 de los Representantes Permanentes ante el Organismo de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, China, Croacia, Eslovenia, Espana, Estados Unidos de America, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Letonia, Lituania, Luxemburgo, Malta, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Sudafrica, Suecia, Suiza, Turquia y Ucrania relativas a la exportacion de materiales, equipo y tecnologia nucleares.

  14. Integrated scheme of long-term for spent fuel management of power nuclear reactors; Esquema integrado de largo plazo para la administracion de combustible gastado de reactores nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Palacios H, J. C.; Martinez C, E., E-mail: ramon-ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    After of irradiation of the nuclear fuel in the reactor core, is necessary to store it for their cooling in the fuel pools of the reactor. This is the first step in a processes series before the fuel can reach its final destination. Until now there are two options that are most commonly accepted for the end of the nuclear fuel cycle, one is the open nuclear fuel cycle, requiring a deep geological repository for the fuel final disposal. The other option is the fuel reprocessing to extract the plutonium and uranium as valuable materials that remaining in the spent fuel. In this study the alternatives for the final part of the fuel cycle, which involves the recycling of plutonium and the minor actinides in the same reactor that generated them are shown. The results shown that this is possible in a thermal reactor and that there are significant reductions in actinides if they are recycled into reactor fuel. (Author)

  15. Nuclear power reactor technology

    International Nuclear Information System (INIS)

    1978-09-01

    Risoe National Laboratory was established more than twenty years ago with research and development of nuclear reactor technology as its main objective. The Laboratory has by now accumulated many years of experience in a number of areas vital to nuclear reactor technology. The work and experience of, and services offered by the Laboratory within the following fields are described: Health physics site supervision; Treatment of low and medium level radioactive waste; Core performance evaluation; Transient analysis; Accident analysis; Fuel management; Fuel element design, fabrication and performance evaluation; Non-destructive testing of nuclear fuel; Theoretical and experimental structural analysis; Reliability analysis; Site evaluation. Environmental risk and hazard calculation; Review and analysis of safety documentation. Risoe has already given much assistance to the authorities, utilities and industries in such fields, carrying out work on both light and heavy water reactors. The Laboratory now offers its services to others as a consultant, in education and training of staff, in planning, in qualitative and quantitative analysis, and for the development and specification of fabrication techniques. (author)

  16. Design of a heterogeneous subcritical nuclear reactor with molten salts based on thorium; Diseno de un reactor nuclear subcritico heterogeneo con sales fundidas a base de torio

    Energy Technology Data Exchange (ETDEWEB)

    Medina C, D.; Hernandez A, P.; Letechipia de L, C.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico); Sajo B, L., E-mail: dmedina_c@hotmail.com [Universidad Simon Bolivar, Laboratorio de Fisica Nuclear, Apdo. Postal 89000, Caracas 1080-A (Venezuela, Bolivarian Republic of)

    2015-09-15

    This paper presents the design of a heterogeneous subcritical nuclear reactor with molten salts based on thorium, with graphite moderator and a {sup 252}Cf source, whose dose levels at the periphery allows its use in teaching and research activities. The design was realized by the Monte Carlo method, where the geometry, dimensions and the fuel was varied in order to obtain the best design. The result was a cubic reactor of 110 cm of side, with graphite moderator and reflector. In the central part having 9 ducts of 3 cm in diameter, eight of them are 110 cm long, which were placed on the Y axis; the separation between each duct is 10 cm. The central duct has 60 cm in length and this contains the {sup 252}Cf source, also there are two irradiation channels and the other six contain a molten salt ({sup 7}LiF - BeF{sub 2} - ThF{sub 4} - UF{sub 4}) as fuel. For the design the k{sub eff} was calculated, neutron spectra and ambient dose equivalent. In the first instance the above was calculated for a virgin fuel, was called case 1; then a percentage of {sup 233}U was used and the percentage of Th was decreased and was called case 2. This with the purpose of comparing two different fuels operating within the reactor. For the two irradiation ducts three positions are used: center, back and front, in each duct in order to have different flows. (Author)

  17. Dictionary of the energy-producing industry. Nuclear and non-nuclear energy sources. Vol. 3. Fachwoerterbuch zur Energiewirtschaft. Nukleare und nichtnukleare Energietraeger. - Diccionario tecnico de terminos de la industria de energia. Recursos energeticos nucleares y no nucleares. Bd. 3. Aleman-Espanol/Espanol-Aleman

    Energy Technology Data Exchange (ETDEWEB)

    Mannhardt, K H

    1981-01-01

    This technical dictionary, compiled in everyday practice, gives an outline of the terminology and phraseology of a modern field of engineering. Users should have some basic knowledge of the Spanish language and also of engineering as well as access to standard-language dictionaries. Core subjects of the dictionary are nuclear power, reactor engineering, fusion technology, solar energy, wind energy, tidal energy, radiation protection, nuclear safety, coal gasification and coal liquefaction, cooperative agreements and managerial problems.

  18. Análise de um sistema de aquecimento de água para residências rurais, utilizando energia solar

    OpenAIRE

    Basso,Luiz H.; Souza,Samuel N. M. de; Siqueira,Jair A. C.; Nogueira,Carlos E. C.; Santos,Reginaldo F.

    2010-01-01

    A conscientização da importância do meio ambiente tem incentivado o estudo de novas fontes energéticas renováveis e menos poluentes. Dentre essas fontes, a energia solar destaca-se por ser perene e limpa. A utilização da energia solar em sistemas de aquecimento de água residencial rural pode colaborar com a economia de energia elétrica, base da matriz energética brasileira. Conhecer os fatores que influenciam na operação de um sistema de aquecimento de água por energia solar é importante na d...

  19. Inversor para sistemas domésticos de produção de energia eólica

    OpenAIRE

    Rocha, Cirilo Leonel da

    2008-01-01

    O presente trabalho descreve a simulação de um gerador e inversor para sistemas domésticos de produção de energia eólica. Este projecto pretende simular a produção de energia eléctrica por meio de uma energia renovável (vento). Descreve-se toda a arquitectura do sistema e respectiva implementação. São apresentados os resultados das partes mais importantes do sistema e respectiva análise. Os diversos componentes do sistema são inicialmente apresentados individualmente, ...

  20. Conditions of a new development of the nuclear energy: the new imperatives of the electric competition; Condiciones de un nuevo desarrollo de la energia nuclear: los nuevos imperativos de la competencia electrica

    Energy Technology Data Exchange (ETDEWEB)

    Finon, D. [Centre International de Recherche sur l' Environment et le Developpement, CNRS, Campus du Jardin Tropical 45 bis, avenue de la Belle Gabrielle 94736, Nogent-sur-Marne Cedex (France)

    2009-07-01

    In this work firstly, it is present a panorama that it makes mention to the energy and environmental aspects of long term for which the reactivation of the nuclear sector could be one of the main answers in the electric industry. Next, we will determine the specific imperatives that weigh on the nuclear investment in a market environment. Later on we will examine the way in that the general problem of the investments in the liberalized electric industries takes progressively to abandon the competitive pattern of reference in diverse countries, that which allows to establish a field most favorable for the nuclear investment. Finally, we will analyze the viability of the public areas that the states could apply to create a specific mark dedicated to organize the nuclear investments in the electric industries where the competition continued being very strong. (Author)

  1. Correlações entre a densitometria do cristalino através da imagem de Scheimplufg, tempo e gasto de energia na cirurgia de facoemulsificação

    Directory of Open Access Journals (Sweden)

    Bruno de Freitas Valbon

    2011-06-01

    Full Text Available OBJETIVO:Correlacionar a densitometria do cristalino(PNS - patient nuclear scorepor meio da imagem de Scheimplufgcom o tempo de facoemulsificação e o gasto de energia. MÉTODOS: Estudo observacional prospectivo, envolvendo 22 olhos de 22 pacientes que se submeteram à cirurgia de catarata por facoemulsificação com implante de lente intraocular. A densitometria do cristalino (PNS foi medida através da tomografia de segmento anterior e córnea (Pentacam no pré-operatório com a imagem de Scheimplufg. O tempo de facoemulsificação e o gasto de energia foram verificados e anotados ao término de cada cirurgia. O teste de correlação de Pearson foi utilizado para análise estatística através do programa Bioestat 5.0. Foi considerado como estatisticamente significante p < 0,05%. RESULTADOS: As correlações entre PNS x Tempo de Facoemulsificação (s e PNS x Gasto de Energia obtiveram respectivamente um p < 0,0050 e RP (Coeficiente de Pearson de 0,5757 e p < 0,0029 e RP (Coeficiente de Pearson de 0,6034. CONCLUSÃO: Observamos uma forte associação entre o método objetivo de classificação da catarata através da imagem de Scheimplufg (PNS, tempo e gasto de energia. Assim há possibilidade de realizarmos um planejamento cirúrgico pré-operatório baseado em métodos objetivos da classificação da catarata, reduzindo a fluídica, energia e tempo na cirurgia de facoemulsificação.

  2. Nuclear reactor cavity streaming shield

    International Nuclear Information System (INIS)

    Klotz, R.J.; Stephen, D.W.

    1978-01-01

    The upper portion of a nuclear reactor vessel supported in a concrete reactor cavity has a structure mounted below the top of the vessel between the outer vessel wall and the reactor cavity wall which contains hydrogenous material which will attenuate radiation streaming upward between vessel and the reactor cavity wall while preventing pressure buildup during a loss of coolant accident

  3. Complete automation of nuclear reactors control; Automatisation complete de la conduite des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The use of nuclear reactor for energy production induces the installation of automatic control systems which need to be safe enough and can adapt to the industrial scale of energy production. These automatic control systems have to insure the constancy of power level and adjust the power produced to the energy demand. Two functioning modes are considered: nuclear plant connected up to other electric production systems as hydraulic or thermic plants or nuclear plants functioning on an independent network. For nuclear plants connected up with other production plants, xenon poisoning and operating cost lead to keep working at maximum power the nuclear reactors. Thus, the power modulation control system will not be considered and only start-up control, safety control, and control systems will be automated. For nuclear power plants working on an independent network, the power modulation control system is needed to economize fuel. It described the automated control system for reactors functioning with constant power: a power measurement system constituted of an ionization chamber and a direct-current amplifier will control the steadfastness of the power produced. For reactors functioning with variable power, the automated power control system will allow to change the power and maintain it steady with all the necessary safety and will control that working conditions under P{sub max} and R{sub max} (maximum power and maximum reactivity). The effects of temperature and xenon poisoning will also be discussed. Safety systems will be added to stop completely the functioning of the reactor if P{sub max} is reached. (M.P.)

  4. Development of the process of energy transfer from a nuclear Power Plant to an intermediate temperature electrolyse; Desarrollo del proceso de transferencia de energia desde una central nuclear a un electrolizador de temperatura intermedia

    Energy Technology Data Exchange (ETDEWEB)

    Munoz Cervantes, A.; Cuadrado Garcia, P.; Soraino Garcia, J.

    2013-07-01

    Fifty million tons of hydrogen are consumed annually in the world in various industrial processes. Among them, the ammonia production, oil refining and the production of methanol. One of the methods to produce it is the electrolysis of water, oxygen and hydrogen. This process needs electricity and steam which a central nuclear It can be your source; Hence the importance of developing the transfer process energy between the two. The objective of the study is to characterize the process of thermal energy transfer from a nuclear power plant to an electrolyzer of intermediate temperature (ITSE) already defined. The study is limited to the intermediate engineering process, from the central to the cell.

  5. Twenty years of Radiology in RP-10 nuclear reactor protection; Veinte anos de proteccion radiologica en el reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Zapata, Alejandro L.; Ramos, Fernando T.; Arrieta, Rolando W.B.; Vela Mora, Mariano, E-mail: lzapata@ipen.gob.pe, E-mail: framos@ipen.gob.pe, E-mail: rarrieta@ipen.gob.pe, E-mail: mvela@ipen.gob.pe [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru)

    2013-07-01

    In this report we present the results about radiation controls during 1990 - 2010, carried out in the Nuclear Reactor RP-10 of the Nuclear Center of Huarangal. These controls and radiological evaluation are of much utility for the radio personnel protection of this one and other reactors, since it allows to compares these variables with respect to the time. From the results obtained in monitoring and radiation controls, we conclude that in no case it has been reached the limits allowed by the Peruvian Regulating Authority. (author)

  6. Pesquisa ambiental de agentes de esporotricose em Portugal

    OpenAIRE

    Dançante, Ana Mafalda da Silva Grilo Carreteiro

    2017-01-01

    A esporotricose é uma das principais micoses subcutâneas reportadas mundialmente. O agente etiológico é um complexo de espécies dimórficas relacionadas conhecido como complexo Sporothrix schenckii. Considerada uma doença rara na Europa, foi recentemente identificado um caso autóctone em Portugal. Este trabalho teve como principal objetivo, desenvolver um ensaio baseado em PCR para detetar e identificar membros do complexo S. schenckii em amostras ambientais, e realizar uma pesquisa ...

  7. Techniques of thermal energy conservation; Tecnicas de conservacion de la energia termica

    Energy Technology Data Exchange (ETDEWEB)

    Caltenco Estevez, Juan Luis; Roblez Lopez, Francisco; Ceballos Serna, Andres Alberto [Instituto Mexicano del Petroleo (Mexico)

    1996-07-01

    In modern industry the thermal energy is the energy more intensely used, which implies that in the processes and equipment that operate based on it, rely the greatest opportunities for saving . In this paper some saving and conservation techniques of thermal energy, which nowadays have been developed, are presented, whose application has helped to the successful attainment of the objectives of increased productivity of industrial plants, with the additional benefit of reducing the environmental impact of the production activities. [Spanish] En la industria moderna la energia termica es la forma de energia mas intensamente utilizada, lo cual implica que en los procesos y equipos que operan basandose en esta, residan las mayores oportunidades de ahorro. En este trabajo se presentan algunas de las tecnicas de ahorro y conservacion de energia termica, que hoy en dia se han desarrollado, cuya aplicacion ha coadyuvado a la consecucion exitosa de los objetivos de incremento de la productividad de plantas industriales, con el beneficio adicional de reducir el impacto ambiental de las actividades productivas.

  8. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant; Analisis de documentos de los materiales de la envolvente del nucleo del reactor nuclear de la CLV U-1

    Energy Technology Data Exchange (ETDEWEB)

    Zamora R, L.; Medina F, A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  9. Nuclear reactor sealing system

    International Nuclear Information System (INIS)

    McEdwards, J.A.

    1983-01-01

    A liquid metal-cooled nuclear reactor sealing system is disclosed. The nuclear reactor includes a vessel sealed at its upper end by a closure head. The closure head comprises at least two components, one of which is rotatable; and the two components define an annulus therebetween. The sealing system includes at least a first and second inflatable seal disposed in series in an upper portion of the annulus. The system further includes a dip seal extending into a body of insulation located adjacent a bottom portion of the closure head. The dip seal comprises a trough formed by a lower portion of one of the components, and a seal blade pendently supported from the other component and extending downwardly into the trough. A body of liquid metal is contained in the trough which submerges a portion of the seal blade. The seal blade is provided with at least one aperture located above the body of liquid metal for providing fluid communication between the annulus intermediate the dip seal and the inflatable seals, and a body of cover gas located inside the vessel. There also is provided means for introducing a purge gas into the annulus intermediate the inflatable seals and the seal blade. The purge gas is introduced in an amount sufficient to substantially reduce diffusion of radioactive cover gas or sodium vapor up to the inflatable seals. The purge gas mixes with the cover gas in the reactor vessel where it can be withdrawn from the vessel for treatment and recycle to the vessel

  10. Nuclear reactor trip system

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

    Each parameter of the processes of a nuclear reactor and components operatively associated with it is monitored by a set of four like sensors. A trip system normally operates on a ''two out four'' configuration; i.e., to trip the reactor it is necessary that at least two sensors of a set sense an off-normal parameter. This assumes that all sensors are in normal operating condition. However, when a sensor is in test or is subject to maintenance or is defective or disabled, the ''two out of four''configuration would be reduced to a ''one out of three'' configuration because the affected sensor is taken out of service. This would expose the system to the possibility that a single sensor failure, which may be spurious, will cause a trip of the reactor. To prevent this, it is necessary that the affected sensor be bypassed. If only one sensor is bypassed, the system operates on a ''two out of three'' configuration. With two sensors bypassed, the sensing of an off-normal parameter by a third sensor trips the reactor. The by-pass circuit also disables the circuit coupling the by-passed sensor to the trip circuit. (author)

  11. Nuclear Reactor Sharing Program

    International Nuclear Information System (INIS)

    1994-01-01

    The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter measurements. For neutron activation analysis and analyses of natural environmental radioactivity, the NRL maintains the gamma ray spectroscopy system (GRSS). It is comprised of two PC-based 8192-channel multichannel analyzers (MCAs) with all the required software for quantitative analysis. A 3 double-prime x 3 double-prime NaI(Tl), a 14 percent Ge(Li), and a High Purity Germanium detector are currently available for use with the spectroscopy system

  12. Reactor accidents and nuclear catastrophes

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Linde, H.J.

    1979-01-01

    Assuming some preliminary knowledge of the fundamentals of atomic physics, the book describes the effects of ionizing radiation on the human organism. In order to assess the potential hazards of reactor accidents and the extent of a nuclear catastrophe, the technology of power generation in nuclear power stations is presented together with its potential dangers as well as the physical and medical processes occurring during a nuclear weapons explosion. The special medical aspects are presented which range from first aid in the case of a catastrophe to the accute radiation syndrome, the treatment of burns to the therapy of late radiolesions. Finally, it is confirmed that the treatment of radiation injured persons does not give rise to basically new medical problems. (orig./HP) [de

  13. L'uso pacifico dell'energia nucleare da Ginevra 1955 ad oggi : il caso italiano : atti del convegno

    CERN Document Server

    2007-01-01

    Energia e sviluppo (le fonti energetiche) ; l'Italia e l'opzione nucleare ; stato a prospettive delle tecnologie nucleari ; reattori nucleari di nuova generazione ; tecniche nucleari in biologia, medicina biochimica, agraria e beni culturali ; sicurezza e ambiente.

  14. Development of a remote monitoring system, through monitoring of key safety parameters for a nuclear research reactor; Desarrollo de un sistema de vigilancia remota, por medio del monitoreo de parametros claves de seguridad, para un reactor nuclear de investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Urcia, Agustin; Arrieta, Rolando [Direccion de Produccion, Instituto Peruano de Energia Nuclear, Lima (Peru); Baltuano, Oscar; Chan, Renzo [Direccion de Investigacion y Desarrollo, Instituto Peruano de Energia Nuclear, Lima (Peru); Tincopa, Jean Pierre [Facultad de Ingenieria Electrica y Electronica, Universidad Nacional del Callao, Callao (Peru); Urquizo, Rafael [Facultad de Ingenieria Electronica, Universidad Tecnologica del Peru, Lima (Peru); Rosas, Bernick [Facultad de Ingenieria Electronica, Universidad Nacional de Ingenieria, Lima (Peru)

    2014-07-01

    This paper presents the detailed development, installation and commissioning of water level sensors and exposure rate range in the 11 meters level (mouth of tank) of the RP-10 nuclear reactor used to continuously monitor these values and use them as security for the periods of no presence of operating personnel (overlooking situation) with the reactor in shutdown state. The levels of these parameters are packaged and transmitted to a controller in the control room of reactor for display and activation of alarm levels. Additionally, the design of these warning signs is shown in conjunction with the fire alarm in the building of reactor and auxiliary laboratories to be transmitted to the physical security facility, located at a distance of 500 meters. (authors).

  15. 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

  16. 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

  17. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  18. Competencias lingüísticas de docentes de párvulos. Un análisis del discurso conversacional de profesionales de la Junta Nacional de Jardines Infantiles

    Directory of Open Access Journals (Sweden)

    Sandra Ruperta Pérez Lisboa

    2014-01-01

    Full Text Available Recibido 02 de junio de 2013 • Corregido 27 de setiembre de 2013 • Aceptado 01 de octubre de 2013 Las competencias lingüísticas de docentes de párvulos son un referente continuo en el desarrollo del lenguaje de niñas y niños. Esto, porque son un modelo, debido a que utilizan constantemente la comunicación oral para trabajar, jugar o dar instrucciones. En relación con esta premisa, esta investigación tiene por objetivo analizar las competencias lingüísticas de un grupo de educadoras de párvulos del nivel transición menor.  Con base en la observación de docentes que trabajan en la Junta Nacional de Jardines Infantiles –de la zona poniente de la provincia de Santiago–, se realizó un estudio relativo al discurso conversacional de las profesionales. Se plantea que la posesión de mayores competencias lingüísticas, por parte de educadores, favorece el desarrollo del lenguaje oral de los párvulos.

  19. 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)

  20. Water cooled nuclear reactor

    International Nuclear Information System (INIS)

    1975-01-01

    A description is given of a cooling water intake collector for a nuclear reactor. It includes multiple sub-collectors extending out in a generally parallel manner to each other, each one having a first end and a second one separated along their length, and multiple water outlets for connecting each one to a corresponding pressure tube of the reactor. A first end tube and a second one connect the sub-collector tubes together to their first and second ends respectively. It also includes multiple collector tubes extending transversely by crossing over the sub-collector tubes and separated from each other in the direction of these tubes. Each collector tubes has a water intake for connecting to a water pump and multiple connecting tubes separated over its length and connecting each one to the corresponding sub-collector [fr

  1. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The seals described are for use in a nuclear reactor where there are fuel assemblies in a vessel, an inlet and an outlet for circulating a coolant in heat transfer relationship with the fuel assemblies and a closure head on the vessel in a tight fluid relationship. The closure head comprises rotatable plugs which have mechanical seals disposed in the annulus around each plug while allowing free rotation of the plug when the seal is not actuated. The seal is usually an elastomer or copper. A means of actuating the seal is attached for drawing it vertically into the annulus for sealing. When the reactor coolant is liquid sodium, contact with oxygen must be avoided and argon cover gas fills the space between the bottom of the closure head and the coolant liquid level and the annuli in the closure head. (U.K.)

  2. Nuclear reactor container

    International Nuclear Information System (INIS)

    Yamaki, Rika; Kawabe, Ryuhei.

    1989-01-01

    A venturi scrubber is connected to a nuclear reactor container. Gases containing radioactive aerosols in the container are introduced into the venturi scrubber in the form of a high speed stream under the pressure of the container. The radioactive aerosols are captured by inertia collision due to the velocity difference between the high speed gas stream and water droplets. In the case of the present invention, since the high pressure of the reactor container generated upon accident is utilized, compressor, etc. is no more required, thereby enabling to reduce the size of the aerosol removing device. Further, since no external power is used, the radioactive aerosols can be removed with no starting failure upon accidents. (T.M.)

  3. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    1975-01-01

    A description is given of a nuclear reactor fuel assembly comprising a cluster of fuel elements supported by transversal grids so that their axes are parallel to and at a distance from each other, in order to establish interstices for the axial flow of a coolant. At least one of the interstices is occupied by an axial duct reserved for an auxiliary cooling fluid and is fitted with side holes through which the auxiliary cooling fluid is sprayed into the cluster. Deflectors extend as from a transversal grid in a position opposite the holes to deflect the cooling fluid jet towards those parts of the fuel elements that are not accessible to the auxiliary coolant. This assembly is intended for reactors cooled by light or heavy water [fr

  4. RESISTÊNCIA AO CISALHAMENTO DAS JUNTAS ADESIVAS PRODUZIDAS COM TRÊS DIFERENTES ESPÉCIES DE MADEIRAS E ADESIVOS VINÍLICOS PARA APLICAÇÕES NÃO ESTRUTURAIS

    Directory of Open Access Journals (Sweden)

    Maurício Pinheiro Oliveira

    2015-04-01

    Full Text Available Os adesivos utilizados na colagem de madeiras para aplicações não estruturais normalmente contêm uma emulsão de poli(acetato de vinila (PVAc estabilizada com poli(álcool vinílico e alguns aditivos. A ligação adesiva formada com essa classe de adesivo é pobre quando exposta à umidade e à temperatura. Nesse contexto, a classificação prévia dos adesivos utilizados para aplicações não estruturais, com resistência à umidade e à temperatura, é muito importante para a qualidade e durabilidade das juntas adesivas. Neste trabalho, foi estudada a influência de três espécies de madeiras (Fagus sylvatica L., Mimosa scabrella Bentham e Micropholis cf. venulosa Mart. & Eichler na resistência ao cisalhamento das juntas adesivas preparadas com três adesivos vinílicos, sintetizados com diferentes concentrações do N-butoximetilacrilamida (NBMA. Os ensaios de resistência ao cisalhamento, na linha de colagem, foram realizados sob diferentes ciclos de acondicionamento das juntas adesivas. Os resultados indicaram que há diferenças significativas na resistência de colagem das juntas adesivas e na porcentagem de falha na madeira provocada, tanto pela espécie de madeira quanto pelo tipo de adesivo utilizado. Os adesivos produzidos foram classificados de acordo com a classe de durabilidade, após várias etapas de acondicionamento. Os valores mais altos de resistência ao cisalhamento foram observados nas juntas coladas com as madeiras de Micropholis cf. venulosa Mart. & Eichler e Fagus sylvatica L., com o adesivo AD-3. O menor valor de resistência ao cisalhamento foi observado nas juntas adesivas preparadas com a madeira da espécie Mimosa scabrella Bentham. A madeira Micropholis cf. venulosa Mart. & Eichler mostrou-se mais adequada para a substituição da madeira Fagus sylvatica L.

  5. Inovação e sustentabilidade na produção de energia: o caso do sistema setorial de energia eólica no Brasil

    Directory of Open Access Journals (Sweden)

    Thiago Cavalcante Nascimento

    Full Text Available Este artigo tem por objetivo verificar como as ações do sistema setorial brasileiro de energia eólica se relacionam com as perspectivas econômicas, sociais e ambientais que caracterizam inovações sustentáveis. Argumenta que as questões energéticas estão no cerne do desenvolvimento humano ao longo de sua história e que, em decorrência do atual cenário de mudanças climáticas, o desenvolvimento de fontes alternativas de energia é de vital importância na contemporaneidade. Metodologicamente, o estudo pode ser considerado exploratório e descritivo em relação aos fins e bibliográfico no que diz respeito aos meios. Foram utilizados dados primários de agências nacionais, regionais e mundiais de energia eólica para aumentar a consistência das informações coletadas e do trabalho como um todo. Os resultados evidenciam que o sistema setorial de energia eólica está estruturado em torno de uma série de instituições públicas, autarquias, associações de pesquisa e outros stakeholders que demonstram crescente interesse no desenvolvimento do setor no país. Os dados indicam, ainda, que os valores alcançados ao longo dos últimos leilões de energia eólica têm evidenciado o potencial de competitividade dessa fonte energética em comparação com as demais. Conclusivamente, é possível verificar que os pilares da sustentabilidade podem ser visualizados ao longo de praticamente todas as questões envolvendo a implantação de novas usinas eólicas, mas que a dimensão econômica ainda é a de maior destaque, tornando as dimensões sociais e ambientais dependentes da capacidade dessa modalidade de energia competir com outras.

  6. KIT EDUCACIONAL PARA ESTUDO DE GERAÇÃO ELÉTRICA A PARTIR DE ENERGIA EÓLICA

    Directory of Open Access Journals (Sweden)

    Antonio Luiz P. S. Campos

    2010-09-01

    Full Text Available Vários estudos desenvolvidos nos últimos anos apontam para as implicações e impactos sócio-ambientais do consumo de energia. Fontes de energias renováveis são apresentadas como alternativa para atender as demandas da sociedade com qualidade, segurança e redução dos danos ambientais decorrentes do consumo de energia. Este artigo apresenta uma proposta de kit educacional para ensino do uso de energia eólica na geração de energia elétrica. Inicialmente, o artigo descreve a evolução do aproveitamento da energia eólica. Depois, o artigo apresenta algumas experiências sobre o ensino desse tipo de energia no ensino médio e superior. O kit educacional é apresentado, mostrando-se resultados obtidos com o aerogerador tais como tensão gerada e circuitos eletrônicos utilizados. Algumas práticas são sugeridas. Por fim, as principais conclusões acerca do sistema são apresentadas.

  7. Fast reactors in nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Kazachkovskii, O

    1981-02-01

    The possible applications are discussed of fast reactor nuclear power plants. Basic differences are explained in fast and thermal reactors, mainly with a view to nuclear fuel utilization. Discussed in more detail are the problems of nuclear fuel reproduction and the nost important technical problems of fast reactors. Flow charts are shown of heat transfer for fast reactors BN-350 (loop design) and BN-600 (integral coolant circuit design). Main specifications are given for demonstration and power fast reactors in operation, under construction and in project-stage.

  8. Social representation for future teachers on the nuclear energy: probable implications of the public opinion; Representacoes sociais de futuros professores a respeito da energia nuclear: possiveis implicacoes na opiniao publica

    Energy Technology Data Exchange (ETDEWEB)

    Ayllon, Rafaella Menezes; Farias, Luciana Aparecida, E-mail: rafaellayllon@hotmail.com [Universidade Federal de Sao Paulo (UNIFESP), Sao Paulo, SP (Brazil); Favaro, Deborah I.T., E-mail: ditfavaro@yahoo.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    This study aimed to study the SR (social representation) regarding the 'Nuclear Energy' (NW) and 'Nuclear Chemistry' (NC) of students of Science - Bachelor of Federal University of Sao Paulo - UNIFESP. Individual questionnaires to research the topic, followed by the presentation of seminars with the focus of the research were applied. The methodology used was the technique of free word (Abric ,1994) which gives the frequency of each element that was mentioned and their average order of evocation, as well as semi -structured questionnaire with questions. Among the first results, it was found that the words 'Bomb' and 'Reactor' were the most mentioned by the group when asked evocations related to 'NE', while the terms 'Health' and 'Safety' are among the least mentioned. When referring to 'NC' the most frequent terms were 'Chemistry' and 'Atoms/Elements and 'Reactor' and 'Development' were less frequent. However, even though as a possible central core elements that match a negative SR theme, these students indicated Nuclear Energy as a strong option/option for diversifying the Brazilian energy matrix.

  9. Advanced nuclear reactor and nuclear fusion power generation

    International Nuclear Information System (INIS)

    2000-04-01

    This book comprised of two issues. The first one is a advanced nuclear reactor which describes nuclear fuel cycle and advanced nuclear reactor like liquid-metal reactor, advanced converter, HTR and extra advanced nuclear reactors. The second one is nuclear fusion for generation energy, which explains practical conditions for nuclear fusion, principle of multiple magnetic field, current situation of research on nuclear fusion, conception for nuclear fusion reactor and economics on nuclear fusion reactor.

  10. La actividad fotográfica durante la Guerra Civil a través de las fichas de filiación de la Junta Delegada de Defensa de Madrid (1936-1939

    Directory of Open Access Journals (Sweden)

    Juan Miguel Sánchez Vigil

    2014-03-01

    Full Text Available La actividad fotográfica en Madrid durante la guerra civil fue controlada por la Delegación de Propaganda y Prensa de la Junta Delegada de Defensa de Madrid, organismo que elaboró fichas de filiación que rellenaron los propios implicados. Se analizan estos documentos, conservados en el Centro de Documentación de la Memoria Histórica, para lo que se han elaborado dos bases de datos y se ha consultado la bibliografía especializada. Los resultados obtenidos son de relevancia para la historia de la fotografía española ya que aparecen nuevos autores y se aporta información sobre los ya conocidos. Asimismo el estudio nos permite conocer las instituciones y empresas para las que trabajaron, las tareas específicas que realizaron y su vinculación a sindicatos, partidos políticos, entidades públicas o privadas, y agrupaciones como la Sociedad Obrera de Fotógrafos Profesionales, Unión Fotográfica, Asociación de Profesionales de Prensa y Unión de Informadores Gráficos de Prensa. Se detalla la actividad de los reporteros gráficos y de los retratistas de galería, el papel de las mujeres y el de los profesionales extranjeros que acudieron a nuestro país en funciones informativas y humanitarias.

  11. Fuel element for nuclear reactors

    International Nuclear Information System (INIS)

    Cadwell, D.J.

    1982-01-01

    The invention concerns a fuel element for nuclear reactors with fuel rods and control rod guide tubes, where the control rod guide tubes are provided with flat projections projecting inwards, in the form of local deformations of the guide tube wall, in order to reduce the radial play between the control rod concerned and the guide tube, and to improve control rod movement. This should ensure that wear on the guide tubes is largely prevented which would be caused by lateral vibration of the control rods in the guide tubes, induced by the flow of coolant. (orig.) [de

  12. Palomares Summary Report

    Science.gov (United States)

    1975-01-15

    Navascues , President of the Junta de Energia Nuclear OEN), discussed the radiation situation and recovery operations with newsmen. A lengthy article was...allegations of the ILTA SANOMAT story. 204 SECTION7 SUBSEQUENT BIOMEDICAL AND ENVIRONMENTAL FACTORS The fact that Junta de Energia Nuclear (TEN...Palomares incident. The program was to be strictly under the direction of the Junta de Energia Nuclear’s Division de Medicine y Proteccion (Dr. Eduardo

  13. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E. D.

    1984-01-01

    An array of rods is assembled to form a fuel element for a pressurized water reactor, the rods comprising zirconium alloy sheathed nuclear fuel pellets and containing helium. The helium gas pressure is selected for each rod so that it differs substantially from the helium gas pressure in its closest neighbors. In a preferred arrangement the rods are arranged in a square lattice and the helium gas pressure alternates between a relatively high value and a relatively low value so that each rod has as its closest neighbors up to four rods containing helium gas at the other pressure value

  14. Nuclear reactor fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Hindle, E. D.

    1984-10-16

    An array of rods is assembled to form a fuel element for a pressurized water reactor, the rods comprising zirconium alloy sheathed nuclear fuel pellets and containing helium. The helium gas pressure is selected for each rod so that it differs substantially from the helium gas pressure in its closest neighbors. In a preferred arrangement the rods are arranged in a square lattice and the helium gas pressure alternates between a relatively high value and a relatively low value so that each rod has as its closest neighbors up to four rods containing helium gas at the other pressure value.

  15. Nuclear reactor control assembly

    International Nuclear Information System (INIS)

    Negron, S.B.

    1991-01-01

    This patent describes an assembly for providing global power control in a nuclear reactor having the core split into two halves. It comprises a disk assembly formed from at least two disks each machined with an identical surface hole pattern such that rotation of one disk relative to the other causes the hole pattern to open or close, the disk assembly being positioned substantially at the longitudinal center of and coaxial with the core halves; and means for rotating at least one of the disks relative to the other

  16. Electric energy saving in the cellulose and paper industry; Ahorro de energia electrica en la industria de celulosa y papel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    This paper delineates the results of the demonstration project for electric energy saving, which is one of the twenty four projects in which the Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE) sponsors the diagnosis as well as the applied measures and the measures currently in application. Also the potential opportunity areas and the measures applied and in course of application, as well as the required investments and their recuperation periods. [Espanol] En este trabajo se describen los resultados del proyecto de demostracion de ahorro de energia electrica que es uno de los veinticuatro proyectos, en los que el Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE) financia tanto el diagnostico como la aplicacion de medidas. Se presentan tanto las areas de oportunidad, potenciales y medidas aplicadas y en aplicacion, asi como las inversiones requeridas y los periodos de recuperacion de las mismas.

  17. Electric energy saving in the cellulose and paper industry; Ahorro de energia electrica en la industria de celulosa y papel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    This paper delineates the results of the demonstration project for electric energy saving, which is one of the twenty four projects in which the Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE) sponsors the diagnosis as well as the applied measures and the measures currently in application. Also the potential opportunity areas and the measures applied and in course of application, as well as the required investments and their recuperation periods. [Espanol] En este trabajo se describen los resultados del proyecto de demostracion de ahorro de energia electrica que es uno de los veinticuatro proyectos, en los que el Fideicomiso de Apoyo al Programa de Ahorro de Energia (FIDE) financia tanto el diagnostico como la aplicacion de medidas. Se presentan tanto las areas de oportunidad, potenciales y medidas aplicadas y en aplicacion, asi como las inversiones requeridas y los periodos de recuperacion de las mismas.

  18. Modelos para estimar as exigências de energia metabolizável para poedeiras

    OpenAIRE

    Sakomura,Nilva Kazue; Basaglia,Roberta; Sá-Fortes,Cristina M. L.; Fernandes,João Batista K.

    2005-01-01

    Objetivou-se, com este trabalho, elaborar um modelo para estimar as exigências de energia metabolizável (EM) para poedeiras leves da linhagem Lohmann LSL, utilizando-se o método fatorial. Para determinar o efeito da temperatura sobre as exigências de EM para mantença, foram conduzidos experimentos em câmaras climáticas com temperaturas constantes de 12, 22 e 31ºC, utilizando a técnica do abate comparativo. A exigência de energia líquida para o ganho de peso foi determinada por meio da regress...

  19. Nuclear reactor container

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1989-01-01

    Aerosol filters considered so far for nuclear reactor containers in conventional BWR type nuclear power plants make the facility larger and involve a risk of clogging. In view of the above, in the present invention, the diameter of a flow channel of gases entering from a bent pipe to a suppression pool is made smaller thereby decreasing the diameter of gas bubbles in the supperssional pool. Since this reduces the force of surface tension, the diameter of resulted gas bubbles is made remarkably smaller as compared with the case where the gases are released from the lower end of the bent pipe. Since the absorption velocity of bubble-entrained aerosols into water is in proportion to the square of the bubble diameter, the absorption efficiency can be increased remarkably by reducing the diameter of the gas bubbles. Accordingly, it is possible to improve the efficiency of eliminating radioactivity of released gases. (K.M.)

  20. Plano de social media marketing para a TAP Portugal

    OpenAIRE

    Lopes, Andreia Cristina Figueiredo

    2014-01-01

    Mestrado em Marketing O social media marketing adquire cada vez maior relevo para as empresas e exige, tal como noutras áreas de marketing, a delineação de um plano estratégico por forma a potenciar o seu sucesso. Tomando como objecto de estudo a companhia aérea TAP Portugal, foi elaborado um Plano de Social Media Marketing, com base no modelo conceptual de Barker et al. (2013), designado de "Social Media Planning Cycle". Para a elaboração do Plano, foram recolhidos dados primários, seguin...

  1. Papers presented at the Fourteenth International conference on Plasma Physics and Controlled Nuclear Fusion Research. Organization International de la Energia Atomica Wuerzberg, Alemania 30 September - 7 October 1992

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains the contributions of the CIEMAT's Fusion Unit to the 14th International Conference on Plasma Physics and Controlled Nuclear Fusion Research that was held by the International Atomic Energy Agency in Wuerzberg, Germany from 30 September to 7 October 1992. Three papers were presented that summarized the, main lines of work done in the Unit during the previous two years: The first one on the theoretical advances in the understanding of the Fexible Heliac TJ-II under construction, the second on the confinement studies performed in the operating TJ-I Tokamak and the third one on the description of the physical properties of the soon to be started TJ-IU Torsatron. (Author) 25 refs

  2. Power Nuclear Reactors: technology and innovation for development in future; Centrales Nucleares de Potencia: tecnologias actuales e innovaciones para el futuro

    Energy Technology Data Exchange (ETDEWEB)

    Suarez Antola, R [Universidad Catolica del Uruguay, Montevideo(Uruguay); Ministerio de Industria Energia y Minerria, Montevideo(Uruguay)

    2009-07-01

    The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view.

  3. Thermionic nuclear reactor systems

    International Nuclear Information System (INIS)

    Kennel, E.B.

    1986-01-01

    Thermionic nuclear reactors can be expected to be candidate space power supplies for power demands ranging from about ten kilowatts to several megawatts. The conventional ''ignited mode'' thermionic fuel element (TFE) is the basis for most reactor designs to date. Laboratory converters have been built and tested with efficiencies in the range of 7-12% for over 10,000 hours. Even longer lifetimes are projected. More advanced capabilities are potentially achievable in other modes of operation, such as the self-pulsed or unignited diode. Coupled with modest improvements in fuel and emitter material performance, the efficiency of an advanced thermionic conversion system can be extended to the 15-20% range. Advanced thermionic power systems are expected to be compatible with other advanced features such as: (1) Intrinsic subcritically under accident conditions, ensuring 100% safety upon launch abort; (2) Intrinsic low radiation levels during reactor shutdown, allowing manned servicing and/or rendezvous; (3) DC to DC power conditioning using lightweight power MOSFETS; and (4) AC output using pulsed converters

  4. Nuclear reactor installation

    International Nuclear Information System (INIS)

    Jungmann, A.

    1976-01-01

    A nuclear reactor metal pressure vessel is surrounded by a concrete wall forming an annular space around the vessel. Thermal insulation is in this space and surrounds the vessel, and a coolant-conductive layer is also in this space surrounding the thermal insulation, coolant forced through this layer reducing the thermal stress on the concrete wall. The coolant-conductive layer is formed by concrete blocks laid together and having coolant passages, these blocks being small enough individually to permit them to be cast from concrete at the reactor installation, the thermal insulation being formed by much larger sheet-metal clad concrete segments. Mortar is injected between the interfaces of the coolant-conductive layer and concrete wall and the interfaces between the fluid-conductive layer and the insulation, a layer of slippery sheet material being interposed between the insulation and the mortar. When the pressure vessel is thermally expanded by reactor operation, the annular space between it and the concrete wall is completely filled by these components so that zero-excursion rupture safeguard is provided for the vessel. 4 claims, 1 figure

  5. Nuclear reactor building

    International Nuclear Information System (INIS)

    Oshima, Nobuaki.

    1991-01-01

    The secondary container in a nuclear reactor building is made of a transparent structure having a shielding performance such as lead glass, by which the inside of the secondary container can be seen without undergoing radiation exposure. In addition, an operator transportation facility capable of carrying about 5 to 10 operators at one time is disposed, and the side of the facility on the secondary container is constituted with a transparent material such as glass, to provide a structure capable of observing the inside of the secondary container. The ventilation and air conditioning in the operator's transportation facility is in communication with the atmosphere of a not-controlled area. Accordingly, operators at the outside of the reactor building can reach the operator's transportation facility without taking and procedures for entering the controlled area and without undergoing radiation exposure. The inside of the secondary container in the reactor building can be seen from various directions through the transparent structure having the shielding performance. (N.H.)

  6. Luis Crespí Jaume, científico de la Junta para Ampliación de Estudios y catedrático de Agricultura del Instituto-Escuela

    Directory of Open Access Journals (Sweden)

    Masip Hidalgo, Carmen

    2011-06-01

    Full Text Available This article about Luis Crespí Jaume (Madrid, 1889- 1963 aims to recall his teaching work as Agriculture Professor at “Madrid Instituto-Escuela” and its stage as scientist linked to “Junta para Ampliación de Estudios “(JAE. This following text focuses on his teaching practice which was based on the analysis of the didactic planning in the field of Agriculture that he developed, the methodology applied, the scientific materials used in the class and laboratory sessions, the class and laboratory students’ notebooks and finally the books that they consulted for their classworks.

    Este artículo sobre Luis Crespí Jaume (Madrid, 1889-1963 pretende recordar su labor pedagógica como catedrático de Agricultura del Instituto-Escuela de Madrid y su etapa como científico vinculado a la Junta para Ampliación de Estudios (JAE. Nuestro comentario sobre su práctica docente se basa en el análisis de la programación de la materia de Agricultura que él mismo elaboró, en la metodología que aplicó, en los materiales científicos utilizados en el aula y en el laboratorio, en los cuadernos de clase y de prácticas de sus alumnos y en los libros que éstos consultaban para sus trabajos.

  7. Virtual nuclear reactor for education of nuclear reactor physics

    International Nuclear Information System (INIS)

    Tsuji, Masashi; Narabayashi, Takashi; Shimazu, Youichiro

    2008-01-01

    As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

  8. Etudes sur le Portugal au Temps de l'Humanisme

    Directory of Open Access Journals (Sweden)

    J. Cruz Costa

    1953-06-01

    Full Text Available BATAILLON (Marcel. — Etudes sur le Portugal au Temps de l'Humanisme.  Acta Universitatis Conimbrigencis, 1952, 309 pp. (Primeiro Parágrafo do Artigo O Prof. Marcel Bataillon, erudito dos mais inteligentes da França atual, autor de uma obra que é hoje impr:scindível para quem pretenda estudar o humanismo renascentista na Espanha ou em Portugal, diríamos melhor, talvez: para quem pretenda estudar o Humanismo e a Renascença, — acaba de publicar, na coleção Acta Universitatis Conimbrigencis, êste volume no qual reune alguns trabalhos da mais alta importância para o conhecimento de muitos aspectos da vida espiritual portuguêsa do século XVI.

  9. Nuclear reactor power supply

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

    The redundant signals from the sensor assemblies measuring the process parameters of a nuclear reactor power supply are transmitted each in its turn to a protection system which operates to actuate the protection apparatus for signals indicating off-process conditions. Each sensor assembly includes a number of like sensors measuring the same parameters. The sets of process signals derived from the sensor assemblies are each in its turn transmitted from the protection system to the control system which impresses control signals on the reactor or its components to counteract the tendency for conditions to drift off-normal status requiring operation of the protection system. A parameter signal selector is interposed between the protection system and the control system. This selector prevents a parameter signal of a set of signals, which differs from the other parameters signals of the set by more than twice the allowable variation of the sensors which produce the set, from passing to the control system. The selectors include a pair of signal selection units, one unit sending selected process signals to primary control channels and the other sending selected process signals to back-up control channels. Test signals are periodically impressed by a test unit on a selected pair of a selected unit and control channels. When test signals are so impressed the selected control channel is disabled from transmitting control signals to the reactor and/or its associated components. This arrangement eliminates the possibility that a single component failure which may be spurious will cause an inadvertent trip of the reactor during test

  10. Problems in producing nuclear reactor for medical isotopes and the Global Crisis of molybdenum supply; Problemas en la produccion en reactores nucleares de isotopos con fines medicos y la crisis mundial de suministro de molibdeno ({sup 9}9Mo)

    Energy Technology Data Exchange (ETDEWEB)

    Zubiarrain, A.

    2011-07-01

    Nuclear medicine uses drugs that incorporate a radioactive isotope radiopharmaceuticals. Every year are performed, worldwide, 35 million nuclear medicine procedures, of which 80% are done with radiopharmaceuticals containing the isotope, molybdenum-99, produced in nuclear reactors. In recent years, there have been several supply crisis of molybdenum-99, which have hampered diagnostic procedure with technitium-99m. (Author)

  11. Analizan partículas calientes del accidente nuclear de Palomares

    OpenAIRE

    León Dueñas, Sergio David

    2012-01-01

    Investigadores pertenecientes al Centro Nacional de Aceleradores, CNA, (Universidad de Sevilla-Junta de Andalucía-CSIC) en colaboración con la Organización Internacional de la Energía Atómica (IAEA), han llevado a cabo me didas de elementos transuránicos en partículas calientes procedentes de accidentes nucleares tales como el de Thule (Groenlandia) o Palomares (España).

  12. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology; Comunicaciones recibidas de diversos Estados Miembros relativas a las directrices para las transferencias de equipos, materiales y programas informaticos (software) de doble uso del ambito nuclear y tecnologia relacionada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-11

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [Spanish] El Director General del Organismo Internacional de Energia Atomica ha recibido Notas verbales de fecha 1 de diciembre de 2005 de los Representantes Permanentes ante el Organismo de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, Croacia, Eslovenia, Espana, Estados Unidos de America, Estonia, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Letonia, Lituania, Luxemburgo, Malta, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Sudafrica, Suecia, Suiza, Turquia y Ucrania relativas a las transferencias de equipos, materiales y programas informaticos de doble uso del ambito nuclear y tecnologia relacionada.

  13. Nuclear reaction data and nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Paver, N [University of Trieste (Italy); Herman, M [International Atomic Energy Agency, Vienna (Austria); Gandini, A [ENEA, Rome (Italy)

    2001-12-15

    These two volumes contain the lecture notes of the workshop 'Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety', which was held at the Abdus Salam ICTP in the Spring of 2000. The workshop consisted of five weeks of lecture courses followed by practical computer exercises on nuclear data treatment and design of nuclear power systems. The spectrum of topics is wide enough to timely cover the state-of-the-art and the perspectives of this broad field. The first two weeks were devoted to nuclear reaction models and nuclear data evaluation. Nuclear data processing for applications to reactor calculations was the subject of the third week. On the last two weeks reactor physics and on-going projects in nuclear power generation, waste disposal and safety were presented.

  14. Determination of nitrogen in wheat flour through Activation analysis using Fast neutron flux of a Thermal nuclear reactor; Determinacion de nitrogeno en harina de trigo mediante analisis por activacion empleando el flujo de neutrones rapidos de un reactor nuclear termico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, T

    1976-07-01

    In this work is done a technical study for determining Nitrogen (protein) and other elements in wheat flour Activation analysis, with Fast neutrons from a Thermal nuclear reactor. Initially it is given an introduction about the basic principles of the methods of analysis. Equipment used in Activation analysis and a brief description of the neutron source (Thermal nuclear reactor). The realized experiments for determining the flux form in the irradiation site, the half life of N-13 and the interferences due to the sample composition are included too. Finally, the obtained results by Activation and the Kjeldahl method are tabulated. (Author)

  15. La perversión de lo privado: violencia e incesto en Malas Juntas, Oxido de Carmen y Los vigilantes

    Directory of Open Access Journals (Sweden)

    Nicolás Román

    2014-07-01

    Full Text Available En la dictadura, la irracionalidad y la violencia repercutieron en la construcción de la intimidad de los habitantes del país. El desarrollo de los mecanismos de persecución y ejecución de los disidentes atentó contra las formas de sociabilidad, generando una opacidad en las relaciones sociales. En distintos relatos se buscan los elementos que pervierten la construcción de la subjetividad y transforman la intimidad en dispositivos torcidos de la vida privada. A partir de José Leandro Urbina, Ana María del Río y Diamela Eltit se hará un análisis que liga la corrupción de los vínculos de parentesco y la distorsión de la casa como el refugio frente a las agresiones del régimen.

  16. Immobilization of Ion Exchange radioactive resins of the TRIGA Mark III Nuclear Reactor; Inmovilizacion de resinas de intercambio ionico radiactivas del reactor nuclear TRIGA Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Martinez, H

    1999-07-01

    In the last decades many countries in the world have taken interest in the use, availability, and final disposal of dangerous wastes in the environment, within these, those dangerous wastes that contain radioactive material. That is why studies have been made on materials used as immobilization agent of radioactive waste that may guarantee its storage for long periods of time under drastic conditions of humidity, temperature change and biodegradation. In mexico, the development of different applications of radioactive material in the industry, medicine and investigation, have generated radioactive waste, sealed and open sources, whose require a special technological development for its management and final disposal. The present work has as a finality to develop the process and define the agglutinating material, bitumen, cement and polyester resin that permits immobilization of resins of Ionic Exchange contaminated by Barium 153, Cesium 137, Europium 152, Cobalt 60 and Manganese 54 generated from the nuclear reactor TRIGA Mark III. Ionic interchange contaminated resin must be immobilized and is analysed under different established tests by the Mexican Official Standard NOM-019-NUCL-1995 {sup L}ow level radioactive wastes package requirements for its near-surface final disposal. Immobilization of ionic interchange contaminated resins must count with the International Standards applicable in this process; in these standards, the following test must be taken in prototype examples: Free-standing water, leachability, compressive strength, biodegradation, radiation stability, thermal stability and burning rate. (Author)

  17. Natural ionizing system to electrical protection and energy; Sistema ionizante natural de proteccion electrica y energias

    Energy Technology Data Exchange (ETDEWEB)

    Cabareda Fermin; Luis [Universidad de Los Andes (Venezuela)]. E-mail: lcabaredaf@gmail.com

    2013-03-15

    This is the new highest technology, 100% Venezuelan and unique in the world, technological innovation, world patent for maximum protection, security and zero risk (0) to all electrical and power generation systems: hydroelectric and thermoelectric power plants, wind, nuclear and solar power plants, etc; it's the only technology around the world that has the potential to disperse and propagate to land mass the enormous energies associated to the atmospheric discharges (lightning), which are in the order: 200,000 to 500,000 Amperes; 1,000 million Kilowatts and high-level transient voltage of 100 million Volts. This new high technology is the solution to the paradigm of Benjamin Franklin and it is the mechanism to end blackouts that produce so many damages and losses of billions of dollars to both generators and users of electrical service, throughout the world. [Spanish] Esta nueva mas alta tecnologia, 100% venezolana y unica en el mundo, innovacion tecnologica, patente mundial ofrece maxima proteccion, seguridad y riesgo cero (0) a todos los sistemas de generacion electrica: centrales hidroelectricas, termoelectricas, de viento, nucleares y solar, otros; es la unica tecnologia en el mundo que tiene el potencial para dispersar y propagar a la masa terrestre las enormes energias asociadas a las descargas atmosfericas (rayos) que estan en el orden de: 200.000 a 500.000 amperios, 1.000 millones de kilovatios y voltajes transitorios de alto nivel de 100 millones de voltios. Esta nueva alta tecnologia es la solucion al paradigma de Benjamin Franklin y es el mecanismo para eliminar apagones que producen danos y perdidas de billones de dolares para ambos: generados y usuarios del servicio electrico, alrededor del mundo.

  18. Nuclear reactors safety issues

    International Nuclear Information System (INIS)

    Barre, Francois; Seiler, Nathalie

    2008-01-01

    Full text of publication follows: Since the seventies, economic incentives have led the utilities to drive a permanent evolution of the light water reactor (LWR). The evolution deals with the reactor designs as well as the way to operate them in a more flexible manner. It is for instance related to the fuel technologies and management. On the one hand, the technologies are in continuous evolution, such as the fuel pellets (MOX, Gd fuel, or Cr doped fuels..) as well as advanced cladding materials (M5 TM , MDA or ZIRLO). On the other hand, the fuel management is also subject to continuous evolution in particular in terms of increasing the level of burn-up, the reactor (core) power, the enrichment, as well as the duration of reactor cycles. For instance, in a few years in France, the burn-up has raised beyond the value of 39 GWj/t, initially authorized up to 52 GWj/t for the UO 2 fuel. In the near future, utilities foreseen to reach fuel burn-up of 60 GWj/t for MOX fuel and 70 GWj/t for UO 2 fuel. Furthermore, the future reactor of fourth generation will use new fuels of advanced conception. Furthermore with the objective of improving the safety margins, methods and calculation tools used by the utilities in the elaboration of their safety demonstrations submitted to the Safety Authority, are in movement. The margin evaluation methodologies often consist of a calculation chain of best-estimate multi-field simulations (e.g. various codes being coupled to simulate in a realistic way the evolution of the thermohydraulic, neutronic and mechanic state of the reactor). The statistical methods are more and more sophisticated and the computer codes are integrating ever-complex physical models (e.g. three-dimensional at fine scale). Following this evolution, the Institute of Radioprotection and Nuclear Safety (IRSN), whose one of the roles is to examine the safety records and to rend a technical expertise, considers the necessity of reevaluating the safety issues for advanced

  19. Nuclear reactors for the future

    International Nuclear Information System (INIS)

    Vijayan, P.K.; Kamble, M.T.; Dulera, I.V.

    2013-01-01

    For the sustainable development of nuclear power plants with enhanced safety features, economic competitiveness, proliferation resistance and physical protection, several advanced reactor developments have been initiated world-wide. The major advanced reactor initiatives and the proposed advanced reactor concepts have been briefly reviewed along with their advantages and challenges. Various advanced reactor designs being pursued in India have also been briefly described in the paper. (author)

  20. A nuclear reactor core fuel reload optimization using Artificial-Ant-Colony Connective Networks; Recarga de reatores nucleares utilizando redes conectivas de colonias de formigas artificiais

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Alan M.M. de; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear]. E-mail: alan@lmp.ufrj.br; schirru@lmp.ufrj.br

    2005-07-01

    A Pressurized Water Reactor core must be reloaded every time the fuel burnup reaches a level when it is not possible to sustain nominal power operation. The nuclear core fuel reload optimization consists in finding a burned-up and fresh-fuel-assembly pattern that maximizes the number of full operational days. This problem is NP-hard, meaning that complexity grows exponentially with the number of fuel assemblies in the core. Besides that, the problem is non-linear and its search space is highly discontinual and multimodal. In this work a parallel computational system based on Ant Colony System (ACS) called Artificial-Ant-Colony Networks is introduced to solve the nuclear reactor core fuel reload optimization problem. ACS is a system based on artificial agents that uses the reinforcement learning technique and was originally developed to solve the Traveling Salesman Problem, which is conceptually similar to the nuclear fuel reload problem. (author)

  1. Influência da Espessura do Filme Polimérico Intermediário na Resistência Mecânica de Juntas Híbridas de Alumínio 2024-T3 e CF-PPS Produzidas por União Pontual por Fricção

    Directory of Open Access Journals (Sweden)

    Natália M. André

    2016-03-01

    Full Text Available Resumo A União Pontual por Fricção (FSpJ é uma técnica inovadora para união de estruturas híbridas metal-polímero e baseia-se na geração de calor por fricção. Juntas de alumínio 2024-T3 e compósito laminado de poli(sulfeto de fenileno com fibra de carbono (CF-PPS foram produzidas com filme intermediário de PPS. Duas espessuras de filme foram investigadas: 100 e 500 µm. Ensaios de cisalhamento sob tração demonstraram que as juntas com filmes de 100 µm são mais resistentes (2093 ± 180 N em relação às juntas com filme de 500 µm (708 ± 69 N. Adicionalmente, as superfícies de fratura das juntas revelaram áreas de união maiores para as juntas com filmes de 100 µm (53 ± 2 contra 40 ± 1 mm2. Para o filme mais fino, a extensão do amolecimento devido ao calor friccional é maior. Consequentemente, a baixa viscosidade atingida com a fusão do polímero favorece a molhabilidade das superfícies dos componentes da junta pelo PPS amolecido, resultando em melhor adesão entre as partes. Ademais, análises microestruturais demonstraram que a formação do cerne metálico e a interdifusão das moléculas de PPS entre compósito e filme também são favorecidas. Portanto, concluiu-se que a adição do filme mais fino produziu juntas mais resistentes.

  2. Nuclear reactor cooling device

    International Nuclear Information System (INIS)

    Hoshi, Masaya; Makihara, Yoshiaki.

    1985-01-01

    Purpose: To improve the heat transfer performance, as well as reducing and simplifying the structure while preventing the intrusion of primary coolants to utilization systems. Constitution: Heat transfer from the primary coolant circuit to the utilization circuits is conducted by means of heat pipe type heat exchangers. The heat exchanger comprises a tightly closed vessel divided by a partition wall, through which a plurality of heat pipes are passed. The primary coolants receiving the heat from the nuclear reactor enter the first chamber of the heat exchanger to heat the evaporating portion of the heat pipes. The heated flow of steams in the heat pipes transfer to the condensating portion in the second chamber to conduct heat exchange with the utilization system. In this way, since secondary coolant circuits are saved, the heat transfer performance can be improved significantly and the risk of failure can be reduced. (Kamimura, M,)

  3. Nuclear reactor spacer assembly

    International Nuclear Information System (INIS)

    Anthony, A.J.; Groves, M.D.

    1979-01-01

    A fuel assembly for a nuclear reactor is disclosed wherein the fuel element receiving and supporting grid is comprised of a first metal, the guide tubes which pass through the grid assembly are comprised of a second metal and the grid is supported on the guide tubes by means of expanded sleeves located intermediate the grid and guide tubes. The fuel assembly is fabricated by inserting the sleeves, of initial outer diameter commensurate with the guide tube outer diameters, through the holes in the grid assembly provided for the guide tubes and thereafter expanding the sleeves radially outwardly along their entire length such that the guide tubes can subsequently be passed through the sleeves. The step of radial expansion, as a result of windows provided in the sleeves having dimensions commensurate with the geometry of the grid, mechanically captures the grid and simultaneously preloads the sleeve against the grid whereby relative motion between the grid and guide tube will be precluded

  4. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    Vikhorev, Yu.V.; Biryukov, G.I.; Kirilyuk, N.A.; Lobanov, V.N.

    1977-01-01

    A fuel assembly is proposed for nuclear reactors allowing remote replacement of control rod bundles or their shifting from one assembly to another, i.e., their multipurpose use. This leads to a significant increase in fuel assembly usability. In the fuel assembly the control rod bundle is placed in guide tube channels to which baffles are attached for fuel element spacing. The remote handling of control rods is provided by a hollow cylinder with openings in its lower bottom through which the control rods pass. All control rods in a bundle are mounted to a cross beam which in turn is mounted in the cylinder and is designed for grasping the whole rod bundle by a remotely controlled telescopic mechanism in bundle replacement or shifting. (Z.M.)

  5. Spectrographic determination of metallic impurities in organic coolants for nuclear reactors; Determinacion espectrografica de impurezas metalicas en refrigerantes organicos para reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martin Munoz, M; Alvarez Gonzalez, F

    1969-07-01

    A spectrochemical method for determining metallic impurities in organic coolants for nuclear reactors is given. The organic matter in solid samples is eliminated by controlled distillation and dry ashing in the presence of magnesium oxide as carrier. Liquid, samples are vacuum distillated. The residue is analyzed by carrier distillation and by total burning techniques. The analytical results are discussed and compared with those obtained destroying the organic matter without carrier and using the copper spark technique. (Author) 12 refs.

  6. Nuclear reactor container

    International Nuclear Information System (INIS)

    Shioiri, Akio.

    1992-01-01

    In a nuclear reactor container, a vent tube communication port is disposed to a pressure suppression pool at a position higher than the pool water therein for communication with an upper dry well, and the upper end opening of a dry well communication pipe is disposed at a position higher than the communication port. When condensate return pipeline is ruptured in the upper dry well, water in a water source pool is injected to the pressure vessel and partially discharged out of the ruptured port and a depressurization valve connected to the pressure vessel to the inside of the upper dry well. The discharged water stays in the upper dry well and, when the water level reaches the height of the vent tube communication port, it flows into the pressure suppression pool. Even in a state that the entire amount of water in the water source pool is supplied, since water does not reach the upper opening port of the dry well communication pipe, water does not flow into a lower dry well. Accordingly, the motor of a control rod drives disposed in the lower dry well can be prevented from submerging. The reactor core can be cooled more reliably, to improve the reliability of the pressure suppression function. (N.H.)

  7. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

  8. The program of reactors and nuclear power plants

    International Nuclear Information System (INIS)

    Calabrese, Carlos R.

    2001-01-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

  9. Potential of energy saving with photovoltaic systems; Potencialidad de ahorro de energia con sistemas fotovoltaicos

    Energy Technology Data Exchange (ETDEWEB)

    Guzman S, Eusebio; Bratu S, Neagu [Universidad Autonoma Metropolitana, Mexico, D. F. (Mexico)

    1998-12-31

    This paper presents an approach on the application of photovoltaic systems in energy saving. The problem of the electric energy demand in the coming years is analyzed and its consequences on the environment and on the energy reserves of conventional sources. A model of the electric circuit equivalent to a photovoltaic cell illustrates the behavior of the photovoltaic cell in function of the climatological conditions. The former in order to show some of the limiting factors in this type of generator. Also, the evolution of the applications of the photovoltaic systems and its forecasting in the installed capacity in the next 20 years, is described. [Espanol] En este trabajo se presenta un enfoque de la aplicacion de los sistemas fotovoltaicos en el ahorro de energia. Se plantea el problema del crecimiento de la demanda energetica en los proximos anos y sus consecuencias sobre el medio ambiente y las reservas de energia por fuentes convencionales. Un modelo del circuito electrico equivalente de una celda fotovoltaica ilustra el comportamiento del generador fotovoltaico en funcion de las condiciones climatologicas. Lo anterior con el fin de mostrar algunas limitantes de este tipo de generador. Tambien se describe la evolucion de las aplicaciones de los sistemas fotovoltaicos y el pronostico de la potencia instalada en los proximos 20 anos.

  10. Potential of energy saving with photovoltaic systems; Potencialidad de ahorro de energia con sistemas fotovoltaicos

    Energy Technology Data Exchange (ETDEWEB)

    Guzman S, Eusebio; Bratu S, Neagu [Universidad Autonoma Metropolitana, Mexico, D. F. (Mexico)

    1999-12-31

    This paper presents an approach on the application of photovoltaic systems in energy saving. The problem of the electric energy demand in the coming years is analyzed and its consequences on the environment and on the energy reserves of conventional sources. A model of the electric circuit equivalent to a photovoltaic cell illustrates the behavior of the photovoltaic cell in function of the climatological conditions. The former in order to show some of the limiting factors in this type of generator. Also, the evolution of the applications of the photovoltaic systems and its forecasting in the installed capacity in the next 20 years, is described. [Espanol] En este trabajo se presenta un enfoque de la aplicacion de los sistemas fotovoltaicos en el ahorro de energia. Se plantea el problema del crecimiento de la demanda energetica en los proximos anos y sus consecuencias sobre el medio ambiente y las reservas de energia por fuentes convencionales. Un modelo del circuito electrico equivalente de una celda fotovoltaica ilustra el comportamiento del generador fotovoltaico en funcion de las condiciones climatologicas. Lo anterior con el fin de mostrar algunas limitantes de este tipo de generador. Tambien se describe la evolucion de las aplicaciones de los sistemas fotovoltaicos y el pronostico de la potencia instalada en los proximos 20 anos.

  11. ENERGIA FÓSSIL: implantação de refletores na quadra de esportes, utilizando energia fóssil

    Directory of Open Access Journals (Sweden)

    Alisson Mazzola

    2011-07-01

    Full Text Available O presente projeto consiste na utilização da energia fóssil para aplicar melhorias na quadra desportiva da escola Oswaldo Cruz, localizada na cidade de Sinop/MT.Tais melhorias poderão ser vistas na iluminação, tomadas e acessibilidade. Todavia, isto irá trazer benefícios para toda a sociedade, como acontecimento de eventos esportivos, lúdicos e sua utilização no período noturno.A energia fornecida para a quadra será através de um motor a combustão (gasolina, que será menos poluente, pois os hidrocarbonetos da gasolina poluem menos que do óleo diesel.Assim será produzido 15 horas de iluminação por cada tanque do motor. 

  12. Graphite materials for nuclear reactors

    International Nuclear Information System (INIS)

    Oku, Tatsuo

    1991-01-01

    Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the surrounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related properties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described. (author)

  13. Technological advances in zero energy buildings; Avances tecnologicos en edificios de energia cero

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Milla, Guillermo; Perez Rebolledo, Hugo; Acoltzi Acoltzi, Higinio [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2011-07-01

    Buildings use a large amount of energy to operate and are one of the main sources of contaminating emissions. A building is a complex system and all of their components contribute to the total energy demand. The technology to construct zero-energy buildings is already available, but obstacles exist such as the lack of information and technical training of architects and engineers to design highly energy efficient buildings. The present article describes the progress to-date and the future prospects for the design and construction of zero-energy buildings, as well as the problems involved in its implementation. [Spanish] Los edificios usan una gran cantidad de energia para operar y son una de las principales fuentes de emisiones contaminantes. Un edificio es un sistema complejo y todos sus componentes contribuyen a la demanda total de energia. La tecnologia para construir edificios de energia cero ya esta disponible, pero existen barreras como falta de informacion o capacitacion tecnica a arquitectos e ingenieros, para disenar edificios de alta eficiencia energetica. El presente articulo muestra los avances a la fecha y la prospectiva para el diseno y construccion de edificios de energia cero, asi como la problematica para su implementacion.

  14. The situation of the nuclear energy in the world; A situacao da energia nucleoeletrica no mundo

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Jair Albo Marques de [and others

    1996-12-01

    This work presents an overview of the nuclear energy in the world. It approaches the following main topics: kinds of nuclear power plants; operation experience of the nuclear plants; environmental and social aspects of the nuclear energy; economic aspects of the nuclear energy; development of the reactors technology and supply of the nuclear fuel.

  15. Nuclear reactor container

    International Nuclear Information System (INIS)

    Moriyama, Takeo; Ochiai, Kanehiro; Niino, Tsuyoshi; Kodama, Toyokazu; Hirako, Shizuka.

    1988-01-01

    Purpose: To obtain structures suitable to a container structures for nuclear power plants used in those districts where earthquakes occur frequently, in which no local stresses are caused to the fundamental base portions and the workability for the fundamental structures is improved. Constitution: Basic stabilizers are attached to a nuclear reactor container (PCV) and a basic concrete recess for receiving a basic stabilizer is disposed in basic concretes. A top stabilizer is joined and fixed to a top stabilizer receiving plate at the inside of an outer shielding wall. On the other hand, a PCV top recess for conducting the load of PCV to the top stabilizer is attached to the top of the PCV. By disposing stabilizer structures allowing miner displacements at the two points, that is, the top and the lowermost portion of the PCV, no local stress concentrations can be generated to the extension on the axial direction of components due to the inner pressure of the PCV and to the horizontal load applied to the upper portion of the PCV upon earthquakes. (Yoshino, Y.)

  16. Prevalencia del Sobrepeso y de la Obesidad Infantil en Portugal.Programa MUNSI de Base Municipal

    OpenAIRE

    Rito, Ana; Silva, Ana Lúcia; Carvalho, Maria Ana; Ramos, Carlos; Breda, João

    2010-01-01

    INTRODUCIÓN: Hoy en día la prevalencia de obesidad infantil constituye uno de los problemas más serios de salud pública en Portugal. Estudios recientes demuestran que Portugal tiene una de las peores cifras de los paises de la Comunidad Europea. Hábitos alimentarios poco saludables relacionados con el consumo de alimentos de elevada densidad energética, principalmente en grasas saturadas y azúcares rápidos, asociados a bajos niveles de actividad física, surgen como los principales facto...

  17. Safety of nuclear power reactors

    International Nuclear Information System (INIS)

    MacPherson, H.G.

    1982-01-01

    Safety is the major public issue to be resolved or accommodated if nuclear power is to have a future. Probabilistic Risk Analysis (PRA) of accidental releases of low-level radiation, the spread and activity of radiation in populated areas, and the impacts on public health from exposure evolved from the earlier Rasmussen Reactor Safety Study. Applications of the PRA technique have identified design peculiarities in specific reactors, thus increasing reactor safety and establishing a quide for evaluating reactor regulations. The Nuclear Regulatory Commission and reactor vendors must share with utilities the responsibility for reactor safety in the US and for providing reasonable assurance to the public. This entails persuasive public education and information that with safety a top priority, changes now being made in light water reactor hardware and operations will be adequate. 17 references, 2 figures, 2 tables

  18. A nuclear reactor

    International Nuclear Information System (INIS)

    Keller, W.

    1974-01-01

    Between the steel pressure vessel of the pressurized water power reactor and the biological shield a gap is found which enables inspections as well as cooling by air or gas. Within the gap, fins are equally distributed around the circumference of the pressure vessel summing parallel to each other and to the longitudinal axis of the vessel or being inclined. The fins cross the gap for about 9/10. Each fin consists of a sectional bar supported with its foot on a girder. The girder has got a rectangular steel section of two sectional iron parts. Between one of the parts and a plate anchored in the biological shield a ceramic body is inserted as a heat insulation. A further heat insulation of aluminium foils connects the fins with each other and divides the gap into two concentric subspaces which can be streamed through by a gas having different temperatures. (DG) [de

  19. The dangers of irradiate uranium in nuclear reactors; Les dangers de l'uranium irradie dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The danger of the uranium cans sur-activated by the use in the nuclear reactors is triple: - Irradiation from afar, during manipulations of the cans. - Contamination of air when decladding. - Contamination of air by fire of uranium in a reactor in function The first two dangers are usual and can be treated thanks to the rules of security in use in the atomic industry. The third has an accidental character and claimed for the use of special and exceptional rules, overflowing the industrial setting, to reach the surrounding populations. (authors) [French] Le danger des cartouches d'uranium suractive par utilisation dans les reacteurs nucleaires est triple: - Irradiation a distance, lors des manipulations des cartouches. - Contamination de l'air au moment de leur degainage. - Contamination de l'air par incendie d'uranium dans un reacteur en fonctionnement. Les deux premiers dangers sont habituels et peuvent etre traites grace aux regles de securite en usage dans l'industrie atomique. Le troisieme revet un caractere accidentel et reclame l'emploi de regles speciales et exceptionnelles, debordant le cadre industriel, pour atteindre celui des populations environnantes. (auteurs)

  20. Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors; Calificacion del programa WIMS de calculo neutronico para diseno, seguimiento de operacion y analisis de accidentes de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lerner, A M [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina)

    1997-12-31

    A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

  1. Advances in the development of the Mexican platform for analysis and design of nuclear reactors: AZTLAN Platform; Avances en el desarrollo de la plataforma mexicana para analisis y diseno de reactores nucleares: AZTLAN Platform

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico); Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico)

    2017-09-15

    The AZTLAN platform project: development of a Mexican platform for the analysis and design of nuclear reactors, financed by the SENER-CONACYT Energy Sustain ability Fund, was approved in early 2014 and formally began at the end of that year. It is a national project led by the Instituto Nacional de Investigaciones Nucleares (ININ) and with the collaboration of Instituto Politecnico Nacional (IPN), the Universidad Autonoma Metropolitana (UAM) and Universidad Nacional Autonoma de Mexico (UNAM) as part of the development team and with the participation of the Laguna Verde Nuclear Power Plant, the National Commission of Nuclear Safety and Safeguards, the Ministry of Energy and the Karlsruhe Institute of Technology (Kit, Germany) as part of the user group. The general objective of the project is to modernize, improve and integrate the neutronic, thermo-hydraulic and thermo-mechanical codes, developed in Mexican institutions, in an integrated platform, developed and maintained by Mexican experts for the benefit of Mexican institutions. Two years into the process, important steps have been taken that have consolidated the platform. The main results of these first two years have been presented in different national and international forums. In this congress, some of the most recent results that have been implemented in the platform codes are shown in more detail. The current status of the platform from a more executive view point is summarized in this paper. (Author)

  2. Preparation of mandatory documentation before the start up of the RA-0 `zero power` nuclear reactor at Cordoba National University; Preparacion de la documentacion mandatoria para la puesta en marcha del reactor nuclear RA-0 en la Universidad Nacional de Cordoba

    Energy Technology Data Exchange (ETDEWEB)

    Martin, H R; Keil, W M; Pezzi, N

    1992-12-31

    Before the start up of the RA-0 `zero power` nuclear reactor installed at Cordoba National University, it was necessary to send to the Regulatory Authority the mandatory documentation which is required in the licensing process. With the previous papers existing for the operation in the first years of the `70, a work program for the future operational training personnel was elaborated. Based on the Authority`s applicable rules and the recommendations and with particular criteria originated in the working university conditions, the SAFETY report of RA-0 nuclear reactor was prepared. This paper describes the principal contents, items and documents involved in the safety report. (Author). [Espanol] Con motivo de la nueva puesta en servicio del REACTOR NUCLEAR RA-0 fue necesario elaborar la documentacion mandatoria requerida por la Autoridad Regulatoria Nacional. Siguiendo los lineamientos de las normas y recomendaciones vigentes e incluyendo criterios propios en lo que debia ser el contenido final de dicha documentacion, fue preparado lo que se ha denominado el INFORME DE SEGURIDAD DEL REACTOR NUCLEAR RA-0. Este documento que se describe en este trabajo, si bien contiene las habituales descripciones de todos los Informes de Seguridad, incluye otros aspectos que no siendo requeridos expresamente en el mismo, han dado una mayor coherencia a la conformacion de todos los aspectos que interrelacionan las areas de seguridad fisica, radiologica, nuclear y de control de materiales nucleares bajo salvaguardias. (Autor).

  3. Desalination plan with nuclear reactors as part of a sustainable development program in Mexico; Plan de desalinizacion con reactores nucleares como parte de un programa de desarrollo sustentable en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Rojas A, O; Calleros M, G., E-mail: oziel.rojas.siimisa@gmail.com [Soluciones en Instrumentacion Integral y Mantenimiento Industrial y Servicios, S. A. de C. V. (Mexico)

    2016-09-15

    This paper presents a project for the desalination of seawater with nuclear reactors, in order to supply fresh water to the populations near to the nuclear power plant. A case study is proposed with the nuclear power plant of Laguna Verde, implementing a system that allows taking advantage of the residual heat of the seawater condensate stage and with this, to supply drinking water to the surrounding localities where the vital liquid is scarce. In addition, legislation is proposed to allow some of the thermal energy generated by reactors producing electrical energy in Mexico to be used for the desalination of seawater and/or hydrogen production. (Author)

  4. Estudo comparativo de sistemas de iluminação artificial considerando luz natural e consumo de energia

    Directory of Open Access Journals (Sweden)

    Letícia Niero Moraes

    Full Text Available Além do aproveitamento da iluminação natural, indicado como um fator primordial na economia de energia das edificações, o posicionamento das luminárias bem como de suas especificações pode contribuir para o conforto ambiental e a conservação de energia. Essas preocupações, no entanto, não fazem parte da prática atualmente estabelecida pelos profissionais de iluminação. Considerando essa lacuna, o presente trabalho visa desenvolver um estudo que aborda a avaliação de diferentes sistemas de iluminação artificial. A metodologia da pesquisa é baseada na avaliação do desempenho luminoso, como uniformidade, níveis e distribuição de iluminâncias, e consumo de energia de sistemas de iluminação artificial, através de simulação computacional. As análises de aproveitamento da luz natural foram utilizadas para uma estimativa simplificada do consumo energético para diferentes sistemas de iluminação artificial, através da divisão de circuitos de acionamento. Os sistemas de iluminação artificial propostos eram diferenciados pelas fotometrias e disposições das luminárias. Os resultados mostram diferenças significativas quanto à distribuição da iluminação, assim como no consumo de energia, chegando a economias de até 46% em relação ao projeto-base. As principais contribuições deste estudo são a obtenção de critérios que conduzam a um melhor dimensionamento do sistema de iluminação artificial.

  5. The Role of Non-Destructive Testing in the Los Alamos Reactor Programme; Role des Essais Non Destructifs dans le Programme de Reacteurs de los Alamos; Rol' nedestruktivnykh ispytanij materialov v Los-Alamosskoj reaktornoj programme; Papel de los Metodos de Ensayo No Destructivo en el Programa de Reactores de Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Tenney, G. H. [University of California, Los Alamos Scientific Laboratory, Los Alamos, NM (United States)

    1965-10-15

    temperature UHTREX, actuellement en construction, on a etudie par microiadiogiaphie et au moyen de microscopes electroniques des grains de carbure d'uranium enrobes de carbone pyrolytique, d'un diametre de 150 {mu}m, pour evaluer la translocation de l'uranium en fonction de la temperature. On determine la quantite et l'uniformite de la charge d'uranium dans les elements au graphite d'UHTREX au moyen de compteurs a scintillation specialement concus. Environ 90% des travaux effectues a ce sujet n'ont encore fait l'objet d'aucune publication. (author) [Spanish] El Laboratorio Cientifico de Los Alamos, explotado por la Universidad de California por encargo de la Comision de Energia Atomica de los Estados Unidos, viene ocupandose desde hace mas de veinte afios del proyecto, diseno y construccion de reactores nucleares de cuatro tipos generales; a saber, de investigacion, de potencia, de propulsion espacial y para conjuntos criticos. El llamado Grupo de ensayos no destructivos colabora practicamente en todas las actividades y proyectos del laboratorio. En la presente memoria se exponen algunos de los metodos de ensayo no destructivo y sus aplicaciones, establecidos para uso en el programa de reactores. El programa LAPRE (Los Alamos Power Reactor Experiment) se basa en el empleo de una solucion de fosfato de uranio a alta temperatura. La solucion es muy corrosiva y todas las piezas que entren en contacto con ella deben ir revestidas de oro. Durante el proceso de produccion de chapa de oro laminada a partir de lingotes, se han utilizado procedimientos radiograficos especiales para inspeccionar el metal. Las juntas soldadas se examinaron del mismo modo, y ademas se establecio un metodo para comprobar la presencia de impurezas incrustadas en la superficie de la chapa de oro. El concepto fundamental en que se basa el programa LAMPRE (Los Alamos Molten Plutonium Reactor Experiment) es la utilizacion como combustible de plutonio metalico liquido en vez de solido. El combustible esta

  6. Wind power prognosis statistical system; Sistema estadistico de pronostico de la energia eoloelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Garcia, Alfredo; De la Torre Vega, Eli [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2009-07-01

    The integration of the first Aeolian farm of large scale (La Venta II) to the National Interconnected System requires taking into account the random and discontinuous nature of the Aeolian energy. An important tool, for this task, is a system for the prognosis of the Aeolian energy in the short term. For this reason, the Instituto of Investigaciones Electricas (IIE) developed a statistical model to realize this prognosis. The prediction is done through an adaptable linear combination of alternative competing models, where the weights given to each model are based on its more recent prognosis quality. Also, the application results of the prognoses system are presented and analyzed. [Spanish] La integracion de la primera grana eolica de gran escala (La Venta II) al Sistema Interconectado Nacional requiere tomar en cuenta la naturaleza aleatoria y discontinua de la energia eolica. Una importante herramienta, para esta tarea, es un sistema para el pronostico de la energia eolica a corto plazo. Por ello, el Instituto de Investigaciones Electricas (IIE) desarrollo un modelo estadistico para realizar este pronostico. La prediccion es hecha a traves de una combinacion lineal adaptable de modelos competidores alternativos, donde los pesos dados a cada modelo estan basados en su mas reciente calidad de pronostico. Tambien se presentan y analizan los resultados de la aplicacion del sistema de pronosticos.

  7. AZTLAN platform: Mexican platform for analysis and design of nuclear reactors

    International Nuclear Information System (INIS)

    Gomez T, A. M.; Puente E, F.; Del Valle G, E.; Francois L, J. L.; Martin del Campo M, C.; Espinosa P, G.

    2014-10-01

    The Aztlan platform Project is a national initiative led by the Instituto Nacional de Investigaciones Nucleares (ININ) which brings together the main public houses of higher studies in Mexico, such as: Instituto Politecnico Nacional, Universidad Nacional Autonoma de Mexico and Universidad Autonoma Metropolitana in an effort to take a significant step toward the calculation autonomy and analysis that seeks to place Mexico in the medium term in a competitive international level on software issues for analysis of nuclear reactors. This project aims to modernize, improve and integrate the neutron, thermal-hydraulic and thermo-mechanical codes, developed in Mexican institutions, within an integrated platform, developed and maintained by Mexican experts to benefit from the same institutions. This project is financed by the mixed fund SENER-CONACYT of Energy Sustain ability, and aims to strengthen substantially to research institutions, such as educational institutions contributing to the formation of highly qualified human resources in the area of analysis and design of nuclear reactors. As innovative part the project includes the creation of a user group, made up of members of the project institutions as well as the Comision Nacional de Seguridad Nuclear y Salvaguardias, Central Nucleoelectrica de Laguna Verde (CNLV), Secretaria de Energia (Mexico) and Karlsruhe Institute of Technology (Germany) among others. This user group will be responsible for using the software and provide feedback to the development equipment in order that progress meets the needs of the regulator and industry; in this case the CNLV. Finally, in order to bridge the gap between similar developments globally, they will make use of the latest super computing technology to speed up calculation times. This work intends to present to national nuclear community the project, so a description of the proposed methodology is given, as well as the goals and objectives to be pursued for the development of the

  8. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    nucleoelectrica de Humboldt Bay (Pacific Gas and Electric Company, Eureka, California), la central nucleoelectrica de Garigliano (Societa Elettronucleare Nazionale, Scauri, Italia), y el reactor de potencia japones para fines de demostracion (Instituto de Investigaciones Nucleares, Tokai Mura, Japon). La puesta en marcha y el funcionamiento inicial de estas centrales confirma las esperanzas despertadas por las centrales de Dresden, Kahl y Vallecitos. Los registros de rendimiento de las centrales de Dresden, Kahl y Vallecitos han puesto claramente de manifiesto la estabilidad y seguridad de los reactores de agua hirviente. Ademas, los niveles de radiacion dentro de la central y en sus alrededores se han mantenido muy por debajo de los limites fijados en los permisos de explotacion. Ha quedado confirmada la sencillez y facilidad de explotacion de los reactores de agua hirviente. La rapidez de la respuesta del reactor con doble ciclo de Dresden a las fluctuaciones de la demanda es excelente. Ninguno de los trabajos de conservacion y reparacion, sea cual fuere su importancia, exige calificaciones especiales ni entrana riesgos de irradiacion excesivos. La inspeccion general y la revision de la turbina de la central de Dresden puso de manifiesto la inexistencia de problemas de conservacion despues de mas de 12 000 h de funcionamiento con el vapor en ciclo directo, a pesar de que la explotacion prosiguio despues de haberse comDtobado algunas fallas en los elementos combustibles. (author) [Russian] K nastoyashchemu vremeni priobreten znachitel'nyj opyt v ehkspluatatsii ehlektrostantsij s kipyashchim reaktorom. K kontsu 1962 goda proizvedeno svyshe 2200 mln.kvt.ch ehlektroehnergii na trekh ehlektrostantsiyakh ehnergosistemy kommunal'nogo obsluzhivaniyagna Drezdenskoj atomnoj ehlektrostantsii, ''Kommonvels Ehdison kompani'', Morris, Illinojs, na atomnoj ehlektrostantsii Valleeitos,''Pasifik gaz ehnd ehlektrik kompani'', Plezanton, Kaliforniya, i na Kal'skoj atomnoj ehlektrostantsii

  9. [Usefulness of the ankle-arm index for detection of peripheral arterial disease in a working population of Junta de Andalucía at Málaga].

    Science.gov (United States)

    Alonso, Inmaculada; Valdivielso, Pedro; Josefa Zamudio, María; Sánchez Chaparro, Miguel Angel; Pérez, Francisca; Ramos, Heliodoro; González Santos, Pedro

    2009-01-17

    Detection of asymptomatic peripheral arterial disease increases the risk of vascular morbibity and mortality. We aimed to estimate the prevalence of clinical and subclinical peripheral arterial disease using the ankle-arm index (AAI) as diagnostic tool in a working population. We included 450 workers, older than 50 years old, attending voluntary regular health check-up at Centro de Prevención de Riesgos Laborales de la Junta de Andalucía in Málaga (Spain). We recorded clinical and anthopometrical data. Blood samples were taken after an overnight fast. Vascular risk was calculated using Framinghan and SCORE scales. Every participant was asked for symptoms of intermittent claudicatio and AAI was measured. AAI was considered normal within 0.9-1.3 values. Most of our workers were at low- or moderate vascular risk. Only 48 (10.6%) of individuals had an abnormal AAI: 9 (2%) showed an AAI1.3. An AAI or = 5%, and in 11% of those having a Framinghan risk > or = 20%. Intermittent claudication was present in 4 out of 9 (44%) of those having an AAI<0.9 and in 7 out of 402 (1.7%) with a normal AAI. Systematic screening of peripheral arterial disease using the AAI is not recommended in active working population over 50 years-old of age. Thus, AAI measurement is indicated only for those individuals suffering from intermitent claudicatio and those who are at moderate- or high vascular risk.

  10. Some particular aspects of control in nuclear power reactors; Quelques aspects particuliers du controle dans les piles atomiques de puissance

    Energy Technology Data Exchange (ETDEWEB)

    Furet, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Pupponi, J [Electricite de France (EDF), 75 - Paris (France)

    1964-07-01

    There are still many problems in the field of measurement and control of neutron flux. The present studies in connexion with high flux reactors contribute to the solution of these problems which concern specialists in reactor control. The present state of this investigation and the results of different studies carried out in France by the C A and the EDF are pointed out: A - In the nuclear instrumentation field, work is at present devoted to the technologies used to develop detectors and cables, which have to work at high temperature and in a high {gamma} background; fast electronic techniques are applied to fission counters to measure low neutron fluxes in a high {gamma} background (10 Rh). B - In the control and safety field, there is a real need for studies on the behaviour of reactors in the subcritical state. This increases the margin of security during restarts when poison effects must be overcome The perturbations due to control rod movements necessitate a new organisation of power level safety and control assemblies, in connexion with thermal or activation measurements. Two methods of fast start-up are described. They are related to the fission rate measurement as a function of time. This is done either continuously by a constant and high reactivity change, or step by step. The application of automatic techniques to detector motion seems to give the answer to control and safety in normal start-up. C - The scope of these studies covers the methods used for the control of E.D.F. 3, which are described. (authors) [French] La mesure et le controle du flux neutronique dans les piles de puissance posent encore de nombreux problemes. Les etudes actuellement entreprises dans le domaine des piles a haut flux, doivent apporter une contribution importante a la solution de ces problemes qui interessent les specialistes du controle des piles de puissance. On analyse l'etat actuel de ces etudes et on donne les resultats des differents travaux effectues en France, dans

  11. Concept of transfer functions for a nuclear reactor; Notion de fonction de transfert pour un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dalfes, Abdi [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires. Departement d' Electronique Generale, Service d' Electronique des Reacteurs

    1966-07-01

    The solution to the correlation equations are expressed in terms of the eigenvalues and Eigen-matrices of the transport operator, for a subcritical zero power reactor. This allows to define, for each point of the reactor and for detectors detecting neutrons of given velocities, correlation and transfer functions driven by the same white-noise source. A precise meaning is also given to the importance operator, which is the adjoin of the transport operator. (author) [French] La solution des equations regissant les matrices de correlation est exprimee en fonction des valeurs et matrices propres de l'operateur de transport pour un reacteur sous-critique et de puissance nulle. Ceci permet de definir, en chaque point du reacteur et pour des detecteurs repondant a des neutrons de vitesse definie, des fonctions de correlation et de transfert dont les entrees sont attaquees par une meme source de bruit blanc. Le role joue par l'operateur importance, adjoint de l'operateur de transport, est aussi precise. (auteur)

  12. Nuclear power plant safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The Code of Practice for the Safe Operation of Nuclear Power Plants states that: 'In discharging its responsibility for public health and safety, the government should ensure that the operational safety of a nuclear reactor is subject to surveillance by a regulatory body independent of the operating organization'. In Brazil this task is being carried out by the Comissao Nacional de Energia Nuclear in accordance with the best international practice. (orig./RW)

  13. Nuclear reactor kinetics and control

    International Nuclear Information System (INIS)

    Lewins, J.

    1978-01-01

    A consistent, integrated account of modern developments in the study of nuclear reactor kinetics and the problem of their efficient and safe control. It aims to prepare the student for advanced study and research or practical work in the field. Special features include treatments of noise theory, reliability theory and safety related studies. It covers all aspects of the operation and control of nuclear reactors, power and research and is complete in providing physical data methods of calculation and solution including questions of equipment reliability. The work uses illustrations of the main types of reactors in use in the UK, USA and Europe. Each chapter contains problems and worked examples suitable for course work and study. The subject is covered in chapters, entitled: introductory review; neutron and precursor equations; elementary solutions at low power; linear reactor process dynamics with feedback; power reactor control systems; fluctuations and reactor noise; safety and reliability; nonlinear systems (safety and control); analogue computing. (author)

  14. On elastic structural elements for nuclear reactors

    International Nuclear Information System (INIS)

    Povolo, F.

    1978-03-01

    The in-pile stress-relaxation behaviour of materials usually employed for the elastic structural elements, in nuclear reactors, is critically reviewed and the results are compared with those obtained in commercial zirconium alloys irradiated under similar conditions. Finally, it is shown that, under certain conditions, some zirconium alloys may be used as an alternative material for these structural elements. (orig.) [de

  15. Process for producing nuclear reactor fuel oxides

    International Nuclear Information System (INIS)

    Goenrich, H.; Druckenbrodt, W.G.

    1981-01-01

    The waste gases of the calcination process furnace in the AVC or AV/PuC process (manufacture of nuclear reactor fuel dioxides) are returned to the furnace in a closed circuit. The NH 3 produced replaces the hydrogen which would otherwise be required for reduction in this process. (orig.) [de

  16. Pressure vessel for nuclear reactors

    International Nuclear Information System (INIS)

    1975-01-01

    The invention applies to a pressure vessel for nuclear reactors whose shell, made of cast metal segments, has a steel liner. This liner must be constructed to withstand all operational stresses and to be easily repairable. The invention solves this problem by installing the liner at a certain distance from the inner wall of the pressure vessel shell and by filling this clearance with supporting concrete. Both the concrete and the steel liner must have a lower prestress than the pressure vessel shell. In order to avoid damage to the liner when prestressing the pressure vessel shell, special connecting elements are provided which consist of welded-on fastening elements projecting into recesses in the cast metal segments of the pressure vessel. Their design is described in detail. (TK) [de

  17. Influência da energia de soldagem em uniões de lâminas finas através de laser pulsado de Nd:YAG Effect of the heat input on pulsed Nd:YAG laser welding of thin foil

    Directory of Open Access Journals (Sweden)

    Vicente A. Ventrella

    2010-12-01

    Full Text Available A soldagem laser vem sendo utilizada como um importante processo de manufatura. Ela pode ser utilizada tanto no modo contínuo quanto no modo pulsado. No processo onde se utiliza laser pulsado é possível realizar soldas de costura em lâminas finas, através da sobreposição dos pulsos. Nesse caso a velocidade de soldagem é definida pela taxa de sobreposição, taxa de repetição e diâmetro do pulso. A soldagem de sobreposição de lâminas finas apresenta problemas típicos como distorção excessiva da junta soldada, falta de contato entre as lâminas a serem soldadas (presença de um gap de ar, perfuração da junta e presença de altos níveis de tensões residuais. O processo de laser pulsado é preferido em relação ao processo por laser contínuo, pois ele possibilita um melhor controle da energia de soldagem. O presente trabalho estudou a influência da energia do pulso, no caso processo de soldagem laser Nd:YAG, na soldagem de lâminas finas ( 100µm de aço inoxidável austenítico AISI 316L, utilizado no revestimento de sensores (que trabalham em ambiente corrosivo da indústria sucroalcooleira. Utilizou-se energia de pulso de 1,0 a 2,25 Joules, com incremento de 0,25 Joules e largura temporal de 4 ms. As soldas foram realizadas com proteção gasosa de argônio. Foram realizadas análises macrográficas das juntas soldadas, através de secções transversais das mesmas e, ensaios de microdureza Vickers e ensaios de tração. Os resultados obtidos mostraram que o controle da energia do pulso, em processo de soldagem por laser de lâminas finas é de fundamental importância para a geração de juntas soldadas com boas propriedades mecânicas e livres de descontinuidades. O limite de resistência da junta soldada aumentou no início e depois sofreu um pequeno decréscimo em função do aumento da energia do pulso. O processo mostrou-se muito sensível à presença de gap entre as lâminas.Laser beam welding has been used widely

  18. Individual performance evaluation of the Brazilian Nuclear Energy Commission (CNEN): a meta-evaluative study; Avaliação de desempenho individual da Comissão Nacional de Energia Nuclear: um estudo meta-avaliativo

    Energy Technology Data Exchange (ETDEWEB)

    Bezerra, Leonardo Ferreira

    2017-07-01

    The present study is a summative meta-evaluation that had as objective to evaluate the quality of the process of evaluation of individual performance of the servers of the National Commission of Nuclear Energy, being guided by the scientific curiosity to know to what extent the evaluation of performance the National Commission for Nuclear Energy meets the quality standards disseminated by the Joint Committee on Standards for Educational Evaluation. The methodology chosen to be used was based on the management approach and had as a guiding principle of the study the elaboration of a framework of criteria considering the aforementioned standards. The criteria established in the criteria framework guided the preparation of the items of the questionnaire sent to the National Commission of Nuclear Energy servers. In addition to the questionnaire, the observation of this author was considered in the context where the phenomenon occurred, which allowed a better reflective analysis of the data collected by the questionnaire. Regarding the results, it can be inferred that the performance evaluation developed at the National Commission of Nuclear Energy can be considered of quality, highlighting the servers' trust for the data, the communication process of the program stages, the credibility of the evaluators, the process of negotiation of goals and adaptability of the instrument over the course of the cycle. However, there are some opportunities for improvement, considering the relevance of evaluation as a tool to improve the performance of the autarchy's servers. Among the points that need to be improved is that there is currently a lack of knowledge about the legal basis and justification of the process of evaluation process by the servers and the lack of clarity regarding the content of the final evaluation report. Among the recommendations of this study, one can consider as the most relevant the need to: disseminate the results of this meta-evaluation to the

  19. Nuclear reactor control rod

    International Nuclear Information System (INIS)

    Cearley, J.E.; Izzo, K.R.

    1987-01-01

    This patent describes a vertically oriented bottom entry control rod from a nuclear reactor: a frame including an elongated central spine of cruciform cross section connected between an upper support member and a lower support member both of cruciform shape having four laterally extending arms. The arms are in alignment with the arms of the lower support member and each aligned upper and lower support members has a sheath extending between; absorber plates of neutron absorber material, different from the material of the frame, one of the absorber plates is positioned within a sheath beneath each of the arms; attachment means suspends the absorber plates from the arms of the upper support member within a sheath; elongated absorber members positioned within a sheath between each of the suspended absorber plates and an arm of the lower support member; and joint means between the upper ends of the absorber members and the lower ends of the suspended absorber plates for minimizing gaps; the sheath means encloses the suspended absorber plates and the absorber members extending between aligned arms of the upper and lower support members and secured

  20. Nuclear reactor container

    International Nuclear Information System (INIS)

    Fukui, Tooru; Murase, Michio; Kataoka, Yoshiyuki; Hidaka, Masataka; Sumita, Isao; Tominaga, Kenji.

    1992-01-01

    In a nuclear reactor container, a chamber in communication with a wet well of a pressure suppression chamber is disposed and situated to such a position that the temperature is lower than a chamber containing pool water upon occurrence of loss of coolant accident. In addition, the inner surface of the pressure suppression chamber is constituted with steel walls in contact with pool water, and an outer circumferential pool is disposed at the outer circumferential surface thereof. Further, a circulation channel is disposed, and a water intake port is disposed at a position higher than an exit to the pool water, and a water discharge port is opened in the pool water at a position lower than the exit to the pool water. With such a constitution, the allowable temperature of the pressure suppression pool water can be elevated to a saturated steam temperature corresponding to the resistant pressure of the container, so that the temperature difference between the pressure suppression pool and the outer side thereof is increased by so much, to improve thermal radiation performance. Accordingly, it can be utilized as a pressure suppression means for a plant of greater power. Further, thermal conduction efficiency from the pool water region of the pressure suppression chamber to the outer circumferential pool water is improved, or thermal radiation area is enlarged due to the circulation channel, to improve the heat radiation performance. (N.H.)

  1. Safety device for nuclear reactor

    International Nuclear Information System (INIS)

    Jacquelin, Roland.

    1977-01-01

    This invention relates to a safety device for a nuclear reactor, particularly a liquid metal (generally sodium) cooled fast reactor. This safety device includes an absorbing element with a support head connected by a disconnectable connector formed by the armature of an electromagnet at the end of an axially mobile vertical control rod. This connection is so designed that in the event of it becoming disconnected, the absorbing element gravity slides in a passage through the reactor core into an open container [fr

  2. Nuclear reactor vessel inspection apparatus

    International Nuclear Information System (INIS)

    Blackstone, E.G.; Lofy, R.A.; Williams, L.P.

    1979-01-01

    Apparatus for the in situ inspection of a nuclear reactor vessel to detect the location and character of flaws in the walls of the vessel, in the welds joining the various sections of the vessel, in the welds joining attachments such as nozzles, elbows and the like to the reactor vessel and in such attachments wherein an inspection head carrying one or more ultrasonic transducers follows predetermined paths in scanning the various reactor sections, welds and attachments

  3. Control rod drive of nuclear reactor

    International Nuclear Information System (INIS)

    Zhuchkov, I.I.; Gorjunov, V.S.; Zaitsev, B.I.

    1980-01-01

    This invention relates to nuclear reactors and, more particularly, to a drive of a control rod of a nuclear reactor and allows power control, excess reactivity compensation, and emergency shut-down of a reactor. (author)

  4. Nuclear reactor in deep water

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    Events during October 1980, when the Indian Point 2 nuclear reactor was flooded by almost 500 000 litres of water from the Hudson river, are traced and the jumble of human errors and equipment failures chronicled. Possible damage which could result from the reactor getting wet and from thermal shock are considered. (U.K.)

  5. Transmutation of nuclear waste in nuclear reactors

    International Nuclear Information System (INIS)

    Abrahams, K.; Kloosterman, J.L.; Pilate, S.; Wehmann, U.K.

    1996-03-01

    The objective of this joint study of ECN, Belgonucleaire, and Siemens is to investigate possibilities for transmutation of nuclear waste in regular nuclear reactors or in special transmutation devices. Studies of possibilities included the limits and technological development steps which would be needed. Burning plutonium in fast reactors, gas-cooled high-temperature reactors and light water reactors (LWR) have been considered. For minor actinides the transmutation rate mainly depends on the content of the minor actinides in the reactor and to a much less degree on the fact whether one uses a homogeneous system (with the actinides mixed into the fuel) or a heterogeneous system. If one wishes to stabilise the amount of actinides from the present LWRs, about 20% of all nuclear power would have to be generated in special burner reactors. It turned out that reactor transmutation of fission products would require considerable recycling efforts and that the time needed for a substantial transmutation would be rather long for the presently available levels of the neutron flux. If one would like to design burner systems which can serve more light water reactors, a large effort would be needed and other burners (possibly driven by accelerators) should be considered. (orig.)

  6. Sexualidad juvenil y cambio social: el caso de Portugal

    Directory of Open Access Journals (Sweden)

    Machado-Pais José

    2003-01-01

    Full Text Available OBJETIVO: Investigar si, dentro de un marco de profundos cambios sociales, las nuevas generaciones estarán creando nuevos valores sociales. MATERIAL Y MÉTODOS: Aplicando el método de las generaciones, se utilizaron datos de una encuesta sobre valores y generaciones, hecho en 1996 a 2 012 individuos residentes en Portugal continental y representativos de la población portuguesa. Recurriendo al programa SPAD (Estadística para análisis de datos, se procedió a un análisis factorial de correspondencias múltiples en conjugación con un análisis de tipo cluster. RESULTADOS: Constatamos que las principales discontinuidades intergeneracionales se presentan en el área de las actitudes y prácticas sexuales. Comprobamos que los grupos y agregados resultantes del análisis tienen índices de sobrerrepresentación de generaciones específicas. Por ejemplo, los encuestados hedonistas se caracterizan por un elevado índice de sobrerrepresentación de jóvenes, en contraste con los inhibidos o los moralistas. CONCLUSIONES: Los jóvenes portugueses aparecen como una generación portadora de valores hedonistas y de carácter experimental en el plano de la vida sexual y amorosa. Sin embargo, se caracterizan al mismo tiempo por su vulnerabilidad a conductas de riesgo.

  7. Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant; Estimacion de requerimientos de energia eolica equivalente a la generacion electrica de la Central Nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A.; Hernandez M, I.A. [Facultad de Ingenieria, Division de Ingenieria Electrica, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: maiki27@yahoo.com; Martin del Campo M, C. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2004-07-01

    The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

  8. Energy balance of the metropolitan zone of the valley of Mexico, methodology and the entailment energy-air quality; Balance de energia de la zona metropolitana del valle de Mexico metodologia y la vinculacion energia - calidad del aire

    Energy Technology Data Exchange (ETDEWEB)

    Bazan Navarrete, Gerardo [Universidad Nacional Autonoma de Mexico, Mexico, D.F. (Mexico)

    2001-07-01

    The present document raises a methodology for the elaboration of the Energy Balance of the Metropolitan Zone of the Valley of Mexico (ZMVM), in order to unify criteria and to facilitate the work of entities and investigators, mainly of those that require the entailment of energy and environment. The applied methodology, the consolidated format and the caloric unity facilitates the insertion of the Energy Balance of the ZMVM within the National Balance of Energy. The regional balances of energy have the intention of knowing the energy consumption patterns in the ZMVM and the indexes of energy intensity by sector. They establish the relationship of the indexes of energy intensity with the local and global air quality of the region, performing studies of incidence with the main polluting agents and with the greenhouse effect gases. [Spanish] El presente documento plantea una metodologia para la elaboracion del Balance de Energia de la Zona Metropolitana del Valle de Mexico (ZMVM), con el proposito de unificar criterios y facilitar el trabajo de organismos e investigadores, sobre todo de aquellos que requieren vincular energia y medio ambiente. La metodologia aplicad, el formato consolidado y la unidad calorica facilitan la insercion del Balance de Energia de la ZMVM dentro del Balance Nacional de Energia. Los balances regionales de energia tienen el proposito de conocer los patrones de consumo de energia en la ZMVM y los indices de intensidad energetica por sector. Establecen la relacion de los indices de intensidad energetica con la calidad del aire local y global de la region, realizando estudios de incidencia con los principales contaminantes y con los gases de efecto invernadero.

  9. Nuclear reactors: physics and materials

    Energy Technology Data Exchange (ETDEWEB)

    Yadigaroglu, G

    2005-07-01

    In the form of a tutorial addressed to non-specialists, the article provides an introduction to nuclear reactor technology and more specifically to Light Water Reactors (LWR); it also shows where materials and chemistry problems are encountered in reactor technology. The basics of reactor physics are reviewed, as well as the various strategies in reactor design and the corresponding choices of materials (fuel, coolant, structural materials, etc.). A brief description of the various types of commercial power reactors follows. The design of LWRs is discussed in greater detail; the properties of light water as coolant and moderator are put in perspective. The physicochemical and metallurgical properties of the materials impose thermal limits that determine the performance and the maximum power a reactor can deliver. (author)

  10. Carbon Bonds and the saving of energy; Bonos de carbono y el ahorro de energia

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez Ramirez, Alejandro [NovaEnergia (Mexico)

    2005-07-01

    This document deals with the development of the carbon bond project, the energy saving and the entry into force of the Kyoto Protocol at a world-wide level. In this project Mexico opts for a development model in which the economic growth brakes ties with the discharge of greenhouse effect gases and in which the progress does not mean more damages to our planet. [Spanish] Este documento trata sobre el desarrollo del proyecto de bonos de carbono, ahorro de energia y la entrada en vigor del Protocolo de Kyoto a nivel mundial, en el cual Mexico opta por un modelo de desarrollo en el que el crecimiento economico esta desvinculado de la emision de gases de efecto invernadero y en donde el progreso no signifique mas danos a nuestro planeta.

  11. Prestressed reactor vessel for nuclear power plants

    International Nuclear Information System (INIS)

    Schoening, J.; Schwiers, H.G.

    1982-01-01

    With usual pressure vessels for nuclear reactor plants, especially for gas-cooled nuclear reactors, the load occurring due to the inner overpressure, especially the tensile load affecting the vessel top and/or bottom, their axis of inertia being horizontal, shall be compensated without a supplementary modification in design of the top and/or the bottom. This is attained by choosing an appropriate prestressing system of the vessel wall in the field the top and/or the bottom, so that the top and/or the bottom form a tension vault directed towards the interior of the vessel. (orig.) [de

  12. Nuclear Reactor Engineering Analysis Laboratory

    International Nuclear Information System (INIS)

    Carlos Chavez-Mercado; Jaime B. Morales-Sandoval; Benjamin E. Zayas-Perez

    1998-01-01

    The Nuclear Reactor Engineering Analysis Laboratory (NREAL) is a sophisticated computer system with state-of-the-art analytical tools and technology for analysis of light water reactors. Multiple application software tools can be activated to carry out different analyses and studies such as nuclear fuel reload evaluation, safety operation margin measurement, transient and severe accident analysis, nuclear reactor instability, operator training, normal and emergency procedures optimization, and human factors engineering studies. An advanced graphic interface, driven through touch-sensitive screens, provides the means to interact with specialized software and nuclear codes. The interface allows the visualization and control of all observable variables in a nuclear power plant (NPP), as well as a selected set of nonobservable or not directly controllable variables from conventional control panels

  13. O franchising como paradigma de crescimento das PME em Portugal

    OpenAIRE

    Carvalhosa, José Manuel Pinto

    2011-01-01

    Mestrado em Controlo e Gestão dos Negócios O tecido empresarial português assenta maioritariamente em organizações com características que se enquadram na categoria denominada de pequenas e médias empresas. Consequentemente gozam de enorme relevância e influência na economia nacional. O franchising teve origem nos Estados Unidos da América e começou a dar os primeiros passos no início do século passado. A introdução em Portugal deste conceito foi mais recente, final da dé...

  14. Radioactive nuclides in nuclear reactors

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1982-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around nuclear reactors. The curricula of the courses contain also chemical subject materials. With reference to the foreign curricula, a plan of educational subject material of chemistry was considered for students of the school in the previous report (JAERI-M 9827), where the first part of the plan, ''Fundamentals of Reactor Chemistry'', was reviewed. This report is a review of the second part of the plan containing fission products chemistry, actinoids elements chemistry and activated reactor materials chemistry. (author)

  15. Random processes in nuclear reactors

    CERN Document Server

    Williams, M M R

    1974-01-01

    Random Processes in Nuclear Reactors describes the problems that a nuclear engineer may meet which involve random fluctuations and sets out in detail how they may be interpreted in terms of various models of the reactor system. Chapters set out to discuss topics on the origins of random processes and sources; the general technique to zero-power problems and bring out the basic effect of fission, and fluctuations in the lifetime of neutrons, on the measured response; the interpretation of power reactor noise; and associated problems connected with mechanical, hydraulic and thermal noise sources

  16. Criminalidade de estrangeiros julgada em Portugal

    OpenAIRE

    Seabra, Hugo Martinez de

    2004-01-01

    As instituições têm desempenhado desde sempre um papel importante na análise económica, opondo-se por vezes à teoria económica neoclássica e ao conceito do homo economicus. Actualmente considera-se que as instituições são um factor de grande importância para o desempenho das economias, em particular nos processos de crescimento e de desenvolvimento económico, a tal ponto que o Relatório sobre o Desenvolvimento Mundial de 2002 do Banco Mundial se intitula “Buiding Institutions for Markets”. No...

  17. Flexibilidade e mercado de trabalho em Portugal

    OpenAIRE

    Centeno, Mário; Novo, Álvaro

    2008-01-01

    A era de rápida evolução tecnológica em que vivemos, associada em particular ao desenvolvimento de tecnologias de informação, coloca às economias novos desafios, mas também novas oportunidades, abrindo à concorrência mercados anteriormente fechados. Neste ambiente mais competitivo, não é estranho que o apelo a uma maior flexibilidade do emprego tenha ganho proeminência na discussão político-económica da organização do mercado de trabalho.

  18. Nuclear data for nuclear reactor analyses

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1984-01-01

    A discussion of nuclear data is presented emphasizing to what extent data are known and to what accuracy. The principal data of interest is that for neutron cross-sections. The changing status of data, evaluated nuclear data files and data validation and improvement are described. Although the discussion relates to nuclear data for reactor analysis may of the results also apply to fusion, accelerator, shielding, biomedical, space and defense studies. (U.K.)

  19. Efeito do Tratamento Térmico de Solubilização e Estabilização Convencional e Alternativo na Microestrutura de uma Junta Soldada com Aço Inox 347

    Directory of Open Access Journals (Sweden)

    Renata Barbosa Gonçalves

    2015-03-01

    Full Text Available Este trabalho estuda a microestrutura formada na zona termicamente afetada (ZTA e na zona fundida (ZF de uma junta soldada pelo processo TIG automático no passe de raiz, processo plasma nos passes de enchimento e soldagem SAW para os passes de acabamento em junta de topo com chanfro “V” simples, usando o aço inoxidável austenítico AISI 347. Foram estudadas as condições: como soldada; após tratamento térmico convencional de solubilização a 1060 °C e estabilização a 900 °C; e após tratamento térmico alternativo, onde a peça foi solubilizada a 1060 °C e mantida no forno que foi resfriado até 900 °C para a estabilização. Os resultados mostram que, na condição como soldado houve crescimento de grão na ZTA e a ZF apresentou 13% de ferrita com diferentes morfologias, tendo sido observada a precipitação de carbetos de Cr e de Nb. Após o tratamento térmico convencional de solubilização e estabilização, foi observada uma diminuição significativa do teor de ferrita na ZTA e na ZF, tendo sido observados carbetos de Nb e Cr, distribuídos de forma mais dispersa e com tamanhos menores, que contribuem para minimizar a possibilidade de ocorrer o fenômeno da sensitização. Após tratamento térmico alternativo de solubilização e estabilização, a microestrutura da ZTA e ZF foi similar à obtida no tratamento convencional, sendo que o teor de ferrita δ na ZF foi ainda mais reduzido, de 4,5%. Foi concluído que o tratamento térmico alternativo de solubilização e estabilização foi tão eficaz quanto o tratamento térmico convencional para a adequação da microestrutura da junta soldada, com uma significativa vantagem do tratamento térmico proposto em reduzir o tempo e o custo desta operação.

  20. The future of nuclear reactors

    International Nuclear Information System (INIS)

    Teller, E.

    1989-01-01

    The Atomic Energy Commission Advisory Committee on Reactor Safeguards began work in early 1948 with the firm and unanimous conviction that nuclear power could not survive a significant damaging accident. They as a committee felt that their job was to make reactors so safe that no such event would ever occur. However, ambitious reactor planners did not like all the buts and cautions that the committee was raising. They seemed to delay unduly their setting sail into the brave new world of clean, cheap, safe nuclear energy. The committee was soon nicknamed the Committee on Reactor Prevention. Reactors, of course, represented a tremendous step into the future. To an unprecedented extent, they were based on theory. But the committee did not have the luxury of putting a preliminary model into operation and waiting for difficulties to show up. In assessing new designs and developments, they had to anticipate future difficulties. Their proposals in good part were accepted, but their deep emphasis on safety did not become a part of the program. Today, forty years later, the author still believes both in the need for nuclear reactors and in the need of a thorough-going, pervasive emphasis on their safety. Real, understandable safety can be achieved, and that achievement is the key to our nuclear future. The details he gives are only examples. The need for reactors that are not only safe but obviously safe can be ignored only at our peril