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Sample records for nuclear para protecao

  1. Nuclear energy for environmental protection; A energia nuclear para protecao do meio ambiente

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Jair Albo Marques de

    1993-12-31

    In 1990 nuclear energy supplied about 17% of the total electric power produced in the world, what makes it the third most used power source after coal and hydropower. In this paper the advantages of using nuclear power for generating large quantities of electric power are presented 18 figs., 23 tabs.

  2. Nuclear energy for environmental protection; A energia nuclear para protecao do meio ambiente

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Jair Albo Marques de

    1992-12-31

    In 1990 nuclear energy supplied about 17% of the total electric power produced in the world, what makes it the third most used power source after coal and hydropower. In this paper the advantages of using nuclear power for generating large quantities of electric power are presented 18 figs., 23 tabs.

  3. Ionizing radiation, nuclear energy and radiation protection for school; Radiacao ionizante, energia nuclear e protecao radiologica para a escola

    Energy Technology Data Exchange (ETDEWEB)

    Lucena, E.A.; Reis, R.G.; Pinho, A.S.; Alves, A.S.; Rio, M.A.P.; Reis, A.A., E-mail: arlene@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Silva, J.W.S. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Paula, G.A. de; Goncalves Junior, M.A. [Escola Sesc de Ensino Medio, Rio de Janeiro, RJ (Brazil)

    2017-04-01

    Since the discovery of X-rays in 1895, ionizing radiation has been applied in many sectors of society, such as medicine, industry, safety, construction, engineering and research. However, population is unaware of both the applications of ionizing radiation and their risks and benefits. It can be seen that most people associate the terms 'radiation' and 'nuclear energy' with the atomic bomb or cancer, most likely because of warlike applications and the stealthy way radioactivity had been treated in the past. Thus, it is necessary to clarify the population about the main aspects related to the applications, risks and associated benefits. These knowledge can be disseminated in schools. Brazilian legislation for basic education provides for topics such as nuclear energy and radioactivity to high school students. However, some factors hamper such an educational practice, namely, few hours of class, textbooks do not address the subject, previous concepts obtained in the media, difficulty in dealing with the subject in the classroom, phobia, etc. One solution would be the approximation between schools and institutions that employ technologies involving radioactivity, which would allow students to know the practices, associated radiological protection, as well as the risks and benefits to society. Currently, with the increasing application of ionizing radiation, especially in medicine, it is necessary to demystify the use of radioactivity. (author)

  4. Fundaments for creation of national radiation protection standard for nuclear gauges; Fundamentos para implantacao de norma nacional de protecao radiologica para medidores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Luiz Cavalcante

    2016-11-01

    The present work It aims to provide fundaments for the creation of a national standard of practice, safety and responsible use of nuclear gauges in accordance with the recommendations already existing national and international. The work deals with the protection against ionizing radiation, an outline of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of safety and security, and some pointes that are also relevant such as the responsibilities of those involved in acquisition and nuclear gauge operation, storage, maintenance, testing and emergency situations. The result is to provide a means to limit the dose of operators and people from the public and maintain these limits within the recommended by CNEN, reducing exposure do ionizing radiation, and having greater control in operating the equipment. (author)

  5. The protection system to Brazilian Nuclear Program; O sistema de protecao ao Programa Nuclear Brasileiro

    Energy Technology Data Exchange (ETDEWEB)

    Andreuzza, Mario Giussepp Santezzi Bertottelli [Secretaria de Assuntos Estrategicos (SAE), Brasilia, DF (Brazil)

    1997-12-31

    The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author) 3 refs., 3 figs.

  6. A study of digital hardware architectures for nuclear reactors protection systems applications - reliability and safety analysis methods; Um estudo de arquiteturas de hardware para aplicacao em sistemas digitais de protecao de reatores nucleares - metodos de analise de confiabilidade e seguranca

    Energy Technology Data Exchange (ETDEWEB)

    Benko, Pedro Luiz

    1997-07-01

    A study of digital hardware architectures, including experience in many countries, topologies and solutions to interface circuits for protection systems of nuclear reactors is presented. Methods for developing digital systems architectures based on fault tolerant and safety requirements is proposed. Directives for assessing such conditions are suggested. Techniques and the most common tools employed in reliability, safety evaluation and modeling of hardware architectures is also presented. Markov chain modeling is used to evaluate the reliability of redundant architectures. In order to estimate software quality, several mechanisms to be used in design, specification, and validation and verification (V and V) procedures are suggested. A digital protection system architecture has been analyzed as a case study. (author)

  7. Development of a protection system for research reactor based in Field Programmable Gate Array - FPGA; Desenvolvimento de sistema de protecao para reator nuclear de pesquisa baseado em Field Programmable Gate Array - FPGA

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Roque Hudson da Silva

    2016-07-01

    This study presents a implementation purpose of a protection system for research nuclear reactors by using a programed device FPGA (Field Programmable Gate Array). As well as logic protection method involved on an automatic shutdown (TRIP) of a reactor, that ensure the security on such systems. These new control and operation mechanics are developed to guarantee that the security limits of a power plant are not exceeded, these mechanics can work isolated or in groups to safe guard the security levels. For this implementation to be completed, there will be presented the main aspects and concepts referred to protection systems, mostly about research nuclear reactors, with some applications terms exposed. The system proposed at this paper was developed following the VHDL (Very High Speed Integrated Circuits) hardware describing language, and the Modelsim software from Altera Software to program the automatic turning off routines, and hypothetical simulations for such. The results show that for every software application for supporting nuclear reactors, like security devices, they have to meet the IEC 60880 criteria. This paper have great importance, seeing that nuclear reactor security systems, are a basic element for ensure the reactor security. (author)

  8. Evaluation of protection measurements for rural environments; Avaliacao de medidas de protecao para ambientes rurais

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo N.G.; Silva, Fernanda L.; Conti, Luiz F., E-mail: dneves@ird.gov.b, E-mail: lfcconti@ird.gov.b, E-mail: fleite@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Wasserman, Maria Angelica V., E-mail: maria.wasserman@pq.cnpq.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Rochedo, Elaine R.R., E-mail: erochedo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CODIN/CNEN), Rio de Janeiro, RJ (Brazil). Coord. de Instalacoes Nucleares

    2011-10-26

    Among the planning activities of actuation in nuclear/radiological emergences, it is included the efficiency evaluation of protection and remediation measurements. From the development of a data base on such measurements for the agricultural areas, the program SIEM was used for effectuation the simulations involving the {sup 137}Cs, {sup 131}I and {sup 90}Sr radionuclides, in scenery previously established for simulation those areas of a 50 km surrounding the Admiral Alvaro Alberto nuclear power plant. The obtained results indicate that the scenery is determinant of efficiency measurements involving various specific factors of each place, such as: agricultural and cattle breeding products, consumption habits of population and the grade of subsistence by the diet items, making not practical the elaboration of predefined generic sceneries. The great dependence on seasoning related to the moment of accident makes inadequate any previous evaluation what soever for evaluation of efficiency of protection and remediation measurements. Therefore, previous decisions are not recommended about the relevance of protection measurements for rural areas. Two classification criteria were defined: (i) the efficiency in reduction the doses in the firs year; and, (i i) efficiency in reduction the dose at long term

  9. Study of application of protective measures for the public and remediation of contaminated areas in case of nuclear and / or radiological accidents in Brazil; Estudo da aplicacao de medidas de protecao para o publico e de remediacao de areas contaminadas em caso de acidentes nucleares e/ou radiologicos no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2011-07-01

    Since the radiological accident in Goiania in 1987, the IRD (Institute of Radiological Protection and Dosimetry - IRD / CNEN) has been developing tools to support decision-making processes after a nuclear or radiological accident which leads to an environmental contamination and to an exposure of individuals the public These processes include the establishment of a supporting multicriteria model, which involves the application of protective and remediation measures of contaminated areas in tropical environments. In this study, it was performed an evaluation of the efficiency of these measures in order to determine the consequences of their implementation, based on results obtained from the code SIEM (Emergency Integrated System), which constitutes an environmental mode1 developed at IRD to simulate this type of accident. In order to perform this evaluation, it was first developed a database containing descriptions of various protection/remediation measures, which could be applied nationwide. Afterwards, some basic scenarios were established, considering the environmental, housing and food characteristics of the population of the vicinity of the nuclear power plants in Angra dos Reis (state of Rio de Janeiro). Thus, the accident simulations were carried out separately containing releases of {sup 137}Cs, {sup 90}Sr and 131 I. The results showed that the dose reduction varies according to the extent and the timing of the remediation measure applied. Although it is possible to establish some basic guidelines, generic solutions are not recommended, since the resulting doses are highly dependent on the actual situation. Any decision-making process should be made case by case, according to the actual conditions of the affected area and to the occupation characteristics and use of the affected areas, considering the characteristics of the source term of contamination, the time of the year in which the accident occurs, the local agricultural practices and food habits of

  10. Radiological respiratory protection in Angra-1 Nuclear Power Plant; Protecao respiratoria radiologica na Usina Nuclear de Angra

    Energy Technology Data Exchange (ETDEWEB)

    Amaral, Marcos A. do [Furnas Centrais Eletricas S.A., Angra dos Reis, RJ (Brazil). Central Nuclear de Angra I. Div. de Protecao Radiologica e Ambiental

    1996-07-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  11. Radiation protection optimization in practices for radiopharmaceuticals production at IEN; Otimizacao da protecao radiologica nas praticas para a producao de radiofarmaco no IEN

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Osvaldir Paulo dos

    2004-06-15

    This works has arisen from the need of updating radiological protection procedures, creating new ones and training qualified personnel to perform radiological protection duties in a nuclear facility. The main purpose of the research was to assess and minimize gamma and neutron dose rates emitted during the production and handling of radiopharmaceuticals at IEN/DIRA. A mobile measurements system (SMMG-N) was developed for on-site measurements. This system has proven to be more handy than the equipment formerly used for for this task. It has also proven to reduce the measurements uncertainties and to allow for the standardization of assessment procedures. He dose rates calculated using the data provided by this system have been compared with results obtained otherwise and good agreement was observed between them. This study has confirmed the need to improve the radiation shielding of KIPROS target-chamber and target vault in order to meet the radiological principles of dose rate limitation and optimization. (author)

  12. Guidelines for the development and environmental protection of the outcrop area in the Guarani aquifer system in Sao Paulo State, Brazil; Diretrizes para o desenvolvimento e protecao ambiental da area de afloramento do Sistema Aquifero Guarani no estado de Sao Paulo, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Alburquerque Filho, J. L.; Carvalho, A. M. de; Ikematsu, P.; Costa Barbosa, M.; Iritani, M.; Nogueira Pressinoti, M. M.; Rocha, G.; Pereira Militao da Silva, M.; Theodorovicz, A.

    2012-11-01

    The Guarani aquifer system (GAS) is an important public water source. The unconfined areas are those where the aquifer is more vulnerable to contamination, justifying the creation of a Protection and Recovery Source Area (Area de Protecao e Recuperacao de Manancial - APRM), as established in Act 9.866/97 of Sao Paulo State. We present here the results of the project Environmental Diagnosis in Support of the Plan for the Development and Environmental Protection Plan of the Outcrop Area of the Guarani Aquifer System in Sao Paulo State (Plano de Desenvolvimento e Protecao Ambiental da Area de Afloramento do Sistema Aquifero Guarani no Estado de Sao Paulo PDPA-SAG) and describe the areas of intervention defined by this law. The characterization of the area studied focuses on the physical and socio-economic aspects of the region, in addition to the pertinent legislation. Partial results indicate that the condition of the aquifer is satisfactory, but territorial discipline continues to be of prime importance. (Author)

  13. Fire protection system management in nuclear facilities: strengthening factor of integrated management system - a case study; Gestao de sistema de protecao contra incendio em instalacoes nucleares: fator de fortalecimento do sistema de gestao integrada - um estudo de caso

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joao Regis dos

    2005-07-01

    The present study investigated and analyzed the importance of a system of integrated safety manage, environment and health in a nuclear installation, having as perspective, the fire protection manage. The inquiry was made using a qualitative research involving a case study, where the considered environment was the Reconversion and UO{sub 2} Plant of the Industrias Nucleares do Brasil (INB), located in Resende, Rio de Janeiro and the studied population, the managers and the staff directly involved with the aspects related to the safety of the industrial complex of the related company. The motivation for the research was the search of a bigger interaction of the questions related to the safety, environment and health in the nuclear industry having, as axle of the investigation, the fire protection. As a result, it was observed that in a nuclear installation, although dealing with diversified safety processes, integration is possible and necessary, since there are more reasons for integration than otherwise. (author)

  14. A contribuicao do direito nuclear para o melhor aproveitamento da energia nuclear para fins pacifico

    International Nuclear Information System (INIS)

    Puig, D.E.

    1983-01-01

    The text describes the contribution of nuclear law in order to improve the nuclear energy utiliation for peaceful uses. The actuation of the nuclear law as mediator between the nuclear progress and its consequences aiming to get better life conditions and education as base for developing are shown [pt

  15. Radiopharmaceuticals for nuclear cardiology; Radiofarmacos para cardiologica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Leon Cabana, Alba [Universidad de la Republica, Facultad de Quimica (Uruguay)

    1994-12-31

    One of the diagnostic technique periodically used in Nuclear Medicine is the angiographic studi e, employee for detect cardiovascular diseases. The radiopharmaceutical more used in the angiographic ones is 99mTc. Between thetopics described in the present work it find: myocardial infarction, radiopharmaceuticals classification for cardiac studies, labelled proceedings, cardiovascular diseases.

  16. Nuclear Science Curriculum and Curriculum para la Ciencia Nuclear.

    Science.gov (United States)

    American Nuclear Society, La Grange Park, IL.

    This document presents a course in the science of nuclear energy, units of which may be included in high school physics, chemistry, and biology classes. It is intended for the use of teachers whose students have already completed algebra and chemistry or physics. Included in this paper are the objectives of this course, a course outline, a…

  17. Desarrollo de proveedores para la industria nuclear argentina Visión desde las Centrales Nucleares

    Directory of Open Access Journals (Sweden)

    DOMINGO QUILICI

    2013-06-01

    Full Text Available Frente al inicio de una nueva etapa en la instalación de capacidad núcleo eléctrica en el país, se recorrerá la historia del desarrollo de la industria nuclear nacional (1964-1986 en búsqueda de antecedentes útiles para esta nueva realidad. Partiendo de la intención de dar repuesta a las preguntas: ¿Por qué se decidió tan tempranamente construir una central nuclear (en adelante CN; ¿por qué se decidió comprarla con una modalidad particular de los contratos “llave en mano”, en vez del desarrollo de una versión “criolla”? Y cuál fue el significado de la apertura del “paquete tecnológico” en aquel momento; se indagará sobre los antecedentes del desarrollo de proveedores para la industria nuclear en la Argentina. Se describirán las acciones que llevaron a la compra de las centrales de Atucha I, Embalse y Atucha II y como a partir de esas decisiones se implementaron políticas para maximizar la participación nacional en la construcción de las mismas y para la transferencia de tecnología del exterior hacia la industria local. Se analizará el Plan Nuclear puesto en vigencia a fines de los años setenta, desde el punto de vista de su influencia sobre el desarrollo tecnológico endógeno. Abstract The history of the development of national nuclear industry (1964-1986 will be reviewed in the search of useful patterns for the present new phase in the installation of nucleo-electric capacity in the country Precedents of development of suppliers for the argentinean nuclear industry will be considered, taking as starting point the following questions: Why the early decision of constructing a Nuclear Power Plant was taken? Why was it decided to buy it under a peculiar version of a turnkey contract instead of developing a “native” design? What were the implications of opening “technological packages” at that time? Actions leading to the construction of Atucha I, Embalse and Atucha II stations will be described, as well

  18. Evaluation of protection measurements for urban environments; Avaliacao de medidas de protecao para ambientes urbanos

    Energy Technology Data Exchange (ETDEWEB)

    Rochedo, Elaine R.R., E-mail: erochedo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CODIN/CNEN), Rio de Janeiro, RJ (Brazil). Coord. de Instalacoes Nucleares; Silva, Diogo N.G.; Nascimento, Udilma; Conti, Luiz F., E-mail: dneves@ird.gov.b, E-mail: lfcconti@ird.gov.b, E-mail: udilma@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Wasserman, Maria Angelica V., E-mail: maria.wasserman@pq.cnpq.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2011-10-26

    Radioactive accidents has shown the necessity of a previous evaluation planning of exposure and directives for implementation of protection measurements. The description or measurements in the literature usually is associated to reduction of concentrations in the medium where they are applied. For verification the efficiency in dose reduction, it is necessary to proceed simulations. Through the development of data base on protection measurements, it was established basic sceneries, typically tropical as far the building type is concerned and the construction material. The program SIEM was used for simulation of contamination with {sup 137}Cs. The results indicates that generic solutions persuade not to and the decision make processes should be effectuated according to the real conditions of contamination and the use of affected area. For affected areas, two classification criteria were defined: (1) efficiency in reducing the dose in the first year; and (2) efficiency in dose reducing at long term

  19. Protection system for high impedance faults; Sistema de protecao para faltas de alta impedancia

    Energy Technology Data Exchange (ETDEWEB)

    Malagodi, Caius Vinicius Sampaio

    1997-07-01

    This paper proposes a protection system against high impedance faults based on the voltage unbalance along the feeder. The main focus is on the sensor developed together with Sao Paulo state utilities through the CED - Center of Excellence in Distribution, to detect this kind of fault. These simulations show the voltage unbalance that allows to safely determine the conductor breakdown, taking into consideration the distribution transformers and the way they are connected to the line. A zero consequence prototype sensor that has as its greatest advantage the coupling with the distribution line through the electric field, is also presented. Sensibility settings and timings delay are included to allow the coordination between the sensors and other feeder protections.When a fault occurs, only the downstream sensors work. In order to have the information of the sensor situation reaching an upstream fault protection device, a way of communication is needed. Distribution lines with supervision and control system already have this advantage, allowing for the function of protection against faults and high impedance to be aggregated to this communication system. For distribution lines that do not have this kind of system, a more detailed study on the carrier signals as a means of communication should be carried out. (author)

  20. Algorithms evaluation for transformers differential protection; Avaliacao de algoritmos para protecao diferencial de transformadores

    Energy Technology Data Exchange (ETDEWEB)

    Piovesan, Luis Sergio

    1997-07-01

    The appliance of two algorithms is evaluated, one based in Fourier analysis and other based in a rectangular transform technique over Fourier analysis, to be used in digital logical circuits (digital protection relays) for the purpose of differential protection of power transformers (ANSI 87T). The first chapter has a brief introduction about electrical protection. The second chapter discusses the general problems of transform protection, the development of digital technology and, with more detail, the differential protection associated to this technology. In this chapter are presented the particular aspects of transformers differential protection concerning sensibility, inrush current situations and harmonic distortions caused by transformer core saturations and the differential protection algorithms and their applications in a specific relay design. In chapter three, a method to make possible testing the protection performance is developed. This work applies digital simulations using EMTP to generate current signal of transformer operation and fault conditions. Digital simulation using Matlab is used to simulate the protection. The EMTP generated field signals are sent to the relay under test, furnishing data of normal operation, internal and external faults. The relay logic simulator at Matlab will work this data and so, it will be possible to verify and evaluate the algorithm behavior and performance. Chapter 4 shows the protection operation over simulations of several of transformer operation and fault conditions. The last chapter presents a conclusion about the protection performance, discussions about all the methods applied in this work and suggestions for further studies. (author)

  1. New method for protection of parallel generator; Novo metodo para protecao do gerador em paralelismo

    Energy Technology Data Exchange (ETDEWEB)

    Silva, M R.C. da [Elfa-Seg Eletronica Ltda. (Brazil)

    1988-07-01

    The protection of synchronous machinery, especially generators working in parallel with the pertaining electric power utility have been extensively discussed specially because of the growing importance of co-generation in Brazil. This work discusses existing efficient methods and suggests new ways of proceeding this protection. 8 refs., 2 figs.

  2. 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.

  3. 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.

  4. Evaluation of seismic input for nuclear power plants; Evaluacion del input sismico para plantas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Saragoni, G. R.

    2012-07-01

    The accident that affected the Fukushima Daiichi nuclear power plant on March 11th 2011 was the result of the Tohoku earthquake (Japan), the fifth largest ever registered in the world. The characteristics of the event will be a subject for study by the nuclear and seismology communities for many years to come. (Author)

  5. 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)

  6. Verification and software validation for nuclear instrumentation; Verificacion y validacion de software para instrumentacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gaytan G, E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Salgado G, J. R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); De Andrade O, E. [Universidad Federal de Rio de Janeiro, Caixa Postal 68509, 21945-970 Rio de Janeiro (Brazil); Ramirez G, A., E-mail: elvira.gaytan@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    In this work is presented a Verification Methodology and Software Validation, to be applied in instruments of nuclear use with associate software. This methodology was developed under the auspices of IAEA, through the regional projects RLA4022 (ARCAL XCIX) and RLA1011 (RLA CXXIII), led by Mexico. In the first project three plans and three procedures were elaborated taking into consideration IEEE standards, and in the second project these documents were updated considering ISO and IEC standards. The developed methodology has been distributed to the participant countries of Latin America in the ARCAL projects and two related courses have been imparted with the participation of several countries, and participating institutions of Mexico like Instituto Nacional de Investigaciones Nucleares (ININ), Comision Federal de Electricidad (CFE) and Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). In the ININ due to the necessity to work with Software Quality Guarantee in systems for the nuclear power plant of the CFE, a Software Quality Guarantee Plan and five procedures were developed in the year 2004, obtaining the qualification of the ININ for software development for the nuclear power plant of CFE. These first documents were developed taking like reference IEEE standards and regulator guides of NRC, being the first step for the development of the methodology. (Author)

  7. Nuclear desalination for the northwest of Mexico; Desalacion nuclear para el noroeste de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R. F. [Instituto de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)

    2008-07-01

    The IMPULSA project of the Engineering Institute of UNAM, it has dedicated from the year 2005 to the study and development of new desalination technologies of seawater with renewable energies. The objective is to form a group of expert engineers and investigators in the desalination topics able to transform their scientific knowledge in engineering solutions, with a high grade of knowledge of the environment and the renewable energies. In the middle of 2007 was took the initiative in the IMPULSA project to study the nuclear desalination topic. It is evident that before the high cost of the hydrocarbons and its high environmental impact, the nuclear generation alternative of energy becomes extremely attractive, mainly for desalination projects of seawater of great size. The Northwest of Mexico is particularly attractive as the appropriate site for one nuclear desalination plant of great size given its shortage of drink water and the quick growth of its population; as well as its level of tourist, agricultural and industrial activity. In this study was revised the state of the art of the nuclear desalination on the world and it is simulated some couplings and operation forms of nuclear reactors and desalination units, from the thermodynamic and economic viewpoint with the purpose of identifying the main peculiarities of this technology. The objective of the study was to characterize several types and sizes of nuclear reactors of the last generation that could be couple to a desalination technology as multi-stage distillation, type flash distillation or inverse osmosis. It is used for this effect the DEEP 3.1 program of the IAEA to simulate the coupling and to carry out an economic preliminary evaluation. Was found cost very competitive of 0.038-0.044 US$/kWh for the electric power production and 0.60 to 0.77 US$/m{sup 3} for the drink water produced, without including the water transport cost or the use of carbon certificates. (Author)

  8. The risk of nuclear power plants for man. O risco das usinas nucleares para o homem

    Energy Technology Data Exchange (ETDEWEB)

    Freire-Maia, A [UNESP, Botucatu, SP (Brazil)

    1981-01-01

    The author analyzes the risk of nuclear power plants for man with respect to biological radiation effects, sources, level and radiation effects in man. He uses the three Mile Island accident as lesson in order to illustrate a situation potentially dangerous. (C.M.).

  9. 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)

  10. Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

  11. 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)

  12. Cybersecurity: new challenge for nuclear power plants; Ciberseguridad: nuevo reto para las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mirambel Boquera, J.

    2011-07-01

    The purpose of this protective strategy is to ensure ability to detect, contain, respond and recover digital systems for monitoring, control and protection and thus ensure business continuity. A defensive strategy that consists of multiple levels is implemented to protect digital systems from unauthorized access, modification erroneous, misuse or any threat that could pose a risk to the Nuclear Security, Physical Security of people and the Radiological Protection, and the Environment.

  13. Engineering for new-built nuclear power plant projects; Ingenieria para proyectos de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

    This article reviews the opportunities existing in the market (electrical utilities and reactor vendors) for an engineering company with the profile of Empresarios Agrupados (EA) in new-built nuclear power plant projects. To do this, reference is made to some representative examples of projects in which EA has been participating recently. the article concludes sharing with the reader some lessons learned from this participation. (Author)

  14. Evaluation of the ocular protection for low intensity therapeutic lasers; Avaliacao da protecao ocular para lasers terapeuticos em baixa intensidade

    Energy Technology Data Exchange (ETDEWEB)

    Cordon, Rosely

    2003-07-01

    The low intensity laser therapy (LILT) has been extensively used in medicine and dentistry presenting positive effects. However, the laser radiation can also cause adverse effects. Due to the ocular focalization property, in the wavelength from 400 to 1400 nm, the retina is more susceptible to damage by radiation than any other part of the human body. Then, the ocular protection is frequently emphasized. This protection must attenuate the radiation to a safe level. The International Electrotechnical Commission (IEC) standard IEC 60825-1 suggests safety requirements for medical laser equipment, including the ocular protection, based on maximum permissible exposure levels. The Brazilian legislation adopts a corresponding IEC standard, the NBR IEC 601.2.22, for safety requirements. The aim of this study was to analyze the adequacy of the ocular protectors furnished by four laser equipment manufacturers, commercially available in Brazil, commonly used for LILT. For this purpose, the laser equipment and the respective ocular protectors were characterized. The adequacy was verified according to the IEC standards. It was found, among other results, ocular protectors attenuating to safe levels the radiation emitted by the respective laser equipment, however, presenting inadequate visual transmission. Inefficient protection and protection indicated in cases where they were not necessary were also observed. (author)

  15. Safety requirements and radiological protection for ore installations; Requisitos de seguranca e protecao radiologica para instalacoes minero-industriais

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-06-15

    This norm establishes the safety and radiological protection requirements for mining installations which manipulates, process and storing ores, raw materials, steriles, slags and wastes containing radionuclides of the uranium and thorium natural series, simultaneously or separated, and which can cause undue exposures to the public and workers, at anytime of the functioning or pos operational stage. This norm applies to the mining installations activities, suspended or which have ceased their activities before the issue date of this norm, destined to the mining, physical, chemical and metallurgical processing, and the industrialization of raw materials and residues containing associated radionuclides from the natural series of uranium and thorium, including the stages of implantation, operation and decommissioning of the installation.

  16. New zirconium alloys for nuclear application; Novas ligas de zirconio para aplicacao nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lobo, R.M.; Andrade, A.H.P., E-mail: rmlobo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2010-07-01

    Zirconium alloys are widely used in the nuclear industry, mainly in fuel cladding tubes and structural components for PWR plants. The service life of these components, which operate under high temperatures conditions ({approx} 300 deg C), has led to developing new alloys with the aim to improve the mechanical properties, corrosion resistance and irradiation damage. The variation in the composition of the alloy produces second phase particles which alter the materials properties according to their size and distribution, is essential therefore, knowledge their characteristics. Analysis of second phase particles in zirconium alloys are carried out by scanning electron microscopy, transmission electron microscopy and image analysis. This study used the zircaloy-4 to illustrate the characterization of these alloys through the study of second phase particles. (author)

  17. Nuclear hydrogen - possibilities for Brazil; Hidrogenio nuclear - possibilidades para o Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Saliba-Silva, Adonis Marcelo; Linardi, Marcelo [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Centro de Celulas a Combustivel e Hidrogenio]. E-mail: saliba@ipen.br

    2008-07-01

    The energy vector hydrogen represents a good possibility to replace fossil fuels. One of the main renewable sources of interest for hydrogen is water, which is abundant and can be decomposed directly into pure H{sub 2} and O{sub 2}. This water splitting can be performed by the following methods: electrolysis, thermal decomposition, and thermochemical cycles. The thermochemical cycles and high temperature electrolysis (HTE) are often thought to be feasible methods to be associated with a High Temperature Gas cooled Reactor (HTGR). Both routines have high efficiency at temperature range of 700-950 deg C. In this work, is presented an attainable proposal for Brazilian production of hydrogen based on a HTGR followed by HTE system. A research group at Fuel Cell and Hydrogen Center - CCCH at IPEN/CNEN-SP has elaborated a working plan for 10 years, where it is proposed a R and D line for hydrogen production based on nuclear energy supplied by HTGR. So, in this work, a Brazilian program for researching in this area is proposed inviting potential cooperation. (author)

  18. Introgression evidence and phylogenetic relationships among three (ParaMisgurnus species as revealed by mitochondrial and nuclear DNA markers

    Directory of Open Access Journals (Sweden)

    Jakovlić I.

    2013-01-01

    Full Text Available The taxonomy of (ParaMisgurnus genera is still debated. We therefore used mitochondrial and nuclear DNA markers to analyze the phylogenetic relationships among Misgurnus anguillicaudatus, Paramisgurnus dabryanus and Misgurnus fossilis. Differing phylogenetic signals from mitochondrial and nuclear marker data suggest an introgression event in the history of M. anguillicaudatus and M. mohoity. No substantial genetic evidence was found that Paramisgurnus dabryanus should be classified as a separate genus.

  19. The protection system to Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    Andreuzza, Mario Giussepp Santezzi Bertottelli

    1997-01-01

    The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author)

  20. Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities; Instalaciones de almacenamiento de combustible nuclear gastado en seco para instalaciones nucleares mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J., E-mail: juan.salmeron@cnsns.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

    In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

  1. Science and technology as strategic way for nuclear activities; A C e T como fator estrategico para as atividades nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Paiano, Silvestre

    2000-07-01

    The article brings few instructive examples on the interaction between nuclear energy and other areas of science and technology, Microelectronics, computer technology, and new materials are among the many technologies which are crucial for developing nuclear energy technology. On the other way round, nuclear energy presents also a wide range of new demands and opportunities for several areas of science and technology. The problem is that such a relationship is not well understood by the society, and to a large extent it brings about the very process of legitimating the use of nuclear energy (author)

  2. Elaboration of database to support the selection of sites for nuclear installations; Elaboracao de banco de dados para suporte a escolha de locais para instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Dayana Braga Cordeiro; Martins, Vivian Borges, E-mail: braga1dayana@gmail.com, E-mail: vbmartins@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The main objective of this study is to collect data to develop a geocoded geographic database, contributing to the monitoring of nuclear activities situated in the Sao Francisco Basin, and also treat, adapt, display, and organize these data in the form of a single database so that they can be used in the decision-making process.

  3. 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)

  4. Identification of uranium signatures in swipe samples on verification of nuclear activities for nuclear safeguards purposes; Identificacao de assinaturas de uranio em amostras de esfregacos (swipe samples) para verificacao de atividades nucleares para fins de salvaguardas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Pestana, Rafael Cardoso Baptistini

    2013-07-01

    The use of environmental sampling for safeguards purposes, has been applied by the International Atomic Energy Agency–IAEA since 1996 and are routinely used as a complementary measure to strengthen the traditional nuclear safeguards procedures. The aim is verify if the states signatory to the safeguards agreements are not diverging their peaceful nuclear activities for undeclared nuclear activities. This work describes a new protocol of collect and analysis of the swipe samples for identification of nuclear signatures that may be related to the nuclear activities developed in the inspected facility. This work was used as a case of study a real uranium conversion plant of the nuclear fuel cycle of IPEN. The strategy proposed uses different analytical techniques, such as alpha radiation meter, SEM-EDX and ICP-MS to identify signatures of uranium adhered to the swipe samples. In the swipe samples analysis, it was possible to identify particles of UO{sub 2}F{sub 2} and UF4 through the morphological comparison and semi-quantitative analyses performed by SEM-EDX technique. In this work, methods were used that as a result has the average isotopic composition of the sample, in which the enrichment ranged from 1.453 ± 0.023 to 18.24 % ± 0.15 % in the {sup 235}U isotope. Through these externally collections, a non-intrusive sampling, it was possible to identify enriched material handling activities with enrichment of 1.453 % ± 0.023 % to 6.331 ± 0.055 % in the isotope {sup 235}U, as well as the use of reprocessed material, through the identification of the {sup 236}U isotope. The uncertainties obtained for the n({sup 235}U)/n({sup 238}U) ratio varied from 0.40% to 0.86 % for the internal swipe samples. (author)

  5. 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)

  6. Nuclear energy and opportunity to strengthen the sustainable electricity sector; Energia nuclear una oportunidad para fortalecer el sector electrico sustentable

    Energy Technology Data Exchange (ETDEWEB)

    Robles N, A. G. [Comision Federal de Electricidad, Direccion de Proyectos de Inversion Financiada, Gerencia de Proteccion Ambiental, Paseo de la Reforma No. 164, Col. Juarez, 06600 Ciudad de Mexico (Mexico)

    2016-09-15

    The beginning of electricity in Mexico was through the use and exploitation of natural resources; as the demand grew, more generation power plants were required with great capacity and at the same time the fuels used varied, although, oil continued to be the main fuel. At present, due to the effects of climate change, the Conference of the Parties has proposed to reduce the consumption of fossil fuels to give way to clean energy (wind, solar, geothermal, nuclear, etc.), which entails gradually modifying the energy matrix of the electricity sector. The National Development Plan and the National Electricity Sector Development Program, this coordinated by the Energy Secretariat in Mexico, establish policies to promote sustainable development, increasing electricity generation through clean energy sources, including nuclear energy. However, such plans are not accurate in the strategy to be followed to ensure compliance with the increased participation of nuclear energy. This article proposes a nuclear program for the Mexican electricity sector, under the terms of a State policy, aimed at crystallizing a sustainable electricity development 2015-2036; considering that the application to the electricity sector constitutes a representative and justified example of the incorporation of environmental aspects in decision processes for the preservation of the environment. In order to determine the quantity and type of reactors, as well as the number of nuclear power plants and increase of the installed capacity, the general planning scheme of the electric sector was used, taking as reference the modeling criteria of the WASP planning system. Finally, is concluded that the electricity generated by fission of radioactive elements is an opportunity to fulfill the commitments made by Mexico at COP 21 and to meet in an environmentally friendly way the energy requirement that our country needs. (Author)

  7. 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

  8. 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

  9. Proposal for a reformulation in the Brazilian nuclear strategy; Proposta para a reformulacao da estrategia nuclear brasileira

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Omar Campos; Urban, Carlos Werth; Mello, Jair Carlos; Ribeiro, Leonardo Marcio Vilela; Ferreira, Angela Fortini Macedo [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

    1995-12-31

    By the projections of the populational growth and electrical energy demand in Brazil, may be expected that from 2010 to 2015 the nuclear energy will play an important role in electrical energy supply. The PWR technology do not may support the social and economic growth of the country by more than two or three decades. Will be necessary to develop a breeder reactor technology. The new technology must be more economic in primary resources and safer in respect to accidents and fissile material proliferation. The Molten Salt Thermal Breeder Reactor seems fulfill these conditions. (author). 11 refs., 2 tabs.

  10. A proactive method for safety management in nuclear facilities; Um metodo proativo para gerenciamento da seguranca em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio Henrique dos Santos; Carvalho, Paulo Victor Rodrigues de; Santos, Isaac Antonio Luquetti dos, E-mail: grecco@ien.gov.br, E-mail: paulov@ien.gov.br, E-mail: luquetti@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN/RJ), Rio de Janeiro, RJ (Brazil). Div. de Instrumentacao e Confiabilidade Humana

    2014-07-01

    Due to the modern approach to address the safety of nuclear facilities which highlights that these organizations must be able to assess and proactively manage their activities becomes increasingly important the need for instruments to evaluate working conditions. In this context, this work presents a proactive method of managing organizational safety, which has three innovative features: 1) the use of predictive indicators that provide current information on the performance of activities, allowing preventive actions and not just reactive in safety management, different from safety indicators traditionally used (reactive indicators) that are obtained after the occurrence of undesired events; 2) the adoption of resilience engineering approach in the development of indicators - indicators are based on six principles of resilience engineering: top management commitment, learning, flexibility, awareness, culture of justice and preparation for the problems; 3) the adoption of the concepts and properties of fuzzy set theory to deal with subjectivity and consistency of human trials in the evaluation of the indicators. The fuzzy theory is used primarily to map qualitative models of decision-making, and inaccurate representation methods. The results of this study aim an improvement in performance and safety in organizations. The method was applied in a radiopharmaceutical shipping sector of a nuclear facility. The results showed that the method is a good monitoring tool objectively and proactively of the working conditions of an organizational domain.

  11. Recommendations for the nuclear fuel management in Mexico; Recomendaciones para la gestion del combustible nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R.F. [FI-UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)

    2003-07-01

    In this work some observations about the economic and strategic importance of the nuclear fuel management of a nucleo electric power station are presented, especially of the fuel management outside of the reactor core or supply function. We know that the economic competitiveness of the nucleo electric generation in fact resides in its low cost of fuel, in comparison with other alternative energy generation sources. Notwithstanding, frequently it is not given to this function the importance that should to have. The objective of this work is to focus again the mission of this activity, at view of the evolution and the peculiarities of the international markets of the nuclear fuel cycle. Equally a brief exhibition of the markets is made, from the uranium supply until the post- irradiation phase. In the case of the pre-irradiation phase we are in front of a market that the buyers dominate and that seemingly it will not present bigger problems in the next years, however situations exist like the decrease of the existent uranium inventories and the lack opening of new mines that can change the panorama. In relation with the post-irradiation phase, is necessary to study the strategies followed by other countries as the one uranium and plutonium recycled. As I have observed that the reality of that this passing in these markets and the practice of the fuel management, sometimes do not go of the hand, I have looked for to contribute some ideas and suggestions, on as going adapting this important function. (Author)

  12. Methodology if inspections to carry out the nuclear outages model; Metodologia de inspeccciones para cumplir el modelo de paradas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Aycart, J.; Mortenson, S.; Fourquet, J. M.

    2005-07-01

    Before the nuclear generation industry was deregulated in the United States, refueling and maintenance outages in nuclear power plants usually lasted orotund 100 days. After deregulation took effect, improved capability factors and performances became more important. As a result, it became essential to reduce the critical path time during the outage, which meant that activities that had typically been done in series had to be executed in parallel. The new outage model required the development of new tools and new processes, The 360-degree platform developed by GE Energy has made it possible to execute multiple activities in parallel. Various in-vessel visual inspection (IVVI) equipments can now simultaneously perform inspections on the pressurized reactor vessel (RPV) components. The larger number of inspection equipments in turn results in a larger volume of data, with the risk of increasing the time needed for examining them and postponing the end of the analysis phase, which is critical for the outage. To decrease data analysis times, the IVVI Digitalisation process has been development. With this process, the IVVI data are sent via a high-speed transmission line to a site outside the Plant called Center of Excellence (COE), where a team of Level III experts is in charge of analyzing them. The tools for the different product lines are being developed to interfere with each other as little as possible, thus minimizing the impact of the critical path on plant refueling activities. Methods are also being developed to increase the intervals between inspection. In accordance with the guidelines of the Boiling Water Reactor Vessel and Internals project (BWRVIP), the intervals between inspections are typically longer if ultrasound volumetric inspections are performed than if the scope is limited to IVVI. (Author)

  13. Multichannel analyzer for nuclear spectrometry with FPGA using Vivado; Analizador multicanal para espectrometria nuclear con FPGA utilizando Vivado

    Energy Technology Data Exchange (ETDEWEB)

    Garcia D, A.; Hernandez D, V. M.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98060 Zacatecas, Zac. (Mexico); Ordaz G, O. O.; Ibarra D, S. [Universidad de Cordoba, Campus de Rabanales, Carretera Nacional IV, km 396, 14014 Cordoba (Spain); Bravo M, I., E-mail: angelogarciad@hotmail.com [Universidad de Alcala, Departamento de Electronica, Campus Universitario s/n, 28805 Alcala de Henares, Madrid (Spain)

    2017-09-15

    The different applications of ionizing radiation have made this a very significant and useful tool, in turn can be dangerous for living beings if they are exposed to uncontrolled doses. However, due to its characteristics, cannot be perceived by the five senses, in such a way that in order to know the presence of it, radiation detectors and additional devices are required that allow to quantify and classify it. This is the case of the multichannel analyzer that is responsible for separating the different pulse heights that are generated in the detectors, in a certain number of channels; according to the number of bits of the analog to digital converter. The development or conditioning of nuclear technology has increased considerably due to the demand of the applications; therefore this allows developing systems that cover some commercial requirements, cost and volume in relation to the user needs. The objective of the work was to design and implement an intellectual property core (IP Core) which functions as a multichannel analyzer for nuclear spectrometry. For the IP Core design methodology, its components were created in VHDL hardware description language and packaged in the Vivado design suite, making use of resources such as the ARM processor cores that the Zynq chip contains. Likewise, for the first phase of the implementation, the hardware architecture was embedded in the FPGA and the application for the ARM processor was programmed in C language. For the second phase, the management, control and visualization of the results, a virtual instrument was developed in the LabView programming platform. The data obtained as a result of the development and implementation of the IP Core was observed graphically in a histogram that is part of the aforementioned virtual instrument. (Author)

  14. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers; Comunicaciones Recibidas De Diversos Estados Miembros Relativas A Las Directrices Para La Exportacion De Tecnologia, Equipo Y Materiales Nucleares. Transferencias Nucleares Y Transferencias De Equipo, Materiales V Tecnologia Afin Al Doble Uso En Materia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-04-15

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [Spanish] El Director General ha recibido una nota verbal de fecha 5 de marzo de 1993 del Ministerio de Relaciones Exteriores de la RepUblica Eslovaca. El objetivo de la nota verbal es proporcionar informaciOn sobre las Directrices para las transferencias nucleares y las Directrices para la transferencia de equipo, materiales y tecnologia afin al doble uso en materia nuclear, de dicho Gobierno. Atendiendo a los deseos expresados al final de la nota verbal, se adjunta al presente documento el texto de la nota verbal.

  15. Automatic system of welding for nuclear fuel rods; Sistema automatico de soldadura para barras de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Romero G, M; Romero C, J [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    The welding process of nuclear fuel must be realized in an inert gas environment (He) and constant flow of this. In order to reach these conditions it is necessary to do vacuum at the chamber and after it is pressurized with the noble gas (purge) twice in the welding chamber. The purge eliminates impurities that can provoke oxidation in the weld. Once the conditions for initiating the welding are gotten, it is necessary to draw a graph of the flow parameters, pressure, voltage and arc current and to analyse those conditions in which have been carried out the weld. The rod weld must be free of possible pores or cracks which could provoke rod leaks, so reducing the probability of these failures should intervene mechanical and metallurgical factors. Automatizing the process it allows to do reliable welding assuring that conditions have been performed, reaching a high quality welding. Visually it can be observed the welding process by means of a mimic which represents the welding system. There are the parameters acquired such as voltage, current, pressure and flow during the welding arc to be analysed later. (Author)

  16. Development of renal simulators for use in nuclear medicine; Desenvolvimento de simuladores renais para uso em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dullius, Marcos Alexandre

    2014-09-01

    Quality control programs in nuclear medicine include verifying the efficiency of all equipment used for diagnosis and therapy, including scintillation cameras. To that end, we have developed and evaluated the performance of four phantom kidneys - two static anthropomorphic, one semi-dynamic, and one dynamic - to acquire static and dynamic renal scintigraphic images. The static anthropomorphic phantoms were used to characterize and evaluate the response of the processing system for different concentrations of radionuclides through static renal scintigraphy images ({sup 99m}Tc-DMSA), obtained with posterior, right posterior oblique, left posterior oblique, and anterior incidences. The static phantoms were made in two ways; one was made of acrylic from a mold of a pair of human kidneys preserved in formalin, and the second was built with acrylonitrile butadiene styrene (ABS), in a 3D printer using the Slicer program, based on a computed tomography (CT) of the thorax, using the Slicer program. The semi-dynamic and dynamic phantoms were constructed to characterize and evaluate images of dynamic renal scintigraphy. In the semi-dynamic phantom, the injection of radiotracer was performed manually, whereas in the dynamic phantom, the radiotracer was automatically injected through an injector system. With the semi-dynamic phantom, it was possible to analyze the formation of a renogram with normal renal scintigraphic appearance using an imaging system. The simulations obtained from the dynamic phantom simulator enabled studies of normal renal scintigraphy and four other forms of renograms. The static anthropomorphic phantom kidneys proved to be efficient for use in evaluations of varying concentrations of radionuclides. The dynamic phantom kidney was useful for analysis of scintigraphic images and obtaining different pathways for elimination of the radioisotope, allowing for analysis of different renograms. Therefore, the new kidney phantoms would be useful for quality

  17. Nuclear power planning study for Venezuela. Estudio de planificacion nucleoelectrica para Venezuela

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The optimum capacity for nuclear power plants that might be built in Venezuela in the period 1985-2000 and the best time for incorporating them into the electric system is defined. The most recent forecasts regarding growth of the population and demand, and of the economy in general, and the taking into account the costs for the fossil-fuel and hydroelectric resources known to exist in Venezuela, as compared with the costs of importing uranium, are discussed.

  18. Gold nanoparticles applications in natural polymer modified for UV protection; Aplicacao de nanoparticulas de ouro em polimero natural modificado para protecao ultravioleta

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Iris O. da; Ladchumananandasivam, Rasiah; Nascimento, Jose H. O. do; Silva, Francisco C. da; Sa, Christiane S. de A., E-mail: iris.oliveira@gmail.com.br [Universidade Federal do Rio Grande do Norte (PPGEM/UFRN), Natal, RN (Brazil)

    2015-07-01

    The protein-based polymers such as milk, such as polylactic acid (PLA) and soya can be cited as examples of substrates used in various fields of engineering, mainly due to its character of biodegradability, generating low environmental impact when compared to chemical polymers to petroleum-based, which take years to decompose in nature. Among these, soy fiber has great application potential because it is a manufactured material base of a residue obtained from the existing folder in the soybean seeds after oil extraction, using resins and chemicals for structural modification. In this work, soy mesh was used to develop a material with ultraviolet protection properties, through the use of nanotechnology. Thus, to connect the gold nanoparticles (NPAu), the fabric had a surface charge modified with the use of chitosan, using 20% of the weight of the material, followed by nanomaterials exhaust process. The NPAu were synthesized via chemical synthesis with sodium nitrate as reducing and stabilizing agent. The analysis of the solution samples were evaluated by absorbance spectroscopy and solid materials through diffuse reflectance spectroscopy and XRD X-ray diffraction. The size of NPAu was evaluated in equipment Zetasizer nanoseries / nanoZ, finding nanoparticles with an average size of 34.59 nm, and also underlined plasmon resonance phenomenon, with peaks between 530 nm and red coloration, and good results from the soundness washes, compared to conventional dyeing. It was found that soy polymer treated with NPAu presented an excellent property with ultraviolet protection factor (UPF) of +50, considered excellent, proving its potential application in the biomedical field. (author)

  19. Development of a ceramic material to cover walls to be applied in diagnostic radiological protection; Desenvolvimento de um material ceramico para utilizacao em protecao radiologica diagnostica

    Energy Technology Data Exchange (ETDEWEB)

    Frimaio, Audrew

    2006-07-01

    This study aims to formulate a ceramic composition for wall coating seeking to contribute to the optimization of diagnosis rooms' shielding. The work was based on experimental measures of X-radiation attenuation (80 and 100 kV) using ceramic coating materials containing different ceramic bases (red, white, gres, stoneware porcelain tiles, etc). Among the appraised ceramic bases, the white gres presented better attenuation properties and it was considered the most suitable material for the targets of this work. Different formulations of white gres were studied and altered in order to obtain better attenuation properties. Simulations of ceramic compositions using gres coating were made maintaining the percentages of 12-20% clay; 6-18% kaolin; 12-25% phyllite; 8-14% quartz; 1018% feldspar; 32-40% pegmatite and 6-8% talc in the composition of the necessary raw-material. The quantitative and qualitative chemical compositions of these materials were also evaluated and the most common representative elements are SiO{sub 2}, Fe{sub 2}O{sub 3}, Al{sub 2}O{sub 3}, CaO and Ti{sub 2}O{sub 3}. Formulations containing Pb and Ba oxides were studied, considering that CaO can be replaced by PbO or BaO. The attenuation properties for X-radiation were investigated by computer simulations considering the incident and transmitted X-ray spectra for the different studied compositions and they were compared to the properties of the reference materials Pb, Ba and BaSO{sub 4} (barite). The results obtained with the simulations indicated the formulated composition of gres ceramic base that presented better attenuation properties considering the X-ray energies used in diagnosis (80, 100 and 150 kV). Ceramic plates based on the formulated compositions that presented lower percentage differences related to Pb were experimentally produced and physically tested as wall coating and protecting barrier. Properties as flexion resistance module, density, load rupture, water absorption and X radiation attenuation were evaluated for all produced plates. (author)

  20. Program of training and technical expertise in radiation protection for personnel of medical radiology; Programa de capacitacao e especializacao tecnica em protecao radiologica para profissionais em radiologia medica

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Sergio R. de, E-mail: oliveirasr@fiocruz.br [Fundacao Oswaldo Cruz (EPSJV/FIOCRUZ), Rio de Janeiro, RJ (Brazil). Escola Politecnica de Saude Joaquim Venancio

    2013-07-01

    This work aims to verify the actual conditions for the training of technicians in Radiology, in relation to the knowledge of radiation protection in the field of Medical Diagnostic Radiology. To evaluate the knowledge of professionals was prepared a questionnaire on the topic, having been answered by workers with varied experience. The questionnaire was divided into three parts, being the initial self-evaluation, followed by closed and open issues, all specific knowledge. With a total of 55 questionnaires answered, it was found that 85% of respondents consider themselves able to work in the area performing the function, but when questioned about the technical details regarding the exposure to ionizing radiation, it was found that only 15% of respondents had some knowledge about the subject. In relation to Radiological Protection, was found that little more than 10% of the respondents know about the subject. The results found in this survey outlined the creation of a technical specialization course in radiation protection, which is part of the permanent staff of course of the Polytechnical School of Health of FIOCRUZ, solving, partially, one of the problems pointed out today by health bodies, that is the lack of trained personnel.

  1. Para-hydrogen raser delivers sub-millihertz resolution in nuclear magnetic resonance

    Science.gov (United States)

    Suefke, Martin; Lehmkuhl, Sören; Liebisch, Alexander; Blümich, Bernhard; Appelt, Stephan

    2017-06-01

    The precision of nuclear magnetic resonance spectroscopy (NMR) is limited by the signal-to-noise ratio, the measurement time Tm and the linewidth Δν = 1/(πT2). Overcoming the T 2 limit is possible if the nuclear spins of a molecule emit continuous radio waves. Lasers and masers are self-organized systems which emit coherent radiation in the optical and micro-wave regime. Both are based on creating a population inversion of specific energy states. Here we show continuous oscillations of proton spins of organic molecules in the radiofrequency regime (raser). We achieve this by coupling a population inversion created through signal amplification by reversible exchange (SABRE) to a high-quality-factor resonator. For the case of 15N labelled molecules, we observe multi-mode raser activity, which reports different spin quantum states. The corresponding 1H-15N J-coupled NMR spectra exhibit unprecedented sub-millihertz resolution and can be explained assuming two-spin ordered quantum states. Our findings demonstrate a substantial improvement in the frequency resolution of NMR.

  2. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1991-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  3. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1992-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  4. Radiological protection procedures for industrial applications of computed radiography; Procedimentos de protecao radiologica em aplicacoes industriais da radiografia computadorizada

    Energy Technology Data Exchange (ETDEWEB)

    Aquino, Josilto Oliveira de

    2009-03-15

    Due to its very particular characteristics, industrial radiography is responsible for roughly half of the relevant accidents in nuclear industry, in developed as well as in developing countries, according to the International Atomic Energy Agency (IAEA). Thus, safety and radiological protection in industrial gamma radiography have been receiving especial treatment by regulatory authorities of most Member States. The main objective of the present work was to evaluate, from the radioprotection point of view, the main advantages of computed radiography (CR) for filmless industrial radiography. In order to accomplish this, both techniques, i.e. conventional and filmless computed radiography were evaluated and compared through practical studies. After the studies performed at the present work it was concluded that computed radiography significantly reduces the inherent doses, reflecting in smaller restricted areas and costs, with consequent improvement in radiological protection and safety. (author)

  5. Development of a simulator for personnel training on nuclear power plants. The authors` experience in the Federal Republic of Germany; Desarrollo de un simulador para entrenamiento de personal de centrales nucleares. Experiencia de los autores en la Republica Federal de Alemania

    Energy Technology Data Exchange (ETDEWEB)

    Hacker, P; Kogan, A; Garzon, D

    1991-12-31

    This work describes the stages necessary to carry out the development of a full scope simulator for personnel training on nuclear power plants operation. (Author). [Espanol] Este trabajo describe los pasos o etapas necesarios para llevar adelante el desarrollo de un simulador de amplio alcance (full scope simulator) para entrenamiento de personal de operacion de centrales nucleares. (Autor).

  6. The PRONUCLEAR role (1976-1986) in the human resource training for the nuclear area in Brazil: science history; O papel do PRONUCLEAR (1976 -1986) na formacao de recursos humanos para a area nuclear no Brasil: historia da ciencia

    Energy Technology Data Exchange (ETDEWEB)

    Schmiedecke, Winston Gomes

    2006-07-01

    In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear power as an alternative supply for the country's energy needs. However, serious limitations were present regarding the transfer of nuclear technology for a third world country. This paper analyzes some aspects of the process involved in the creation of the specialized human resources during the extent of the agreement between Brazil and West Germany. Since its inception, the agreement received harsh criticism from the Brazilian nuclear physics and related fields scientific communities. Because the planning and implementation of the agreement took place during a period of military dictatorship, the decisions relating to the agreement were never debated between the policy makers and the scientific community. Not surprisingly, the agreement received plenty of criticism that ranged from the actual need for nuclear power to technical feasibility and suspicious of possible military uses and even the very policies created to prepare human resources to work in the nuclear area. One of the most important tools of these policies was the Programa de Recursos Humanos para o Setor Nuclear - PRONUCLEAR (Nuclear Sector Human Resources Program), implemented in 1976 and gradually deactivated starting in 1983. (author)

  7. The PRONUCLEAR role (1976-1986) in the human resource training for the nuclear area in Brazil: science history; O papel do PRONUCLEAR (1976 -1986) na formacao de recursos humanos para a area nuclear no Brasil: historia da ciencia

    Energy Technology Data Exchange (ETDEWEB)

    Schmiedecke, Winston Gomes

    2006-07-01

    In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear power as an alternative supply for the country's energy needs. However, serious limitations were present regarding the transfer of nuclear technology for a third world country. This paper analyzes some aspects of the process involved in the creation of the specialized human resources during the extent of the agreement between Brazil and West Germany. Since its inception, the agreement received harsh criticism from the Brazilian nuclear physics and related fields scientific communities. Because the planning and implementation of the agreement took place during a period of military dictatorship, the decisions relating to the agreement were never debated between the policy makers and the scientific community. Not surprisingly, the agreement received plenty of criticism that ranged from the actual need for nuclear power to technical feasibility and suspicious of possible military uses and even the very policies created to prepare human resources to work in the nuclear area. One of the most important tools of these policies was the Programa de Recursos Humanos para o Setor Nuclear - PRONUCLEAR (Nuclear Sector Human Resources Program), implemented in 1976 and gradually deactivated starting in 1983. (author)

  8. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico; Establecimiento del marco regulador nuclear para el proceso de cierre de instalaciones nucleares en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

  9. Nuclear security in major public events: the XV Pan American Games and the III Para-Pan American Games in Brazil

    International Nuclear Information System (INIS)

    Mello, Luiz A. de; Monteiro Filho, Joselio S.; Belem, Lilia M.J.; Torres, Luiz F.B.

    2009-01-01

    The organization of a major public event involving large numbers of spectators and participants, presents important security challenges. Taking this into consideration, the Brazilian Nuclear Energy Commission (CNEN) has been requested, by the National Secretary of Public Security/ Ministry of Justice (SENASP/MJ), by the end of 2006, to participate on the security actions to be implemented in both the XV Pan American Games and III Para Pan American Games. The XV Pan American Games 2007 and the III Para Pan American Games were held in Rio de Janeiro, Brazil from 13 to 29 July 2007 and from 12 to 19 August 2007, respectively. Those events had 8700 participants between athletes, coaches and referees from 42 countries. More than 300 competition events were held at 17 different venues and were covered by 4910 professionals from TV, radio and written press. Around 2 million tickets have been sold or distributed and 18,000 volunteers participated on the organization. The participation of CNEN was concentrated on the implementation of specific nuclear and radiological security measures to be applied at those events. This was part of a multi-institutional plan for the security of the Games, coordinated by the National Secretary of Public Security of the Ministry of Justice (SENASP/MJ). The support provided by IAEA under a Cooperation Arrangement with the Brazilian authorities was a key factor for the success of the whole operation. The actions taken and the lessons identified by the Brazilian Nuclear Energy Commission related to nuclear and radiological security for the Pan American Games and for the Para Pan American Games are presented. (author)

  10. Conflictos socioambientales en torno a la energía nuclear. Perspectivas desde la Investigación para la Paz

    Directory of Open Access Journals (Sweden)

    Luis Sánchez Vázquez

    2011-06-01

    Full Text Available En los últimos años se ha reactivado el debate sobre la energía nuclear. Esta opción ha reemergido amparada en la etiqueta de «energía limpia», por la no emisión de gases de efecto invernadero en su proceso productivo. Sin embargo, la incertidumbre sobre las fases de tratamiento necesarias para administrar con seguridad los residuos, incluyendo, en su caso, el reprocesado del combustible; los problemas ambientales derivados de la minería del uranio; e incluso los riesgos laborales derivados del trabajo con material fisionables, componen un panorama de situaciones conflictivas de carácter complejo que continúa siendo el principal caballo de batalla de la oposición antinuclear y ecologista. En este artículo se pretenden identificar los distintos conflictos socioambientales aparejados a la energía nuclear teniendo en cuenta su ciclo de vida completo, con el objetivo aportar soluciones al debate sobre la problemática ambiental en torno a la energía nuclear desde la perspectiva de la Investigación para la Paz.

  11. 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...

  12. Fundamental bases to implementation the specific national norm for nuclear gauges; Bases fundamentais para a implantação de norma nacional específica para medidores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, L.C.; Silva, E.R.; Ferreira, R.; Peixoto, J.G.P., E-mail: luizxiii@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The aims of this work is to provide grounds for creation a national standard practice security and responsibility in the use of nuclear gauges in accordance with the national recommendation already exist, following the basic security principles, responsibilities of these involved in the acquisition, operation, storage, maintenance and post-emergency on use of nuclear gauges. (author)

  13. 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.

  14. Interesting tools for the cybersecurity plan of a nuclear power plant; Herramientas de utilidad para el plan de Ciberseguridad de una Planta Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pareja, I.; Carrasco, J. A.; Cerro, F. J. del

    2012-07-01

    The use of digital technologies in monitoring and control systems of nuclear power plants and their connectivity requirements, originate cybersecurity difficulties that should be addressed in a cybersecurity plan. This plan should guide the policies and procedures followed during the design maintenance and operation of the systems inside a nuclear power plant. It also should refer to adequate tools able to reach the established cybersecurity requirements. The combination of Datadiodes and tools for publishing video (like tVGA2web), permit an isolation and remote maintenance in a 100% safety way and their use should be disseminated. In the paper other type of tools useful for nuclear power plants are also mentioned.

  15. Determination of leveled costs of electric generation for gas plants, coal and nuclear; Determinacion de costos nivelados de generacion electrica para plantas de gas, carbon y nucleares

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

    The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

  16. Basic information to improve public acceptance to nuclear energy in Brazil; Subsidios para a melhoria da aceitacao da energia nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Gibelli, Sonia M.O.; Lima e Silva, Pedro Paulo de; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    In Brazil, the current production of nuclear energy is restricted to Angra I plant, a 657 MW pressurized water reactor, in operation since 1982. Among the eight units predicted in 1975 within the Brazil Germany nuclear agreement, only two have been effectively contracted, namely Angra 2 and 3. The nuclear alternative, likewise all other energy sources, is very much dependable on the assessment of their own benefits compared to the associated risks posed to the population and the environment. The main goal of this article is to provide information to enable the improvement of public acceptance of the use of nuclear energy in the country, by comparing risks associated with different sources as well as pointing out aspects related to risk perception by the public. (author) 18 refs., 5 figs.; e-mail: sonia at cnen.gov.br; lima-e-silva at pobox.com; axavier at cnen.gov.br

  17. 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.

  18. Nuclear parameters determination of the {sup 127}Te {beta} {sup -} decay: a proposal for teaching nuclear physics; Determinacao de parametros nucleares do nucleo de {sup 127}Te: uma proposta para o ensino de fisica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Batista, Wagner Fonseca

    2011-07-01

    A study of the {sup 127}Te {beta}{sup -} decay was carried out by means of gamma spectroscopy measurements using high resolution HPGe detector, in the region from 30 keV to 1.0 MeV, aiming to get a better understanding of the {sup 127}Te nuclear structure. The radioactive sources of {sup 12}7Te were obtained from the {sup 126}Te(n,{gamma}){sup 1}'2{sup 7}Te nuclear reaction produced in the IEA- R1 nuclear reactor at IPEN/CNEN-SP. Five gamma {sup t}ransitions previously attributed to this decay were confirmed with a better precision than previously. The half-life of {sup 127}Te was also studied resulting in data with lower uncertainty. Using a set of data selected from gamma spectroscopy measurements was developed and applied a didactic proposal for high school students using the Excel software. (author)

  19. Software development for managing nuclear material database; Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tondin, Julio Benedito Marin

    2011-07-01

    In nuclear facilities, the nuclear material control is one of the most important activities. The Brazilian National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), when inspecting routinely, regards the data provided as a major safety factor. Having a control system of nuclear material that allows the amount and location of the various items to be inspected, at any time, is a key factor today. The objective of this work was to enhance the existing system using a more friendly platform of development, through the VisualBasic programming language (Microsoft Corporation), to facilitate the operation team of the reactor IEA-R1 Reactor tasks, providing data that enable a better and prompter control of the IEA-R1 nuclear material. These data have allowed the development of papers presented at national and international conferences and the development of master's dissertations and doctorate theses. The software object of this study was designed to meet the requirements of the CNEN and the IAEA safeguard rules, but its functions may be expanded in accordance with future needs. The program developed can be used in other reactors to be built in the country, since it is very practical and allows an effective control of the nuclear material in the facilities. (author)

  20. Calculation of absorbed dose for skin contamination imparted by beta radiation through the VARSKIN modified code for 122 interesting isotopes for nuclear medicine, nuclear power plants and research; Calculo de dosis absorbida para contaminacion en piel impartida por radiacion beta mediante el codigo VARSKIN modificado para 122 isotopos de interes para medicina nuclear, plantas nucleares e investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez R, J T [Depto. de Metrologia, ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-07-01

    In this work the implementation of a modification of the VARSKIN code for calculation of absorbed dose for contamination in skin imparted by external radiation fields generated by Beta emitting is presented. The modification consists on the inclusion of 47 isotopes of interest even Nuclear Plants for the dose evaluation in skin generated by 'hot particles'. The approach for to add these isotopes is the correlation parameter F and the average energy of the Beta particle, with relationship to those 75 isotopes of the original code. The methodology of the dose calculation of the VARSKIN code is based on the interpolation, (and integration of the interest geometries: punctual or plane sources), of the distribution functions scaled doses in water for beta and electrons punctual sources, tabulated by Berger. Finally a brief discussion of the results for their interpretation and use with purposes of radiological protection (dose insurance in relation to the considered biological effects) is presented.

  1. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  2. 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

  3. Aplicativo para dosimetria interna usando a distribuição biocinética de fótons baseada em imagens de medicina nuclear

    Directory of Open Access Journals (Sweden)

    Viriato Leal Neto

    2014-10-01

    Full Text Available Objetivo: Este artigo apresenta uma forma de se obterem estimativas de dose em pacientes submetidos a tratamentos radioterápicos a partir da análise das regiões de interesse em imagens de medicina nuclear. Materiais e Métodos: Foi desenvolvido o software denominado DoRadIo (Dosimetria das Radiações Ionizantes, que recebe as informações sobre os órgãos fontes e o órgão alvo e retorna resultados gráficos e numéricos. As imagens de medicina nuclear utilizadas foram obtidas de catálogos disponibilizados por físicos médicos. Nas simulações utilizaram-se modelos computacionais de exposição constituídos por fantomas de voxels acoplados ao código Monte Carlo EGSnrc. O software foi desenvolvido no Microsoft Visual Studio 2010 com o modelo de projeto Windows Presentation Foundation e a linguagem de programação C#. Resultados: Da aplicação das ferramentas foram obtidos: o arquivo para otimização das simulações Monte Carlo utilizando o EGSnrc, a organização e compactação dos resultados dosimétricos com todas as fontes, a seleção das regiões de interesse, a contagem da intensidade dos tons de cinza nas regiões de interesse, o arquivo das fontes ponderadas e, finalmente, todos os resultados gráficos e numéricos. Conclusão: A interface de usuários pode ser adaptada para uso em clínicas de medicina nuclear como ferramenta computacional auxiliar na estimativa da atividade administrada.

  4. 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)

  5. Arrangements for preparedness for a nuclear or radiological emergency. Safety guide (Spanish Edition); Disposiciones de preparacion para emergencias nucleares o radiologicas. Guia de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and available results of research relating to response to such emergencies. The primary objectives of this Safety Guide, co-sponsored by FAO, OCHA, ILO, PAHO and WHO, are to provide guidance on preparedness and response for a nuclear or radiological emergency, to describe appropriate responses to a range of emergencies, and to provide background information on past experience, thus helping the user to better implement arrangements that address the underlying issues.

  6. Serpent: an alternative for the nuclear fuel cells analysis of a BWR; SERPENT: una alternativa para el analisis de celdas de combustible nuclear de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Silva A, L.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Gomez T, A. M., E-mail: lidi.s.albarran@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In the last ten years the diverse research groups in nuclear engineering of the Universidad Nacional Autonoma de Mexico and Instituto Politecnico Nacional (UNAM, IPN), as of research (Instituto Nacional de Investigaciones Nucleares, ININ) as well as the personnel of the Nuclear Plant Management of the Comision Federal de Electricidad have been using the codes Helios and /or CASMO-4 in the generation of cross sections (X S) of nuclear fuel cells of the cores corresponding to the Units 1 and 2 of the nuclear power plant of Laguna Verde. Both codes belong to the Studsvik-Scandpower Company who receives the payment for the use and their respective maintenance. In recent years, the code Serpent appears among the nuclear community distributed by the OECD/Nea which does not has cost neither in its use neither in its maintenance. The code is based on the Monte Carlo method and makes use of the processing in parallel. In the Escuela Superior de Fisica y Matematicas of the IPN, the personnel has accumulated certain experience in the use of Serpent under the direction of personal of the ININ; of this experience have been obtained for diverse fuel burned, the infinite multiplication factor for three cells of nuclear fuel, without control bar and with control bar for a known thermodynamic state fixed by: a) the fuel temperature (T{sub f}), b) the moderator temperature (T{sub m}) and c) the vacuums fraction (α). Although was not realized any comparison with the X S that the codes Helios and CASMO-4 generate, the results obtained for the infinite multiplication factor show the prospective tendencies with regard to the fuel burned so much in the case in that is not present the control bar like when it is. The results are encouraging and motivate to the study group to continue with the X S generation of a core in order to build the respective library of nuclear data as a following step and this can be used for the codes PARCS, of USA NRC, DYN3D of HZDR, or others developed locally

  7. Ion chamber-electrometer measurement system for radiation protection tests in X-ray equipment for interventional procedures; Sistema de medicao camara de ionizacao-eletrometro para ensaios de protecao radiologica em equipamentos de raios X para procedimentos intervencionistas

    Energy Technology Data Exchange (ETDEWEB)

    Bottaro, Marcio

    2012-07-01

    A new parallel plate ionization chamber with volume of 500 cc and an electrometer with digital interface for data acquisition, configuring an ion chamber electrometer measurement system, were developed to comply with specific requirements for compulsory radiation protection tests in interventional X-ray equipment. The ion chamber has as main characteristics: low cost, mechanical strength and response variation with beam energy of less than 5% in the 40 kV to 150 kV range. The electrometer has a high gain (5x10{sup 8} V/A) transimpedance amplifier circuit and a data acquisition and control system developed in LabVIEW Registered-Sign platform, including an integrated power supply for the ion chamber bias with adjustable DC voltage output from O to 1000 V and an air density correction system. Electric field calculations, laboratory measurements in standard beams and computational simulations of radiation interactions in chamber volume with Monte Carlo Method were employed in the elaborated methodology of the ion chamber development, which was tested and validated. It was also developed a simplified methodology for electrometer calibration that assures metrological trustworthiness of the measurement system. Tests for the system performance evaluation as environmental influence response, energy response, angular dependency, linearity and air kerma and air kerma rate dependency were performed according to international standards and requirements. Additionally, for a detailed evaluation of the developed ion chamber, simulations with various scattered radiation spectra were performed. The system was applied in leakage radiation, residual radiation and scattered radiation tests, being compared with other reference systems and validated for laboratorial test routine. (author)

  8. 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)

  9. 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)

  10. Rewriting the history: a new future for the nuclear energy in United Kingdom?; Reescribiendo la historia: un nuevo futuro para la energia nuclear en Reino Unido?

    Energy Technology Data Exchange (ETDEWEB)

    Woodman, B. [University of Warwick, Coventry CV4 8UW (United Kingdom)

    2009-07-01

    From ends of the ninety, the new nuclear energy has been rejected three times like an option of viable energy generation for United Kingdom: once during the privatization of the electric supply industry and twice during the subsequent revisions to the energy politicians carried out in 2003. Nevertheless, three years more late, a new debate around the energy politics gave an unusual turning in the industry destination, characterized by the firm consideration in the political calendar about the new reactors development, as well as of governmental politicians guided to impel it. This recent interest arises of restlessness regarding the future security of the supply and to the necessity of reducing the carbon dioxide emissions of United Kingdom. With the purpose of obtaining the sufficient support of civil politicians and investors for the new construction project, the industry will have to devise convincing arguments to prove that it has already solved those problems that it suffered in the past and, also that deserves to receive a special treatment in the liberated market of the electricity. This document synthesizes the structure of the nuclear industry in United Kingdom, some recent historical data and the reasons for those that the new nuclear reactors were not very received in the past. It also indicates the measures that have taken in recent times to modify that perspective. Finally, it analyzes the possible future of the nuclear energy at long term in United Kingdom. (Author)

  11. 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

  12. Sustainability indicators for innovation and research institutes of nuclear area in Brazil; Indicadores de sustentabilidade para institutos de pesquisa e inovacao da area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alves, S.F.; Barreto, A.A.; Rodrigues, P.C.H.; Feliciano, V.M.D., E-mail: sfa@cdtn.br, E-mail: aab@cdtn.br, E-mail: pchr@cdtn.br, E-mail: vmfj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-11-01

    Indicators are relevant tools for measuring sustainability process. In this study, the relevance of sustainability indicators appropriate for research and innovation institutes in Brazil is discussed. As reference for case study, nuclear research and innovation institutes were chosen. Sixty-nine sustainability indicators were considered. Some of these indicators were obtained from lists in the literature review, distributed between the dimensions environmental, economic, social, cultural and institutional. The other indicators were developed through discussions between professionals from nuclear, environmental, economic, social and cultural areas. Among the investigated indicators, 32 were selected as being the most relevant. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed. (author)

  13. A hybrid approach to solving the problem of design of nuclear fuel cells; Un enfoque hibrido para la solucion del problema del diseno de celdas de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Montes T, J. L.; Perusquia del C, R.; Ortiz S, J. J.; Castillo, A., E-mail: joseluis.montes@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    An approach to solving the problem of fuel cell design for BWR power reactor is presented. For this purpose the hybridization of a method based in heuristic knowledge rules called S15 and the advantages of a meta-heuristic method is proposed. The synergy of potentialities of both techniques allows finding solutions of more quality. The quality of each solution is obtained through a multi-objective function formed from the main cell parameters that are provided or obtained during the simulation with the CASMO-4 code. To evaluate this alternative of solution nuclear fuel cells of reference of nuclear power plant of Laguna Verde were used. The results show that in a systematic way the results improve when both methods are coupled. As a result of the hybridization process of the mentioned techniques an improvement is achieved in a range of 2% with regard to the achieved results in an independent way by the S15 method. (Author)

  14. Proposal of guidelines for structuring an independent regulation body for the Brazilian nuclear sector; Proposta de diretrizes para estruturacao de um orgao de regulacao independente para o setor nuclear brasileiro

    Energy Technology Data Exchange (ETDEWEB)

    Nicoll Junior, Ricardo

    2016-07-01

    Regulatory bodies are responsible for regulation in various sectors of society. In Brazil, they work in various areas for the development of the country and have as main objective the social, economic and national development. The progress of new technologies in the nuclear field and their commercialization underscores the need for regulation according to international safety standards. The present research searches through an extensive review of the literature identify the international guidelines for regulatory bodies and make a comparative analysis between Brazil and five countries that have independent regulatory bodies in the nuclear sector. The purpose of the work is to contribute to the Brazilian public sectors, with an evaluation of the country's regulation in the perception of specialists and propose guidelines for the structuring of an independent regulatory body, respecting international agreements and the legislation in force in the country. (author)

  15. 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.

  16. Calculation methods of reactivity using derivatives of nuclear power and Filter fir; Metodos para o calculo da reatividade usando derivadas da potencia nuclear e o filtro FIR

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, Daniel Suescun

    2007-07-01

    This work presents two new methods for the solution of the inverse point kinetics equation. The first method is based on the integration by parts of the integral of the inverse point kinetics equation, which results in a power series in terms of the nuclear power in time dependence. Applying some conditions to the nuclear power, the reactivity is represented as first and second derivatives of this nuclear power. This new calculation method for reactivity has special characteristics, amongst which the possibility of using different sampling periods, and the possibility of restarting the calculation, after its interruption associated it with a possible equipment malfunction, allowing the calculation of reactivity in a non-continuous way. Apart from this reactivity can be obtained with or without dependency on the nuclear power memory. The second method is based on the Laplace transform of the point kinetics equations, resulting in an expression equivalent to the inverse kinetics equation as a function of the power history. The reactivity can be written in terms of the summation of convolution with response to impulse, characteristic of a linear system. For its digital form the Z-transform is used, which is the discrete version of the Laplace transform. In this method it can be pointed out that the linear part is equivalent to a filter named Finite Impulse Response (Fir). The Fir filter will always be, stable and non-varying in time, and, apart from this, it can be implemented in the non-recursive way. This type of implementation does not require feedback, allowing the calculation of reactivity in a continuous way. The proposed methods were validated using signals with random noise and showing the relationship between the reactivity difference and the degree of the random noise. (author)

  17. Nuclear magnetic resonance system with continuous flow of polarized water to obtain the traceability to static magnetic fields; Sistema de ressonancia magnetica nuclear com fluxo continuo de agua polarizada para obtencao da rastreabilidade para campos magneticos estaticos

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Ramon Valls; Nazarre, Diego Joriro, E-mail: ramon@ipt.br [Instituto de Pesquisas Tecnologicas (IPT), Sao Paulo, SP (Brazil)

    2013-07-01

    We have developed a system to obtain the traceability of field or magnetic induction intensity in the range of 2 μT up to 2 T, even in the presence of magnetic field gradients or noisy environments. The system is based on a nuclear magnetic resonance magnetometer, built in streaming water. The calibration procedure of a coil for magnetic field generation is described, as well as the results obtained and the estimated uncertainty (author)

  18. The resurgence of nuclear energy. An option for the climatic change and for the emergent countries?; El resurgimiento de la energia nuclear. Una opcion para el cambio climatico y para los paises emergentes?

    Energy Technology Data Exchange (ETDEWEB)

    Campos A, L. [UNAM, Instituto de Investigaciones Economicas, Circuito Mario de la Cueva, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Nieva G, R.; Mulas, P. [Instituto de Investigaciones Electricas, Av. Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Velez, C. [Electricite de France, Comite Cientifico Asesor, 22-30 avenue de Wagram, 75382 Paris (France); Ortiz M, J. R. [ININ, Carretera Mexico-Toluca s/n, 52759 Ocoyoacac, Estado de Mexico (Mexico); Thomas, S. [University of Greenwich, 30 Park Row, London SE10 9LS (United Kingdom); 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); Woodman, B. [University of Warwick, Coventry CV4 8UW (United Kingdom); Mez, L. [Freie Universitat Berlin, Environmental Policy Research Centre, Thielallee 47, 14195 Berlin (Germany)

    2009-07-01

    The modern society is organized in mistaken form. A tremendous inability of the juridical, political, social and cultural system exists to interrelate the ecosystem (the resources that allow the life and the human activity) with the economic way of production, that is to say with the manner like the human beings appropriate of the nature and they transform it to satisfy the reproduction necessities of the capital and the population. Today we are already paying the consequences of this error. Of continuing with this tendency the next six years, a global increase of five centigrade grades is expected in the temperature, with effects like the increase of the sea level, floods, droughts, among other global problems, for what the gases of greenhouse effect are and they will continue being the main environmental challenge of the X XI century because they not represent alone a threat for the development but also for the humanity survival. The world conscience has wakened up, and in most of the countries where is stopped the construction of new nuclear power plants the plans are reconsidered to return the use of this source, being the two main reasons for reconsideration: the concern for the climatic change and the new world perception about the limits of fossil fuel reserves. The world return of the interest for the nuclear energy, it force to take in consideration the energy politics of Mexico whose structure is too much dependent of hydrocarbons and the import of liquefied natural gas and other energies, subject to the prices volatility and in a frame that lacks long term vision. Here the whole problem of the nuclear industry is exposed, the experiences, the risks, the costs, the future of the energy production for the populations that every time has a bigger consumption, the reader will have, this way, a wide panorama of diverse topics and interests that affect to generation of nuclear energy. (Author)

  19. 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)

  20. 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

  1. Mapa de cuidados para pacientes sometidos a procedimientos en servicios de medicina nuclear Care map for patients under nuclear medicine procedures

    Directory of Open Access Journals (Sweden)

    Cayetano Fernández Sola

    2009-03-01

    Full Text Available Objetivo: desarrollar un instrumento que facilite la sistematización, registro y continuidad del cuidado en servicios de medicina nuclear. Metodología: investigación desarrollada durante 2004 en el servicio de Medicina Nuclear en un Hospital de Almería, España. A partir de la revisión bibliográfica y de la práctica clínica, se realizó búsqueda de problemas de enfermería y de colaboración y se procedió a la estandarización y codificación del lenguaje según taxonomías NANDA, NOC y NIC. Luego de la valoración inicial, focalizada por necesidades básicas, se formularon diagnósticos de enfermería y de complicaciones; y las intervenciones asociadas a los diagnósticos y a problemas de colaboración. Finalmente se realizó seguimiento, evaluación e informe de continuidad de cuidados. Resultados: los diagnósticos de enfermería prevalentes fueron: conocimientos deficientes, temor, interrupción de la lactancia materna y riesgo de lesión. Los resultados esperados, expresados según taxonomía NOC, fueron: Conocimientos del procedimiento, Autocontrol del miedo Lactancia materna: Destete y Control del riesgo; y las Intervenciones de enfermería: Enseñanza del procedimiento, Disminución de la ansiedad, Supresión de la lactancia, Manejo ambiental de seguridad e Intervenciones asociadas a problemas de colaboración. Conclusión: el mapa de cuidados facilita el trabajo, utiliza el proceso de enfermería y ayuda a registrar las intervenciones practicadas en pacientes sometidos a procedimientos en servicios de medicina nuclear.Objective: the development of a tool that provides the systematic, registration and care continuity in the nuclear medicine services. Methodology: this research was developed during 2004 as a result of the creation of the Nuclear Medicine Service in the Torrecárdenas Hospital, in Almeria, Spain. A nursing problem review was undertaken from the data that captured in the bibliography review and clinical practice

  2. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition); Analisis determinista de seguridad para centrales nucleares. Guia de Seguridad Especifica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  3. Standard model for the safety analysis report of nuclear fuel reprocessing plants; Modelo padrao para relatorio de analise de seguranca de usinas de reprocessamento de combustiveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-02-15

    This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization.

  4. Nuclear and mitochondrial DNA markers in traceability of retail beef samples Marcadores de DNA nuclear e mitocondrial para rastreabilidade da carne bovina comercializada

    Directory of Open Access Journals (Sweden)

    Aline S.M. Cesar

    2010-09-01

    ém de dados da cadeia produtiva. Em geral, a empresa certificadora dispõe das informações do animal que está sendo abatido, porém não tem condições de garantir se houve erro entre abate, desossa, processamento e a distribuição dos produtos. Existe diferenciação no custo e na qualidade dos produtos cárneos, especialmente no mercado internacional, em virtude do sexo e composição racial dos animais. Os marcadores genéticos permitem identificar as características que são controladas num programa de rastreabilidade bovina tais como sexo e composição racial, permitindo identificar e avaliar corretamente para o consumidor, o produto final. A hipótese deste estudo foi que a maioria das amostras de carne bovina vendida no mercado local seria proveniente de fêmeas e com grande participação de raças Zebu. O objetivo deste trabalho foi caracterizar amostras de carne bovina com marcadores de DNA para identificar o sexo e a composição racial. Em dez pontos comerciais da cidade de Pirasssununga, SP, Brasil, foram coletadas 61 amostras e todas foram genotipadas como possuindo DNA mitocondrial Bos taurus e 18 foram positivos para amplificação do cromossomo Y (macho. Para o marcador sat1711b-Msp I a frequência alélica do A foi 0.278 e para o marcador Lhr-Hha I a frequência alélica do T foi 0.417. Os resultados das frequências alélicas do sat1711b-Msp I e Lhr-Hha I apresentaram menor proporção do genoma Bos indicus em relação ao Bos taurus quando comparado ao rebanho Nelore. Com a metodologia descrita neste trabalho foi possível avaliar o sexo e as características de subespécie das amostras de carne bovina, tendo uma importante aplicação para a certificação de produtos cárneos especialmente, em programas de rastreabilidade animal.

  5. Treze passos para o juízo final: a nova era do desarmamento nuclear dos Estados Unidos e da Rússia Thirteen steps to judgement day: the new era of Russian and North American nuclear disarmament

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de Jesus

    2008-08-01

    Full Text Available Este artigo procura explicar por que os líderes dos EUA e da Rússia não implementaram total e efetivamente o plano de ação de treze pontos práticos para o desarmamento nuclear, estabelecido na Conferência de Revisão do Tratado de Não-Proliferação Nuclear em 2000. As decisões relacionadas aos treze pontos, tomadas pelos membros dos Executivos das duas maiores potências nucleares, são vistas como resultado da conciliação de imperativos internos e externos por esses indivíduos, que enfrentam oportunidades e dilemas estratégicos distintos simultaneamente nos âmbitos doméstico e internacional. São consideradas as escolhas políticas de membros dos Executivos nacionais e estrangeiros, Legislativos e principais grupos de interesse desses países, bem como a distribuição de poder sobre a formulação da decisão nacional, estabelecida pelas instituições políticas domésticas. As hipóteses apontam que os membros dos Executivos desses países - apoiados por grande parte dos membros dos Legislativos e dos principais grupos de interesse envolvidos, como as Forças Armadas - procuraram garantir autonomia para definir a estrutura e a composição de forças estratégicas e táticas, modernizar arsenais atômicos e operar uma força capaz de lidar com contingências que envolvam não apenas potências nucleares tradicionais, mas principalmente novos Estados detentores de armas de destruição em massa e organizações terroristas.This article aims to explain why U.S. and Russian leaders have not implemented totally and effectively the thirteen practical-step plan of action on nuclear disarmament agreed at the 2000 Nuclear Non-Proliferation Treaty Review Conference. The decisions with regard to the thirteen steps, taken by members of U.S. and Russian Executives, are seen as the result of the conciliation of internal and external imperatives by those individuals, who face distinctive strategic opportunities and dilemmas simultaneously

  6. Nuclear power generation in competition with other sources for base load electricity generation; La generacion nuclear en competencia con otras fuentes para generacion electrica de base

    Energy Technology Data Exchange (ETDEWEB)

    Notari, C; Rey, F C [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

    1997-12-31

    The latest studies performed by OECD and IAEA on the subject were analyzed in order to clarify the international context. Nuclear, gas and coal are compared. The general conclusion is that nuclear power is competitive for electricity generation considering new plants to be commissioned around year 2000. If the discount rate is 5% per annum it is considered the best option in most of the countries included in the studies. If 10% is chosen the levelized costs favour the gas option. In the Argentine case, the analysis of possible plants for the near future shows a clear advantage for the gas projects. This is mainly due to the low capital costs and low local gas prices. The possible evolution of this situation is considered: gas prices will most probably increase because they should approach the price of fuel oil or diesel oil which are used as substitutes in winter for electricity generation and the export projects to Chile and Brasil will also push prices up. The environmental aspects of the question and its influence on regulations and costs is a matter of speculation. Some countries have already penalized greenhouse gases emissions but it is not clear how and when this trend will affect local prices. (author). 4 refs., 6 tabs.

  7. An image analyzer system for the analysis of nuclear traces; Un sistema analizador de imagenes para el analisis de trazas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cuapio O, A

    1990-10-15

    Inside the project of nuclear traces and its application techniques to be applied in the detection of nuclear reactions of low section (non detectable by conventional methods), in the study of accidental and personal neutron dosemeters, and other but, are developed. All these studies are based on the fact that the charged particles leave latent traces of dielectric that if its are engraved with appropriate chemical solutions its are revealed until becoming visible to the optical microscope. From the analysis of the different trace forms, it is possible to obtain information of the characteristic parameters of the incident particles (charge, mass and energy). Of the density of traces it is possible to obtain information of the flow of the incident radiation and consequently of the received dose. For carry out this analysis has been designed and coupled different systems, that it has allowed the solution of diverse outlined problems. Notwithstanding it has been detected that to make but versatile this activity is necessary to have an Image Analyzer System that allow us to digitize, to process and to display the images with more rapidity. The present document, presents the proposal to carry out the acquisition of the necessary components for to assembling an Image Analyzing System, like support to the mentioned project. (Author)

  8. Quality control in nuclear fuel fabrication on the inspection basis; Control de calidad para fabricacion de combustible nuclear en base a inspecciones

    Energy Technology Data Exchange (ETDEWEB)

    Fuentes S, A. [Instituto Tecnologico de Toluca, Toluca (Mexico)

    1997-12-31

    Every plant productive of electric power requires the use of energetics for the transformation to electricity. In the nucleo electric plant the energetic is the uranium, in which it makes ensembles and is used as fuel in the reactor. To assure that the fuel ensembles fulfill the specifications and requirements of design stipulated in the nucleo electric plant is that under a quality control through inspections during the fabrication process. The purpose of this work is to study and verify that the lineaments of the standard 10 CFR 50 appendix B `Quality assurement for nuclear plants` specially in the criteria `Inspections` that is used to guarantee the quality of the ensembles. This standard is the one that rules every activity and operation inside the pilot plant and its established in the quality program in the production of nuclear fuel for the Laguna Verde plant. The quality of the assemble is verified through each one of the tests or inspections due to the importance of it in the fabrication of fuel. (Author)

  9. Quality control in nuclear fuel fabrication on the inspection basis; Control de calidad para fabricacion de combustible nuclear en base a inspecciones

    Energy Technology Data Exchange (ETDEWEB)

    Fuentes S, A [Instituto Tecnologico de Toluca, Toluca (Mexico)

    1998-12-31

    Every plant productive of electric power requires the use of energetics for the transformation to electricity. In the nucleo electric plant the energetic is the uranium, in which it makes ensembles and is used as fuel in the reactor. To assure that the fuel ensembles fulfill the specifications and requirements of design stipulated in the nucleo electric plant is that under a quality control through inspections during the fabrication process. The purpose of this work is to study and verify that the lineaments of the standard 10 CFR 50 appendix B `Quality assurement for nuclear plants` specially in the criteria `Inspections` that is used to guarantee the quality of the ensembles. This standard is the one that rules every activity and operation inside the pilot plant and its established in the quality program in the production of nuclear fuel for the Laguna Verde plant. The quality of the assemble is verified through each one of the tests or inspections due to the importance of it in the fabrication of fuel. (Author)

  10. Practical approach in training (on-the-job) for workers in nuclear industries; Abordagem pratica no treinamento (on-the-job) para trabalhadores em industrias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Vianna, Vilson Bedim; Rocha, Janine Gandolpho da [Industrias Nucleares do Brasil SA, Rio de Janeiro, RJ (Brazil)

    2005-07-01

    This work approaches the 'on-the-job training' - a method of practical training - used in nuclear industries for workers who handle radioactive nuclides. The required training must, in accordance with the ISO 9000 standard, be geared to meet the needs of the organization, including the minimization of errors in operation with radionuclides, which involves various aspects (standard, social, environmental, personal and process safety etc.). Therefore, the training process must have the commitment of everybody and have a logical and documented sequence, where both the individual and the needs of the company are raised and analyzed. The clear identification of the radiological risks associated to the hands-on training is critical to the safety of who is being trained and should be part of the training content. However, the greatest challenge is a mechanism allowing to transform the hands-on training in practical learning. The role of training in the modern nuclear industry should not be restricted to provide conditions for better training or development of the employee, but also motivate the continuous improvement of the company and of the productive process.

  11. National phantoms bank for the service of nuclear medicine in Cuba. Utility for the quality control of the instrumentation; Banco de fantomas nacional para los servicios de medicina nuclear en Cuba. Utilidad para el control de calidad de la instrumentacion

    Energy Technology Data Exchange (ETDEWEB)

    Varela C, C.; Diaz B, M. [CCEEM, Calle 4 No. 455 (altos) e/19 y 21, Vedado, Ciudad Habana (Cuba); Lopez B, G.M. [CPHR, Calle 20 No. 4113 e/41 y 47, Playa Ciudad Habana (Cuba)]. e-mail: consuelo.varela@infomed.sld.cu

    2006-07-01

    Although, most of the applications in Nuclear Medicine have diagnostic ends, its going enlarging considerably the therapeutic applications. So that the diagnostic accuracy or the therapy effectiveness have not been affected, it becomes indispensable the quality control of the instrumentation, independently of its technological complexity and/or its exploitation period. Before the real lack of phantoms in the institutions, it was created a bank that puts to disposition of all the institutions, the existent phantoms in the country, and those that are going acquired, centralized by the State Control of Medical Equipment Center (CCEEM) and with Web access in its place www.eqmed.sld.cu. Having like base the elaboration of the National Protocol for the Quality Control of the Instrumentation in Nuclear Medicine that keeps in mind the international normative and the own existent conditions, were dictated and established two national regulations and its are being carried out the first audits to the instrumentation quality. These have evidenced the partial realization of the established quality controls in the services, the necessity to make aware as for the fulfillment of the criteria and quality concepts for the instrumentation, as well as the necessity to increase the phantoms number to the bank to guarantee the fulfillment of the Quality Control Programs. (Author)

  12. Virtual control desk for operators training: a case study for a nuclear power plant simulator; Mesa de controle virtual para treinamento de operadores: um estudo de caso para um simulador de usina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aghina, Mauricio Alves da Cunha e

    2009-03-15

    Nuclear Power Plant (NPP) is a facility for electrical energy generation. Because of its high degree of complexity and very rigid norms of security it is extremely necessary that operators are very well trained for the NPP operation. A mistaken operation by a human operator may cause a shutdown of the NPP, incurring in a huge economical damage for the owner and for the population in the case of a electric net black out. To reduce the possibility of a mistaken operation, the NPP usually have a full scope simulator of the plant's control room, which is the physical copy of the original control room. The control of this simulator is a computer program that can generate the equal functioning of the normal one or some scenarios of accidents to train the operators in many abnormal conditions of the plant. A physical copy of the control room has a high cost for its construction, not only of its facilities but also for its physical components. The proposal of this work is to present a project of a virtual simulator with the modeling in 3D stereo of a control room of a given nuclear plant with the same operation functions of the original simulator. This virtual simulator will have a lower cost and serves for pretraining of operators with the intention of making them familiar to the original control room. (author)

  13. A simplified study of public perception in the nuclear field: suggestions for educational campaign for different segments of society; Um estudo simplificado sobre a percepcao publica na area nuclear: sugestoes para campanhas educativas para os diferentes segmentos da sociedade

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Renata Araujo de

    2011-07-01

    During the last years the need for the increase in the electricity energy production as much as in Brazil as in the rest of the world, has raised the tone o the debate about the environmental impacts as a result of these debates, the government and the Non-Governmental Organizations (NGO's) have requested several opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation to the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil as the majority of its power grid is made of hydroelectric plants, a renewable energy source. However, when in that year it occurred a drought, the competent authorities have faced the necessity of developing a plan, the National Energy Plan (PNE2030) which recommends, among other objectives, finalizing the construction of the Angra 3 plant and the implementation Df new nuclear plants in places still to be determined. Even considering the complexity of the subject, this paper presents a field research realized from September 28th, 2010 to October 28th, 2010 of the current level of perception of the Brazilian population, specifically the residents of three cities of Rio de Janeiro, about the nuclear area. As a result of this work, it is suggested how the competent authorities should proceed to reach in an efficient manner, by means of communication campaigns both informative and educational, a greater understanding of the population about the proposed subject. (author)

  14. 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.

  15. 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.

  16. Virtual reality for training of occupationally exposed individuals in nuclear medicine; Realidade virtual para treinamento de indivíduos ocupacionalmente expostos na medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, J.S.; Carvalho, J.B.; Silveira, J.L.; Nascimento, A.C.H.; Mol, A.C.A.; Suita, J.C.; Marins, E.R., E-mail: julianedesacarvalho@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    Applications in virtual environments have been an important tool for education and training of skills in several areas. In Nuclear Medicine Services (NMS), whose environment is susceptible to exposure to ionizing radiation, virtual simulation is a complementary tool to the traditional way of training, able to have the required content by norm, good laboratory practices and radioprotection, interactive form without the exposure of the user. The study consists of the research and unification of recommendations, norms and procedures, collected in the scientific literature and in loco, on the activities of professionals of NMS's radiopharmacy, to define the minimum content for training in order to guide the simulations of a virtual environment.

  17. Development of parallel GPU based algorithms for problems in nuclear area; Desenvolvimento de algoritmos paralelos baseados em GPU para solucao de problemas na area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Adino Americo Heimlich

    2009-07-01

    Graphics Processing Units (GPU) are high performance co-processors intended, originally, to improve the use and quality of computer graphics applications. Since researchers and practitioners realized the potential of using GPU for general purpose, their application has been extended to other fields out of computer graphics scope. The main objective of this work is to evaluate the impact of using GPU in two typical problems of Nuclear area. The neutron transport simulation using Monte Carlo method and solve heat equation in a bi-dimensional domain by finite differences method. To achieve this, we develop parallel algorithms for GPU and CPU in the two problems described above. The comparison showed that the GPU-based approach is faster than the CPU in a computer with two quad core processors, without precision loss. (author)

  18. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne, Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of systematizing

  19. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of

  20. Transference patron for the calibration of activemeters for use in nuclear medicine; Patron de transferencia para la calibracion de activimetros de uso en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Cortes P, A; Garcia D, O C; Ortiz P, I; Becerril V, A [Instituto nacional de Investigaciones Nucleares, Laboratorio de Patrones Radiactivos, Departamento de Metrologia, A.P. 18-1027. C.P. 11801 Mexico D.F. (Mexico)

    2000-07-01

    With the object to improve the calibration service of the activemetersof the users (nuclear medicine centres) so internal as external users at ININ and initiating the establishment of the traceability of the activity measures that carry out in the country, with respect to the National Patron of Nuclear Activity No. ININ-PNM-2, it is initiated the characterization and the performance control of the activemeter make Capintec, model CRC-7BT of the laboratory of Radioactive Patrons (LPR) of the Department of Metrology for to convert it in a transference patron. This characterization and control are based in the sustained review of the activemeter calibration for the I-131, Mo-99 and Sm-153 radioisotopes with activities from 100 mCi until some {mu} Ci and the Tc-99m, In-111, Tl-201, Ga-67, Cs-137, Co-60, and Ba-133 with activities of the range of some {mu} Ci. To verify the good performance of the instrument it was revised the linearity of its scale, the stability of readings, the variation of readings respect of the source position inside the activemeter well and it was determined the calibration factors for each one of the radiosotopes mentionated. The radioactive sources of mid-short life that are used which consist in radioactive solutions of 10 cm{sup 3} contained in polyethylene small bottles of 25 cm{sup 3} elaborated in the LPR and whose activity is measured with respect to the National Patron ININ-PNM-2. The sources of mid-large life are ampoules with 5 cm{sup 3} of radioactive solution, calibrated in activity by the primary laboratory, LNHB (formerly LMRI) of France. (Author)

  1. Experience in training of health personnel for response to radiological and nuclear accidents; Experiencia na capacitacao de profissionais de saude para a resposta a acidentes radiologicos e nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Maurmo, Alexandre M., E-mail: ammaurmo@gmail.com [Fundacao Eletronuclear de Assistencia Medica (CMRI/CTNV/FEAM), Praia Brava, RJ (Brazil). Centro de Medicina das Radiacoes Ionizantes. Centro de Treinamento Prof. Nelson Valverde; Leite, Teresa C.S.B., E-mail: feam@feam-etn.org.br [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Praia Brava, RJ (Brazil). Centro de Informacoes em Radioepidemiologia

    2013-07-01

    Eletronuclear Healthcare Foundation is the Institution responsible for the actions of health response involving ionizing radiation in the area of Nuclear Power Plant Almirante Alvaro Alberto in Angra dos Reis. Because of their specific assignments and references for being in training health manpower in the field of ionizing radiation developed a range of Training Courses for Professionals Area Health to prepare them for Response to Radiological and Nuclear Accidents. Modules are proposed specifically for the professional response of the Technical Level and Higher Level, the level Pre-hospital and hospital. These modules are further divided into specific levels or modules, Basic or Introductory, Intermediate and Advanced. Are applied pretests and post tests to monitor the content of fixing, maintaining a historical series of reviews. Your content is theoretical and practical applications developed in 30 to 48 hours, with simulations (drills) and distribution of educational materials. We already have more than 80 applications training, focusing on internal staff and external to the institution, developing interesting partner with the Armed Forces and Civil Defense. It still maintained a link on the institution seeking access and download over 400 titles on the subject and exchange of information and experiences. For improving the teaching material, the authors launched in 2011 the first manual in Portuguese on the subject with new revised edition in 2013: 'Manual of Medical Actions In Radiological Emergencies'. The results indicate increased knowledge and appropriateness of the themes and the strategy proposed for this activity, demonstrating yet passed that information can be multiplied and meets the growing demand of the country that has hosted and will host international events relevant at QBNRE risk. (author)

  2. Retention capacity of samarium (III) in zircon for it possible use in retaining walls for confinement of nuclear residues; Capacidad de retencion de samario (III) en circon para su posible uso en barreras de contencion para confinamiento de residuos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Garcia G, N

    2006-07-01

    Mexico, as country that produces part of its electric power by nuclear means, should put special emphasis in the development of technologies guided to the sure and long term confinement of the high level nuclear residuals. This work studies the capacity that has the natural zircon to retain to the samarium (III) in solution, by what due, firstly, to characterize the zircon for technical instrumental to determine the purity and characteristic of the mineral in study. The instrumental techniques that were used to carry out the physicochemical characterization were the neutron activation analysis (NAA), the infrared spectroscopy (IS), the thermal gravimetric analysis (TGA), scanning electron microscopy (SEM), transmission electron microscopy (TEM), semiquantitative analysis, dispersive energy spectroscopy (EDS), X-ray diffraction (XRD) and luminescence technique. The characterization of the surface properties carries out by means of the determination of the surface area using the BET multipoint technique, acidity constants, hydration time, the determination of the point of null charge (pH{sub PCN}) and density of surface sites (D{sub s}). The luminescence techniques were useful to determine the optimal point hydration of the zircon and for the quantification of the samarium, for that here intends the development of both analysis techniques. With the adjustment of the titration curves in the FITEQL 4 package the constants of surface acidity in the solid/liquid interface were determined. To the finish of this study it was corroborated that the zircon is a mineral that presents appropriate characteristics to be proposed as a contention barrier for the deep geologic confinement. With regard to the study of adsorption that one carries out the samarium retention it is superior to 90% under the described conditions. This investigation could also be applicable in the confinement of dangerous industrial residuals. (Author)

  3. Formulación de un proyecto de instalación de un ciclotrón para la producción de radioisótopos de uso en medicina nuclear

    OpenAIRE

    Zegarra Mayo, Lourdes Lidania; Zegarra Mayo, Lourdes Lidania

    2012-01-01

    El Instituto Peruano de Energía Nuclear (IPEN) como Organismo rector de la energía nuclear en el país, promueve todas las aplicaciones nucleares pacíficas que conduzcan al desarrollo del país, principalmente en la salud que busca el bienestar del ciudadano peruano. En este marco el IPEN promociona la tecnología nuclear en el ámbito de la medicina nuclear para el acceso a la tomografía por emisión de positrones (PET), técnica de diagnóstico médico que se ha desarrollado rápidamente en el mundo...

  4. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  5. Development of an area monitor for neutrons using solid state nuclear track detector; Desenvolvimento de um monitor de area para neutrons utilizando detector solido de tracos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zahn, G.S.

    1994-12-31

    An area monitor for neutrons composed of the solid state nuclear track detector (SSNTD) Makrofol DE, together with a (n,{alpha}) converter, in the center of a 25 cm diameter polyethylene sphere, is developed. The optimal electrochemical etching conditions for the detection of thermal neutrons by the Makrofol DE using the BN converter are studied, leading to the choice of 55 min, at 30{sup 0} C, under a 44,2 kV.cm{sup -1} electric field with oscillation frequency of 2,0 khz. The response of this system to thermal neutrons, in the optimal conditions, is of 2,76(10)x 10{sup -3} tr/n. Changing from the BN converter to a 2,73(3)g compressed boric acid tablet this value lowers to 3,88(17)x 10{sup -4} tr/n. The performance of the whole monitor in the detection of fast neutrons is examined using the BN converter and neutrons from a {sup 241} Am Be source, with a response of 4,4(2)x 10{sup 3} tr.mSv{sup -1}.cm{sup -2} and operational limits between 7(3){mu}Sv and 5,6(2)mSv. The result of the monitoring of the control room of the IPEN Cyclotron accelerator are also presented as a final test for the viability of the practical use of the monitor. (author). 34 refs, 15 figs, 6 tabs, 1 app.

  6. New recommendations from the IAEA for medical exposures: impact on nuclear medicine in Brazil; Novas recomendacoes da IAEA para exposicoes medicas: impacto em medicina nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Sa, Lidia Vasconcellos de; Kodlulovich, Simone, E-mail: lidia@ird.gov.br, E-mail: simone@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2013-10-01

    An assessment of the current national standards was performed in order to verify compliance with the new recommendations, taking into account the number of available facilities and medical physicists to meet the requirements. It was found that compliance with the requirements of protocol optimization and individualization of doses, as well as the assignment of responsibility shared by all professionals involved were not disclosed. In Brazil, there is no reference levels established as also there is not a government program to obtain them. The functions and responsibilities of the medical physicist in conducting dosimetry individual patient, quality control and acceptance tests of equipment and also the calibration is not defined in the standard. Currently in Brazil there are 31 certified Medical Physicists in Medicine Nuclear power to meet approximately 390 facilities, representing only 8% required. As a member state of the IAEA, the Brazilian rules governed by CNEN is based on BSS-115, must come to terms with the GSR. The concern is now meeting the requirements, especially those relating to patients, since we have established benchmarks and individualized dosimetry. Beyond addition, the number of medical physicists are not enough to show the country's demand. (author)

  7. Contribuição da medicina nuclear para a avaliação dos linfomas

    Directory of Open Access Journals (Sweden)

    Sapienza Marcelo T.

    2001-01-01

    Full Text Available A medicina nuclear permite a caracterização funcional de tecidos, acrescentando dados à avaliação anatômica realizada por outros métodos de imagem, como a tomografia computadorizada, ressonância magnética ou ultra-som. Além do diagnóstico e estadiamento, as informações funcionais fornecidas pela medicina nuclear são particularmente úteis no seguimento e avaliação de resposta terapêutica dos pacientes com linfoma. A presença de massa residual após quimioterapia ou a infiltração de linfonodos de pequenas dimensões são exemplos de situações nas quais a avaliação isolada de características anatômicas é insuficiente. Os principais métodos utilizados são a cintilografia com gálio-67, traçador com alta afinidade por transferrina e receptores de ferro, e os estudos com flúor-deoxiglicose, emissor de pósitron que permite a caracterização do metabolismo de glicose nos tecidos. Outros traçadores, como o tálio-201, sestamibi-Tc99m e octreotide-In111, também são utilizados em menor escala na avaliação dos pacientes com linfoma. Os mecanismos de captação, principais indicações dos estudos, limitações e resultados de literatura serão revistos.

  8. The Text of a Regional Co-operative Agreement for Research, Development and Training related to Nuclear Science and Technology. Latest Status. Declarations/Reservations; Texto de un Acuerdo de Cooperacion Regional Para la Investigacion, el Desarrollo y la Capacitacion en Materia de Ciencias y Tecnologia Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1972-08-18

    The text of a Regional Co-operative Agreement for Research, Development and Training Related to Nuclear Science and Technology between the Agency and Member States is reproduced herein for the information of all Members. Section 9 thereof specifies the Members that may become party to it [Spanish] Para conocimiento de todos los Estados Miembros en el presente documento se transcribe el texto de un Acuerdo de Cooperacion Regional para la investigacion, el desarrollo y la capacitacion en materia de ciencias y tecnologia nucleares entre el Organismo y los Estados Miembros. En la Seccion 9 se especifican los Estados Miembros que pueden ser partes en el Acuerdo.

  9. Data acquisition and management system for a nuclear processes simulator; Sistema de adquisicion y manejo de datos para un simulador de procesos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez M, J A; Santiago C, J [Facultad de Ingenieria, UNAM, Campus Morelos (Mexico)

    2003-07-01

    In the development of this work (Data acquisition and management system for a simulator of nuclear processes (SAMAD)), is important to mention the main modules that involve the operation of the same one. At the beginning it was necessary to contemplate the possible programming languages, as well as the compatibility and handling easiness among them. The used languages to be able to land the contemplated ideas are: C{sup ++}, PHP, HTML, as well as the My SQL database manager. After this it was designed the database (DB), which contains the tables of each one of the components, this according to the enter file type of the RELAP5 code that will be use for each simulation, as well as, tables that will allow us to relate and to maintain the control of the information supplied to the DB. Once created the database is interacting with it through an application program based on PHP (Preprocessor). The application basically consists, in extracting the data from each one of the components to work in that moment, that is to say, to obtain the data of the enter file, as well as, to depurate the data, excluding comments. The preprocessor gives bigger easiness to place the data in the DB. Also, it was developed an graphic interface that allows to register variables to the DB, depending from the unfolding to visualize. Another application that has been implemented is the Data Collector that has as function, to obtain in a direct way the data of the display variables of the RELAP5 code, with the purpose of storing them in the DB, this will be carry out in real time and it was updated in a very small time period. (Author)

  10. Study of indicators aggregation techniques for the selection of a new nuclear reactor for Mexico; Estudio de tecnicas de agregacion de indicadores para la seleccion de un nuevo reactor nuclear para Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Barragan M, A.M.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, 04510 Mexico D.F. (Mexico)]. e-mail: ale_bar_m@yahoo.com.mx

    2007-07-01

    A study on several aggregation techniques that can be used as multi criteria analysis methods, like important part of the methodology developed for the selection of a nuclear reactor for Mexico is described. In an arbitrary way three reactors were selected to be compared, these they are the AP1000 (Advance Passive from 1000 MWe), the PBMR (Pebble Bed Modular Reactor) and the GT-MHR (Gas Turbine Modular Helium). The evaluation approaches were classified in three categories: Economic, Socio-political and of safety and environment. In each category they were defined the more important evaluation indicators and then it was built a matrix with those values of each reactor. The four studied aggregation methods are described: Normalization, Linear deliberation, Fuzzy Logic and AHP (Analytic Hierarchy Process). The well-known aggregation mechanisms are those that are obtained of the lineal deliberation and of the normalization, which have demonstrated to give good results before the simplicity of their use. The fuzzy logic has the advantage that it allows to manage qualitative and quantitative information simultaneously without the aggregation problems that are presented since in a conventional system the semantic pattern on that is based, it is provided by the theory of the diffuse groups that has demonstrated in other areas of the knowledge a better approach to the reality, when admitting that the nature has shades and that the decisions take in function of a wide range of possibilities and of approaches in contradictory occasions or in conflict, all equally worth. The Analytic Hierarchical Process (AHP) that consists in formalizing the intuitive understanding of a multi criteria complex problem, by means of the construction of a hierarchical model that allows the decision agent to structure the problem in visual form, giving him the form of a hierarchy of attributes (global objective of the problem, approaches and alternative). Finally, using the matrix of initiators

  11. Aplicación de Resonancia Magnética Nuclear para la caracterización de fracciones pesadas del petróleo en el proceso de desasfaltado por extracción (DEMEX)

    OpenAIRE

    Avella Moreno, Eliseo

    2011-01-01

    En la literatura, se encontró una gran variedad de criterios para la preparación de muestras y para la adquisición y el procesamiento de los espectros de resonancia magnética nuclear de hidrógeno-1 (RMN 1H) o de carbono-13 (RMN 13C) de petróleos, carbones y sus fracciones. Se definieron 33 nuevos intervalos de integración en los espectros de RMN 1H y 47, en los espectros de RMN 13C. Se unificaron sus límites inferior y superior mediante un tratamiento estadístico realizado con ...

  12. 25 years of monitoring the Waste Management Center of the Almirante Alvaro Alberto Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, O.C; Barboza, E.; Cardoso, S.N.M., E-mail: landocf@eletronuclear.gov.br, E-mail: barboza@eletronuclear.gov.br, E-mail: sergion@eletronuclear.gov.br [Eletrobras Eletronuclear S.A (ELETONUCLEAR), Paraty, RJ (Brazil). Lab. de Monitoracao Ambiental

    2013-07-01

    The goal of this paper is to present an assessment of 25 years of monitoring of the environment around the Waste Management Center (WMC) of the Almirante Alvaro Alberto Nuclear Power Station (AAANPS) since 1986 until 2011. The Environmental Monitoring Laboratory (EML) has, for purposes, to monitor the environment around the station to verify if there's a potential impact caused by the operation of the two units and to verify the dose rate levels around the waste deposits. The WMC is located in an area belonging to the AAANPS and receive solid waste of low and medium activities from Angra 1 NPP. The waste generated from Angra 2 NPP is stored inside the unit. The EML monitors the environment around the WMC to determine the environmental dose rate. The monitoring is made by direct measurement of the radiation using thermoluminescent dosimeters (TLD). Nowadays, the TLD are installed, at this time, in 6 points at the boundaries of WMC and are changed monthly. The locations of these points were already changed several times to allow the construction of new buildings. The constitution of the TLD are 4 crystals, being 3 crystals of Calcium Sulphate doped with Thulium (CaSO{sub 4}:Tm) with 3 shields and 1 crystal of Lithium Borate doped with Copper (Li{sub 2}B{sub 4}O{sub 7}:Cu) without shield. The results of the TLD measurements are normalized to a period of 30 days to compensate accidental statistical variations of the dose rates. The results, in these 25 years, show that the external area of the WMC is a supervised area, following the Norm CNEN-NN-3.01 - 'Diretrizes Basicas de Protecao Radiologica' - with access permitted only for authorized people. (author)

  13. 25 years of monitoring the Waste Management Center of the Almirante Alvaro Alberto Nuclear Power Station

    International Nuclear Information System (INIS)

    Ferreira, O.C; Barboza, E.; Cardoso, S.N.M.

    2013-01-01

    The goal of this paper is to present an assessment of 25 years of monitoring of the environment around the Waste Management Center (WMC) of the Almirante Alvaro Alberto Nuclear Power Station (AAANPS) since 1986 until 2011. The Environmental Monitoring Laboratory (EML) has, for purposes, to monitor the environment around the station to verify if there's a potential impact caused by the operation of the two units and to verify the dose rate levels around the waste deposits. The WMC is located in an area belonging to the AAANPS and receive solid waste of low and medium activities from Angra 1 NPP. The waste generated from Angra 2 NPP is stored inside the unit. The EML monitors the environment around the WMC to determine the environmental dose rate. The monitoring is made by direct measurement of the radiation using thermoluminescent dosimeters (TLD). Nowadays, the TLD are installed, at this time, in 6 points at the boundaries of WMC and are changed monthly. The locations of these points were already changed several times to allow the construction of new buildings. The constitution of the TLD are 4 crystals, being 3 crystals of Calcium Sulphate doped with Thulium (CaSO 4 :Tm) with 3 shields and 1 crystal of Lithium Borate doped with Copper (Li 2 B 4 O 7 :Cu) without shield. The results of the TLD measurements are normalized to a period of 30 days to compensate accidental statistical variations of the dose rates. The results, in these 25 years, show that the external area of the WMC is a supervised area, following the Norm CNEN-NN-3.01 - 'Diretrizes Basicas de Protecao Radiologica' - with access permitted only for authorized people. (author)

  14. Design considerations for pressure surge protection for marine terminals, based on real case; Consideracoes de projeto para sistemas de protecao contra surtos de pressao em terminais maritimos existentes, a partir de caso real

    Energy Technology Data Exchange (ETDEWEB)

    Allevato, Monica; Miranda, Jades Marques de [PETROBRAS, Rio de Janeiro, RJ (Brazil); Paula, Jair dos Santos de [PETROBRAS Transporte S.A. (TRANSPETRO), Rio de Janeiro, RJ (Brazil)

    2005-07-01

    Upon the increasing of liquid pumping capacity in maritime terminals and with the developing of quick blockage systems in hydrocarbon ship tankers, is also high the concern with the event of a surge pressure that could result in risky situations, with possible financial damages and environmental accidents of large proportions. On this scenario, the design of hydraulic transient anti-surge systems during crude oil and its products loading or offloading in terminal and tankers, is very important and it involves much more than simple numerical simulation or direct application of theory that takes into account only hydraulic aspects of the system, depending on solid design basis, on practical experience for design and operations and on the knowledge of experts in the field. This paper presents a quick historical background of the national installations, and discuss the main steps for designing hydraulic transient safety systems, taking into account an existing system as guideline for the particularities during the field collection data, the simplification for a representative and efficient numerical modeling and definition of design criteria. This paper discuss also, some of the restrictions of available protection equipment, when applied to existing maritime terminals. (author)

  15. Radiation beans characterization and implantation for study of lead equivalent individual protection device used in radiodiagnostic practices; Caracterizacao e implantacao de feixes de radiacao para estudo de dispositivos de protecao individual com equivalencia em chumbo utilizados em praticas de radiodiagnostico

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Leslie Silva

    2004-07-01

    The protective shielding (IPC) must be used by occupationally exposed professionals, patients and volunteers, in order to optimize the doses who receive due to radiological practices. International and national norms establish the methodology to be adopted for determination of the IPC attenuation. In this work, the IPC had been submitted to X-rays beams with known characteristics, standardized for determination of their attenuation equivalent thickness by comparison to an experimental lead attenuation slope. This comparison technique allowed insurance estimative of the IPC attenuation equivalent thickness in mm of lead. Thus, it was possible to verify the conformity of the attenuation equivalent thickness determined experimentally and the value of the thickness indicated by the manufacturer. To carry out this work, it was necessary the implementation of experimental setups stated in the specifics norms, the study of the X-rays beams original features and the determination of combined additional filters, in order to allow the X-ray equipment used operates in compliance with Norm IEC 61331-1 IEC. The radiation quality selected is characterized by a 100 kV voltage and a 0.25 mm of copper overall filtration. The implementation of this radiation quality it was carried through of its first and second HVL (Half Value Layer). Thus, a methodology according to the international Norms has been implemented in the laboratory. The results of the present work provide suitable and useful information about radiation beams features related to the determination techniques of the attenuation properties. Once implemented the procedures for conformity evaluation of the protection devices, it will be possible to carry out specific quality control tests, which will be helpful to manufacturers, customers, as well as authorities in the radiological protection and health areas. (author)

  16. Main radiation protection actions for medical personnel as primary responders front of an event with radiological dispersive device; Principais acoes de protecao radiologica para equipe medica como primeiros respondedores frente a um evento com dispositivo de dispersao radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Duque, Hildanielle Ramos

    2015-07-01

    After the terrorist attack in New York, USA, in 2001, there was a worldwide concern about possible attacks using radioactive material in conventional detonators, called as Radiological Dispersal Device (RDD) or 'dirty bomb'. Several studies have been and are being made to form a global knowledge about this type of event. As until now, fortunately, there has not been an event with RDD, the Goiania Radiological Accident in Brazil, 1987, is used as a reference for decision-making. Several teams with technical experts should act in an event with RDD, but the medical staffs who respond quickly to the event must be properly protected from the harmful effects of radiation. Based on the radiological protection experts performance during the Goiania accident and the knowledge from lessons learned of many radiological accidents worldwide, this work presents an adaptation of the radiation protection actions for an event with RDD that helps a medical team as primary responders. The following aspects are presented: the problem of radioactive contamination from the explosion of the device in underground environment, the actions of the first responders and evaluation of health radiation effects. This work was based on specialized articles and papers about radiological accidents and RDD; as well as personal communication and academic information of the Institute of Radiation Protection and Dosimetry. The radiation protection actions, adapted to a terrorist attack event with RDD, have as a scenario a subway station in the capital. The main results are: the use of the basic radiation protection principle of time because there is no condition to take care of a patient keeping distance or using a shielding; the use of full appropriate protection cloths for contaminating materials ensuring the physical safety of professionals, and the medical team monitoring at the end of a medical procedure, checking for surface contamination. The main conclusion is that all medical actions as primary responders must be followed up by radiation protection specialists. (author)

  17. Informatization of radiological protection:new tools of information dissemination and sharing knowledge; Informatizacao dos programas de protecao radiologica: novas ferramentas para disseminacao da informacao e compartilhamento do conhecimento

    Energy Technology Data Exchange (ETDEWEB)

    Levy, Denise S., E-mail: denise@omiccron.com.br [Omiccron Programacao Grafica, Atibaia, SP (Brazil); Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Sordi, Gian Maria A.A., E-mail: gian@atomo.com.br [ATOMO - Radioprotecao e Seguranca Nuclear S/C Ltda, Sao Paulo, SP (Brazil); Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    This project aims the informatization of the radiological protection optimization programs in a single system in order to offer unified programs and inter-related information in Portuguese, providing Brazilian radioactive facilities a complete repository for research, consultation and information. In order to meet both national and international recommendations within the scope of this work, we conducted a comprehensive job of perception about each program contents as well as its real dimension, identifying and detailing the vital parts of programs. The content includes concepts, definitions and theory in addition to the optimization programs, help decision making techniques, information related to protection costs, radiation doses and detriment. The content allows to answer to every question when an optimization program is elaborated, according to decision maker's specific situation. For dimensioning the work of informatization and developing the WEB platform according to the needs of the target public profile, we have conducted an extensive research regarding the possibilities of Information and Communication Technology access in companies throughout the country, which allowed to define the best interfaces tools and resources. The servers processing power added to the technology of relational databases allow to integrate information from different sources, enabling complex queries with reduced response time. The project was implemented in a web environment, using the Web 2.0 tools and resources that allow the entire organizational structure, that would enable the inter-relationships and joints needed for proper use of information technology in radiological protection. This project uses the combination of multiple technologies, maximizing the resources available in each one of them in order to achieve our goals. The investigation of the usage profile for five months enabled important data that suggest new possibilities for the development of computerization of other radiation protection programs. According to the results of this project, we intend to lead a further research work and complete the informatization system. (author)

  18. Simulator protection, control and supervision systems: a tool for empowerment of operation and maintenance; Simulador de sistemas de protecao, controle e supervisao: uma ferramenta para capacitacao da operacao e manutencao

    Energy Technology Data Exchange (ETDEWEB)

    Moutinho, J.A.P. [Centrais Eletricas do Norte do Brasil S.A. (ELETRONORTE), Belem, PA (Brazil). Regional de Transmissao do Para. Div. de Engenharia de Automacao, Protecao e Medicao], E-mail: beck@eln.gov.br

    2009-07-01

    The use of digital technology in protection, control and supervision equipment has resulted in the electricity sector companies, new behavior in electrical management systems given his versatility in the implementation of protection system as well as cost reduction in traffic information of power equipment to the man-machine interfaces (MMI) to the system operator. With the capabilities of digital technology it is possible provide simulated systems to allow the training of operations teams of the system, providing resources for development for engineers and maintenance technicians, and above all offer platform for analysis of events in the electrical system. This paper presents the development of a simulator protective relays, control and supervision applied to ELETRONORTE substations. The simulator of protective relays, control and supervision consists of information reproduction in the operator's MMI of the electrical system originated in the units of protection, control and supervision. This information is developed from a software that has the same communication protocol with the original units.

  19. The industrial radiography service in Brazil concerning to the radiation protection aspect; O servico de radiografia industrial no Brasil sob o aspecto da protecao radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Martins, M M

    1994-12-31

    A study about the industrial radiography situation in Brazil, concerning to the radiation protection aspects is shown. With this purpose it was made an inventory, with utilization of the file of facilities officially registered in industrial application from Brazilian Nuclear Energy Commission (CNEN). It was evaluated the quantity of accelerators, radiation monitors and radiation workers (health physics, operator). As quality and performance indicators of radiation protection the mean doses and the collective doses were used, and their variation from 1987 to 1990. As deficiency signals of radiological protection programs and procedures were utilized the 175 abnormal event occurred (radiological accident and emergency situation) from 1976 to 1992, after an analysis of their causes. The results showed that, for around 2000 monitored workers, the mean dose equivalent was between 0.83 to 2.70 mSv, and the collective dose, between 1.54 and 6.18 Sv.man, from 1987 to 1990. In this period, it was verified a tendency for reduction of means dose and collective dose values. It indicates a possible improvement of radiation protection services or an influence of economical situation of the country. From 175 abnormal events analysed, 456 persons were exposed, with 7.2% of them receiving doses above 50 mSv. These results were compared with those from others countries, such as United Kingdom and united States. (author). 76 refs, 16 figs, 24 tabs.

  20. Atomic Transport Problems of Interest in Nuclear Systems; Problemes de Transport Atomique Presentant un Interet dans les Systemes Nucleaires; Problemy perenosa atomov, predstavlyayushchie interes v yadernykh sistemakh; Problemas de Transporte Atomico de Interes para la Ingenieria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lundy, T. S.; Winslow, F. R. [Oak Ridge National Laboratory, TN (United States)

    1966-02-15

    sur la diffusion dans un metal. Leurs resultats sont en bon accord avec les calculs theoriques fondes sur un modele de 1)annihilation de l'excedent de defauts ponctuels (lacunes et interstices) par trois mecanismes, savoir la migration vers des puits fixes dont la distribution est homogene tels que les dislocations, la migration vers une surface libre et la recombinaison de defauts. (author) [Spanish] Se analizan en la memoria varios problemas encontrados al aplicar los datos basicos sobre difusion a sistemas de interes practico para la ingenierfa nuclear. Estos problemas se refieren a experimentos de difusion isotermica, difusion por gradiente termico y efectos de la radiacion sobre los procesos de difusion. La mayor parte de la informacion fidedigna sobre la difusion en solidos proviene de casos donde no existe, en esencia, gradiente alguno de concentracion de las especies que se difunden. Los sistemas que interesan a los ingenieros nucleares, en cambio, presentan casi invariablemente gradientes de concentracion. Asf, pues, para evaluarlos coeficientes adecuados es necesario contar con un conocimiento practico de la relacion existente entre los coeficientes de autodifusiOn y de difusion quimica. Ademas, es preciso conocer los coeficientes de actividad termodinamica como funciones de la composicion. Recientemente se ha demostrado sin lugar a dudas que el uso indiscriminado de una expresion del tipo de la de Arrhenius para describir la manera en que los datos de difusion dependen de la temperatura, puede introducir graves errores en el calculo de los coeficientes de difusion. Se analizan en la memoria las consecuencias de ese hecho, haciendo especial hincapie en los sistemas cubicos centrados en el cuerpo/ del tipo refractario. Los autores han estudiado teorica y experimentalmente el efecto de un gradiente termico sobre la redistribucion de impurezas sustitutivas en un metal. Ese trabajo ha contribuido a un mejor conocimiento de la importancia de este efecto en los

  1. The Text of the Agreement between Iran and the Agency for the Application of Safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons; Texto Del Acuerdo Concertado Entre El Iran Y El Organismo Para La Aplicacion De Salvaguardias En Relacion Con El Tratado Sobre La No Proliferacion De Las Armas Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-12-17

    The text of the agreement between Iran and the 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 [Spanish] Para informacion de todos los Estados Miembros, en el presente documento se trans cribe el texto del Acuerdo concertado entre el Iran y el Organismo para la aplicacion de salvaguardias en relacion con el Tratado sobre la no proliferacion de las armas nucle ares.

  2. 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)

  3. Caracterização do gel polimérico MAGIC-f para aplicação em medicina nuclear utilizando imagens de ressonância magnética

    OpenAIRE

    Marcelo Menna Barreto Schwarcke

    2013-01-01

    Este trabalho visa aprimorar e tornar mais precisa a utilização do dosímetro gel polimérico MAGIC-f no estudo da distribuição de dose para fonte radioativas utilizadas na terapia e diagnóstico em medicina nuclear. Para isso foram avaliados os parâmetros de leitura do gel em equipamentos de ressonância magnética e sua resposta quando comparado a resultados obtidos através da utilização do código PENELOPE de simulação Monte Carlo. Dentre as incertezas observadas no processo global da utilização...

  4. Sistema de medición, control y compensación activa para ciclado de campo magnético en aplicaciones de resonancia magnética nuclear

    OpenAIRE

    Forte, Guillermo Omar

    2013-01-01

    Tesis (DCI)--FCEFN-UNC, 2013 Analiza aspectos de la instrumentación asociada a la técnica de Resonancia Magnética Nuclear (RMN) con Ciclado Rápido de Campo Magnético (FFC, por sus siglas en inglés), los que afectan directamente la calidad de las mediciones realizadas. Se implementó un método para la corrección estática de la dependencia espacial del campo magnético generado por el electroimán principal del sistema, dentro de un volúmen determinado.

  5. DISEÑO CONCEPTUAL DE UN SISTEMA CONTROLADO POR UN ACELERADOR PARA TRANSMUTACIÓN DE RESIDUOS NUCLEARES Y APLICACIONES ENERGÉTICAS

    OpenAIRE

    GARCIA FAJARDO, LAURA

    2012-01-01

    Las posibilidades de desarrollo de la energía nuclear aumentan considerablemente con el incremento de la demanda energética mundial. Sin embargo, el manejo de los residuos provenientes del combustible nuclear gastado de las plantas nucleares convencionales es actualmente uno de los principales problemas que enfrenta el uso de esta fuente de energía. El objetivo del presente trabajo consistió en realizar el diseño conceptual del TADSEA (Transmutation Advanced Device for Sustainable Energy Appl...

  6. Diseño y evaluación de un procedimiento on-line para la biorremediación de aguas radiactivas en centrales nucleares

    OpenAIRE

    Belinchón Vergara, Julio Angel

    2016-01-01

    Recientemente se ha demostrado la existencia de microorganismos en las piscinas de almacenamiento de combustible nuclear gastado en las centrales nucleares utilizando técnicas convencionales de cultivo en el laboratorio. Estudios posteriores han puesto de manifiesto que los microorganismos presentes eran capaces de colonizar las paredes de acero inoxidable de las piscinas formando biopelículas. Adicionalmente se ha observado la capacidad de estas biopelículas de retener radionúclidos, lo que ...

  7. Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine; Metodologia para a implementacao de uma rede de referencia para metrologia de radiofarmacos no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joyra Amaral dos

    2004-01-15

    The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides {sup 67}Ga, {sup 123}I, {sup 131}I,{sup 99m}Tc and {sup 210}Tl were evaluated and {sup 201}TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

  8. A geographic information system and multi criteria analysis method for site selection of spent nuclear fuel disposal; Metodologia baseada em sistemas de informacao geografica e analise multicriterio para a selecao de areas para a construcao de um repositorio para o combustivel nuclear usado

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Vivian Borges

    2009-07-01

    This thesis aims to develop a site selection methodology for the construction of final repository for the spent nuclear fuel disposal, by using geographic information systems (GIS) and multi-criteria decision analysis. Decision making processes of this kind are often complex, given the great number of space parameters to consider and also the typically conflicting opinions of the diverse stake holders. By using GIS, data from different space parameters can be quickly and reliably stored, treated and analyzed. Multi-criteria techniques allow for the incorporation of different stake holders' opinions. These tools, when jointly used, allow for the decision process to be more transparent, quick and reliable. The method developed was applied to the particular case of the state of Rio de Janeiro. Weights obtained from an expert panel and also by using the Hierarchical Analysis Method and cartographic data were combined in the GIS. The application showed that it is possible not only to select and classify areas as to their aptness for the proposed objective, but also to exclude those clearly inadequate areas, thus optimizing the selection process by reducing the search space and consequently minimizing costs and the time spent in the search. (author)

  9. New Technologies for a sustainable nuclear energy and your effect in the management of radioactive waste; Nuevas tecnologias para una energia nuclear sostenible y su efecto en la gestion de residuos radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Romero, E. M.

    2009-07-01

    The probable worldwide increase and distribution of nuclear energy for electricity generation, replacing partially fossil fuels, is promoting the development of technologies that foster its long-term sustain ability. Fast neutron system, combined with closed fuel cycles, are the key elements for the sustain ability. When combined, they can provide a significant reduction on the final high level wastes of the nuclear generation. In particular, Partitioning and Transmutation of actinides would allow the reduction of the nuclear wastes radiotoxicity, their content in fissile material and the heat load to the repository. (Author) 8 refs.

  10. 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...

  11. National Report presented by the Mexican United States to satisfy the compromises of the Nuclear Safety Convention; Informe Nacional que presentan los Estados Unidos Mexicanos para satisfacer los compromisos de la Convencion de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    National Commission of Nuclear Safety and Safeguards, Mexico City (Mexico); Federal Commission for Electricity, Mexico City (Mexico)

    1998-12-31

    In order to satisfy to the compromises derived of the ratification by part of the Mexican Government for the Nuclear Safety Convention it is presented this National Report which is based on the directives proposed as a result of the preparatory meetings held in the IAEA Headquarters in the city of Vienna, Austria. This National Report represents a document summary and activities realized at present in relation with the only nuclear facility in Mexico: the Nuclear Power Plant in Laguna Verde, Veracruz. This report consists of two parts: In the first one it is described how have been satisfied each one of the compromises. The second one talks about the Laws and Regulations on nuclear activities in the country. (Author)

  12. National Report presented by the Mexican United States to satisfy the compromises of the Nuclear Safety Convention; Informe Nacional que presentan los Estados Unidos Mexicanos para satisfacer los compromisos de la Convencion de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    National Commission of Nuclear Safety and Safeguards, Mexico City (Mexico); Federal Commission for Electricity, Mexico City (Mexico)

    1999-12-31

    In order to satisfy to the compromises derived of the ratification by part of the Mexican Government for the Nuclear Safety Convention it is presented this National Report which is based on the directives proposed as a result of the preparatory meetings held in the IAEA Headquarters in the city of Vienna, Austria. This National Report represents a document summary and activities realized at present in relation with the only nuclear facility in Mexico: the Nuclear Power Plant in Laguna Verde, Veracruz. This report consists of two parts: In the first one it is described how have been satisfied each one of the compromises. The second one talks about the Laws and Regulations on nuclear activities in the country. (Author)

  13. Methodology for conducting baseline environmental studies, applied to the environments of two nuclear sites; Metodologia para la realizacion de estudios de estado basico ambiental, aplicada a los entornos de dos emplazamientos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez Baco, L.; Yague Alvarez, F.

    2012-07-01

    The methodology described can understand and document the characteristics of form geo referenced environmental baseline condition of the surroundings of nuclear power plants, covering the needs in this regard made by the legislation of environmental responsibility.

  14. IAEA Capacity Building in Nuclear Techniques for Environmental Sustainability; Asistencia del OIE A en la creacion de capacidad para el empleo de tecnicas nucleares en aras de la sostenibilidad ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Dixit, Aabha [International Atomic Energy Agency, Division of Public Information, Vienna (Austria)

    2013-09-15

    The IAEA helps Member States use nuclear technology for a broad range of applications: from generating electricity to increasing food production, from fighting cancer to managing freshwater resources and protecting coastal areas and the ocean. Assistance provided through IAEA capacity building projects addresses specific national and regional problems. Expertise in the application of nuclear technology and knowledge of good practices are transferred via training activities, information exchange, coordinated research projects and the technical cooperation programme.

  15. Cooperação Internacional para o Desenvolvimento em Ciência e Tecnologia: A Participação Brasileira na Organização Européia para Pesquisa Nuclear (CERN

    Directory of Open Access Journals (Sweden)

    Rafael Pinto Duarte

    2008-12-01

    Full Text Available This work proposes a different approach of International Cooperation on the Brazilian scientific and technological (S&T development process, based on the case of the cooperation among Brazil and the European Organization for Nuclear Research (CERN. The studies lead to a suggestion of a new strategic approach of a system beginning starting at activities of international S&T interchange and collaborations as initial stage that lead to International Cooperation, seen as the only one capable of directly create S&T development. The case of the Brazilian activities at CERN shows that International Cooperation generates S&T development only with long term assured financial and institutional arrangements between Universities and Industries, supported by government policies and programs. The results point to the assumption that International Cooperation is an essential element for elaboration and execution of public policies that aim national development on science and technology.

  16. Economic evaluation of application of nuclear power, fossil and biomass for seawater desalination in the case of Mexico; Evaluacion economica de la aplicacion de la potencia nuclear, fosil y biomasa para desalar agua de mar en el caso de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Palacios G, N.; Gomez A, R.; Vazquez R, R.; Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Depto. de Ingenieria de Procesos e Hidraulica, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)], e-mail: rvr@xanum.uam.mx

    2009-10-15

    In this work the fresh water production costs are compared on base to the seawater desalination, taking advantage of the heat or the electricity generated by means of the nuclear fission, the energy fossil result of the combustion of natural gas, fuel oil and coal, as well as the electricity generated by the bio-fuels combustion. The option of generating electricity and at the same time to produce drinking water is discussed. Using electricity, the best combination of technologies as for costs, the option more cheap, it is the distillation by means of a distillation combined process of multiple effects combined with reverse osmosis using nuclear energy coming from a gas cooled reactor using a cycle Brayton. While using direct heat was as the option more economic the use of nuclear vapor of low pressure exchanging heat in a vapor generator of low pressure, as energy source of a flash distillation process of several stages. In this last case, the energy source or nuclear vapor will be the result of the operation of a nuclear power plant cooled and moderate with water and operating in a cycle Rankine. (Author)

  17. APMO: UN PROGRAMA COMPUTACIONAL PARA EL ESTUDIO DE EFECTOS CUÁNTICOS NUCLEARES MEDIANTE LA TEORÍA DEL ORBITAL MOLECULAR ELECTRÓNICO Y NO ELECTRÓNICO.

    Directory of Open Access Journals (Sweden)

    Sergio González

    2009-04-01

    Full Text Available Con el fin de estudiar teóricamente fenómenos en donde los núcleos atómicos presentan comportamiento cuántico, hemos desarrollado el paquete computacional APMO (Any-Particle Molecular Orbital. Este implementa el método de orbitales moleculares nucleares y electrónicos (OMNE a un nivel de teoría Hartree-Fock (HF, en el que tanto núcleos como electrones se representan como funciones de onda.Para comprobar la correcta implementación del método, se realizaron  cálculos de estructura electrónica regular y núcleo-electrónica de las moléculas H2 y LiH. Las componentes de energía calculadas siguen las  tendencias y están en el mismo orden de magnitud de cálculos similares reportados en la literatura.A diferencia de otros paquetes que implementan el método OMNE, el nuestro fué diseñado para estudiar sistemas con cualquier número de especies cuánticas. 

  18. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR; BUTREN-RC un sistema hibrido para la optimizacion de recargas de combustible nuclear en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J.; Castillo M, J.A. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico); Valle G, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  19. 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)

  20. Application of digital solutions to help the safe and efficient operation of nuclear power plants; Aplicacion de soluciones digitales para la ayuda a la operacion segura y eficiente de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ortega P, F.; Fernandez F, S., E-mail: fortega@tecnatom.es [Tecnatom S. A., Av. Montes de Oca 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

    2017-09-15

    In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

  1. SIMPRO, a practical tool for training the staff of Laguna Verde nuclear power plant; El SIMPRO, una herramienta practica para la capacitacion y entrenamiento del personal de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valdez, Guillermo Omar; Gomez Camargo, Octavio; Castelo Cuevas, Luis; Vazquez Bustos, Jesus [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2012-06-22

    Laguna Verde Nuclear Power Plant (LVNPP) has implemented a real physical model, which represents several parts of a simplified version of its process. This development has proved to be very useful to improve the compliance with training programs and staff training maintenance in the different disciplines of engineering. Such programs are required by regulations and standards applicable for Nuclear Power Plants (NPP), so that the personnel working in these facilities can be able to respond on time to any contingency that might arise. This paper outlines the creation of the real physical model, how it is integrated and some of the practices that can be performed on this model. [Spanish] La Central Nucleoelectrica de Laguna Verde ha implementado un modelo fisico real que representa varias partes de una version simplificada de su proceso. Este desarrollo ha demostrado ser muy util para mejorar el cumplimiento de programas de adiestramiento, incluidos los del personal de mantenimiento, en diferentes disciplinas de ingenieria. Dichos programas son requeridos por las regulaciones y normas aplicables a las centrales nucleoelectricas, de manera que el personal que trabaja en estas instalaciones pueda ser capaz de responder oportunamente a cualquier contingencia que pudiera surgir. Este articulo describe la creacion del modelo fisico real, como se integra y algunas de las practicas que pueden llevarse a cabo con el.

  2. Status report about the works for the start up of the RA-0 `zero power` nuclear reactor at the Cordoba National University; Estado actual de avance de las tareas para la nueva puesta en marcha del reactor nuclear RA-0 en la Universidad Nacional de Cordoba

    Energy Technology Data Exchange (ETDEWEB)

    Martin, H R; Carballido, C; Oliveras, T

    1992-12-31

    After two years of works at the Cordoba National University for the new start-up of the RA-0 `zero power` nuclear reactor, the results obtained are herein presented. Starting with practically null infrastructure at the beginning, specially in human resources and instrumentation of the reactor, the objectives can be considered satisfactory. The training in work of the future operational staff, the design and the construction of the instrumentation and the fitting of the installations are the principal items described in this paper. An special attention is devoted to the insertion of this type of installation in the university organization, usually not prepared for the quality and control activities, which is necessarily considered in these type of works. (Author). [Espanol] Luego de aproximadamente dos anos de trabajo para la nueva puesta en marcha del REACTOR NUCLEAR RA-0, se han alcanzado los resultados presentados en este trabajo. Partiendo de una infraestructura practicamente inexistente en cuanto a recursos humanos y estado de las instalaciones, los avances logrados son significativos. Comenzando por la capacitacion y el entrenamiento del futuro personal de operacion y pasando por la adecuacion de los equipos y componentes, hasta la confeccion de la documentacion mandatoria, se muestran los aspectos mas destacables de los trabajos realizados. Una atencion especial se dedica a la insercion de una instalacion de este tipo en el ambito universitario, el cual por sus particulares caracteristicas, ha debido ser tenido en cuenta permanentemente para la futura operacion de las instalaciones. (Autor).

  3. 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)

  4. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production; UPVAPOR: Aplicacion informatica para el analisis de resultados de produccion en Central Nuclear Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-07-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  5. Thermodynamic study of residual heat from a high temperature nuclear reactor to analyze its viability in cogeneration processes; Estudio termodinamico del calor residual de un reactor nuclear de alta temperatura para analizar su viabilidad en procesos de cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Santillan R, A.; Valle H, J.; Escalante, J. A., E-mail: santillanaura@gmail.com [Universidad Politecnica Metropolitana de Hidalgo, Boulevard acceso a Tolcayuca 1009, Ex-Hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2015-09-15

    In this paper the thermodynamic study of a nuclear power plant of high temperature at gas turbine (GTHTR300) is presented for estimating the exploitable waste heat in a process of desalination of seawater. One of the most studied and viable sustainable energy for the production of electricity, without the emission of greenhouse gases, is the nuclear energy. The fourth generation nuclear power plants have greater advantages than those currently installed plants; these advantages have to do with security, increased efficiencies and feasibility to be coupled to electrical cogeneration processes. In this paper the thermodynamic study of a nuclear power plant type GTHTR300 is realized, which is selected by greater efficiencies and have optimal conditions for use in electrical cogeneration processes due to high operating temperatures, which are between 700 and 950 degrees Celsius. The aim of the study is to determine the heat losses and the work done at each stage of the system, determining where they are the greatest losses and analyzing in that processes can be taken advantage. Based on the study was appointed that most of the energy losses are in form of heat in the coolers and usually this is emitted into the atmosphere without being used. From the results a process of desalination of seawater as electrical cogeneration process is proposed. This paper contains a brief description of the operation of the nuclear power plant, focusing on operation conditions and thermodynamic characteristics for the implementation of electrical cogeneration process, a thermodynamic analysis based on mass and energy balance was developed. The results allow quantifying the losses of thermal energy and determining the optimal section for coupling of the reactor with the desalination process, seeking to have a great overall efficiency. (Author)

  6. 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.

  7. The political economics of the permanent war and the political economics of the nuclear war. Strategic approaches for Latin America; La economia politica de la guerra permanente y la economia politica de la guerra nuclear. Aproximaciones estrategicas para America Latina

    Energy Technology Data Exchange (ETDEWEB)

    Gomez L, I.I

    2005-07-01

    This work treats on the hypothesis that the American imperialism uses its nuclear arsenal for reforming geographical spaces that allow him to impel its economic development in the context of the progressive exhaustion of the natural resources of the planet and of the ferocious dispute for market niches and investment destinations, and like the political and military decisions crawl to the different scenarios of economic competition. In the chapter 1 it is insinuated like has been reproduced the Warlike-industrial Complex (CBI) American from the second world postwar period until the present time in the idea of explaining like it is that it is valorized to the capital in scale enlarged starting from the denominated sector producing of destruction means and understanding that the system specifically capitalist is a system where continually the is destroyed previously taken place to manufacture a new merchandise in a luck of creative destruction. In the chapter 2, the topic of the specific contradictions of the CBI is approached that disable him to be the tip of lance of the world imperialism. The chapter 3 try on the productive linkages in the production of nuclear bombs, as well as in the production of the vectors of nuclear transportation and on the implications derived for the world security of the different industries associated to the nuclear energy (as the petroleum, the electricity, the natural gas) and to the transportation vectors of these locating which you/they are the different States where the world supremacy is disputed and that they have like one of its so many negotiation-confrontation letters its nuclear strategic arsenals. What is looked for in a thermonuclear war is the enemy's total elimination, from their offensive capacity, their defensive capacity, until their supplies, their reservations, etc., with the result that the chapters 4 and 5 of this thesis are presented to offer a better understanding that they mean the nuclear arsenals in the

  8. Introduction of fuel GE14 in the nuclear power plant of Laguna Verde for the extended increase of power; Introduccion del combustible GE14 en la central nuclear Laguna Verde para el aumento de potencia extendido

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A. F.; Cardenas J, J. B.; Contreras C, P. [CFE, Central Nuclear Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5 (Mexico)]. e-mail: natividad.hernandez@cfe.gob.mx

    2008-07-01

    The project of extended increase of power responds to a necessity of electrical energy in the country, increasing the thermal exit of the reactors of the nuclear power plant of Laguna Verde of 2027 MWt to 2317 MWt. In order to support this transition, changes will make in the configuration of the reactor core and in the operation strategies of the cycle, also they will take initiatives to optimize the economy in fuel cycle. At present in both reactors of the nuclear plant of Laguna Verde fuel GE12 is used. The fuel GE14 presents displays with respect to the GE12, some improvements in the mechanical design and consequently in its performance generally. Between these improvements we can mention: 1. Spacers of high performance. 2. Shielding with barrier. 3. Filter for sweepings {sup d}ebris{sup a}nd 4. Fuel rods of minor partial length. The management of nuclear power plants has decided to introduce the use of fuel GE14 in Laguna Verde in the reload 14 for Unit 1 and of the reload 10 for Unit 2. The process of new introduction fuel GE14 consists of two stages, first consists on subjecting the one new design of fuel to the regulator organism in the USA: Nuclear Regulatory Commission, in Mexico the design must be analyzed and authorized by the National Commission of Nuclear Safety and Safeguards, for its approval of generic form, by means of the demonstration of the fulfillment with the amendment 22 of GESTAR II, the second stage includes the specific analyses of plant to justify the use of the new fuel design in a reload core. The nuclear plant of Laguna Verde would use some of the results of the security analyses that have been realized for the project of extended increase of power with fuel GE14, to document the specific analyses of plant with the new fuel design. The result of the analyses indicates that the reload lots are increased of 116-120 assemblies in present conditions (2027 MWt) to 140-148 assemblies in conditions of extended increase of power (2317 MWt

  9. Comparative analysis to determine asphalt density and content, using nuclear and traditional methods; Analisis comparativo para la determinacion de densidad y contenido de asfalto, mediante metodo nuclear y metodo tradicional

    Energy Technology Data Exchange (ETDEWEB)

    Margffoy S, F R; Robayo S, A M

    1989-07-01

    Quality control for flex pavement construction in Colombia for asphaltic mix, as well as for granular and granular sub base layers is made by means of methods that does not guarantee the quality of the job, due to the difficult execution of tests, which impede more to be done or due to inherent problems of the test process. Thanks to the inherent characteristics and advantages of nuclear techniques, those become the optimal alternative to this quality control job. The present research project has been developed with the objective of justifying the use of new technologies applied to road construction; making a comparative analysis between traditional methods used in our country and nuclear techniques that have been using in United States with great success in quality control in road construction.

  10. Adaptive management system for hazardous technology organizations: safety culture as an assumption of nuclear excellence; Sistema de gestao adaptativo para organizacoes com tecnologia perigosa: a cultura de seguranca como pressuposto de excelencia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Obadia, Isaac Jose

    2004-07-01

    This work develops a management system for organizations of sectors that deal with hazardous technology - aviation, petrochemical and nuclear, among others - where safety represents a critical factor to organizational excellence. The system consists of a management process based on the Model of Excellence of the Brazilian Quality Award to which the organisation's safety culture is integrated under an adaptive approach and safety is incorporated as an strategic dimension of excellence. The complexity involved in the organizational changing process, established by the implementation of the system, has been considered in the facilitated change type of intervention, also developed in this work, through a case study performed in a nuclear research and technological development installation. The developed system makes possible as effective safety culture improvement and simultaneously facilitates an effective implementation of the management process in search of excellence. (author)

  11. Validation of a methodology for the study of generation cost of electric power for nuclear power plants; Validacion de una metodologia para el estudio de costos de generacion de electricidad de plantas nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R.F.; Martin del Campo M, C. [Facultad de Ingenieria, UNAM, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550, Jiutepec, Morelos (Mexico)]. E-mail: rfortega@mexis.com

    2004-07-01

    It was developed a model for the calculation of costs of electric generation of nuclear plants. The developed pattern was validated with the one used by the United States Council for Energy Awareness (USCEA) and the Electric Power Research Institute (EPRI), in studies of comparison of alternatives for electric generation of nuclear plants and fossil plants with base of gas and of coal in the United States described in the guides calls Technical Assessment Guides of EPRI. They are mentioned in qualitative form some changes in the technology of nucleo electric generation that could be included in the annual publication of Costs and Parameters of Reference for the Formulation of Projects of Investment in the Electric Sector of the Federal Commission of Electricity. These changes are in relation to the advances in the technology, in the licensing, in the construction and in the operation of the reactors called advanced as the A BWR built recently in Japan. (Author)

  12. 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)

  13. Neuro-fuzzy models for systems identification applied to the operation of nuclear power plants; Sistemas neuro-fuzzy para identificacao de sistemas aplicados a operacao de centrais nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Antonio Carlos Pinto Dias

    2000-09-01

    A nuclear power plant has a myriad of complex system and sub-systems that, working cooperatively, make the control of the whole plant. Nevertheless their operation be automatic most of the time, the integral understanding of their internal- logic can be away of the comprehension of even experienced operators because of the poor interpretability those controls offer. This difficulty does not happens only in nuclear power plants but in almost every a little more complex control system. Neuro-fuzzy models have been used for the last years in a attempt of suppress these difficulties because of their ability of modelling in linguist form even a system which behavior is extremely complex. This is a very intuitive human form of interpretation and neuro-fuzzy model are gathering increasing acceptance. Unfortunately, neuro-fuzzy models can grow up to become of hard interpretation because of the complexity of the systems under modelling. In general, that growing occurs in function of redundant rules or rules that cover a very little domain of the problem. This work presents an identification method for neuro-fuzzy models that not only allows models grow in function of the existent complexity but that beforehand they try to self-adapt to avoid the inclusion of new rules. This form of construction allowed to arrive to highly interpretative neuro-fuzzy models even of very complex systems. The use of this kind of technique in modelling the control of the pressurizer of a PWR nuclear power plant allowed verify its validity and how neuro-fuzzy models so built can be useful in understanding the automatic operation of a nuclear power plant. (author)

  14. A model of objects based on KKS for the processing of alarms at the Angra 2 nuclear power plant; Um modelo de objetos baseado em KKS para o processamento de alarmes da usina nuclear de Angra 2

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Paulo Adriano da

    2000-03-01

    The purpose of this work is to present a new model of the alarm annunciation system of the Angra 2 nuclear power plant, using concepts of object based modeling and having as basic the Angra 2 Systems and Components Identification System - KKS. The present structure of the Computerized Alarm System - CAS of Angra 2 does not permit a fast visualization of the incoming alarms in case that a great number of them go off, because the monitors can only show 7 indications at a time. The herein proposed model permits a fast identification of the generated alarms, making possible for the operator to have a general view of the current nuclear power plant status. Its managing tree structure has an hierarchical dependence among its nodes, from where, the presently activated alarms are shown. Its man-machine interface is easy interaction and understand because it is based on structure well known by the Angra 2 operators which is the Angra 2 Systems and Components Identification System - KKS. The project was implemented in the format of an Angra 2 Alarms Supervision System (SSAA), and, for purpose of simulation, 5 system of the Angra 2 Nuclear Power Plant have been chosen. The data used in the project like measurement KKS, measurement limits, unity, setpoints, alarms text and systems flow diagrams, are actual data of the Angra 2 Nuclear Power Plant. The Visual Basic programming Language has been used, with emphasis to the object oriented programming, which and modification, without modifying the program code. Event hough using the Visual Basic for programming, the model has shown, for its purpose, a satisfactory real time execution. (author)

  15. 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)

  16. Innovation and knowledge generation in cooperation nets: challenges for regulations in the nuclear safety area in Brazil; Inovacao e geracao de conhecimento nas redes de cooperacao: desafios para a regulacao na area de seguranca nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio

    2014-07-01

    The importance of inter-organisational cooperation within the innovation process has been increasingly recognized. In fact, all organisations, at some point, need to look to external sources for inputs to the process of building up technological competence. In this sense, through a detailed case study, this thesis examine theoretical and empirically how collaborative initiatives have supported the Brazilian nuclear regulatory body in the development and implementation of innovations, in order to verify the positive relationship between the collaboration and the organisational innovation performance. Emphasizing the importance of both internal sources of knowledge and external participation, the study encompasses documentary analysis, a preliminary survey and semi-structured interviews with the regulatory body employers in charge of controlling medical and research facilities and activities involving radiation sources. The thesis demonstrates that innovations developed and implemented in the Brazilian nuclear safety and security area are associated with collaborative initiatives, in order to improve the organizational capability to fulfill safety obligations, providing some important implications for regulatory body managers concerned with the management of innovation. The findings also identified actors with a significant degree of influence in the innovation process. The result reveals that the support provided by these actors has a significant influence on the innovation performance of the Brazilian nuclear regulatory body, suggesting that Brazil should adopt more interactive models of innovation and knowledge transfer. In addition, the findings show that these key actors can play a very distinctive role in the context of sectoral systems of innovation information regime. (author)

  17. Virtual reality as information for patients and their families in a therapeutic procedure in Nuclear Medicine; Realidade virtual como meio de informação para pacientes e seus familiares em procedimento terapêutico na Medicina Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mendonça, S.F.; Nascimento, A.C.H.; Mol, A.C.A.; Marins, E.R.; Suíta, J.C. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    This work consists of the research and unification of the guidelines transmitted to the patients and their relatives in the radioiodine therapy procedures. The goal is to provide greater understanding of the use of nuclear radiation and better understanding of treatment, to help patients better adapt to therapy, to demystify misconceptions about radiation use, and to improve care for their protection and for people close to them. Based on written and verbal information, collected in the scientific literature and in loco, accompanying the routine of the therapeutic rooms of Nuclear Medicine Services (NMS) in Rio de Janeiro, the set of actions that define scenarios experienced by radioiodine therapy patients and their helpers is being generated. Based on this information, a virtual environment is being developed in the Virtual Reality Laboratory of the Institute of Nuclear Engineering (IEN/CNEN-RJ), Brazil, a virtual environment that will allow the visualization of the procedures and instructions passed to the patients by the NMS teams. With this virtual environment, the patient will be able to immersive visualize and experience the different phases of the treatment increasing the chances of efficiency of their participation in the process. (author)

  18. Environmental concerns regarding a materials test reactor fuel fabrication facility at the Nuclear and Energy Research Institute - IPEN; Atomos para el desarrollo de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Santos, G. R. T.; Durazzo, M.; Carvalho, E. F. U. [IPEN, CNEN-SP, P.O. Box 11049, CEP 05422-970, Sao Paulo (Brazil); Riella, H. G. [Universidade Federal de Santa Catarina, Departamento de Engenharia Quimica, Campus Universitario, Florianopolis, CEP 88040-900 (Brazil)]. e-mail: grsantos@ipen.br

    2008-07-01

    The aim of the industrial activities success, front to a more and more informed and demanding society and to a more and more competitive market demands an environmental administration policy which doesn't limit itself to assist the legislation but anticipate and prevent, in a responsible way, possible damages to the environment. One of the maim programs of the Institute of Energetic and Nuclear Research of the national Commission of Nuclear Energy located in Brazil, through the Center of Nuclear Fuel - CCN - is to manufacture MTR-type fuel elements using low-enrichment uranium (20 wt% {sup 2}35U), to supply its IEA-RI research reactor. Integrated in this program, this work aims at well developing and assuring a methodology to implant an environment, health and safety policy, foreseeing its management with the use of detailed data reports and through the adoption of new tools for improving the management, in order to fulfil the applicable legislation and accomplish all the environmental, operational and works aspects. The applied methodology for the effluents management comprises different aspects, including the specific environmental legislation of a country, main available effluents treatment techniques, process flow analyses from raw materials and intakes to products, generated effluents, residuals and emissions. Data collections were accomplished for points gathering and tests characterization, classification and compatibility of the generated effluents and their eventual environmental impacts. This study aims to implant the Sustainable Concept in order to guarantee access to financial resources, allowing cost reduction, maximizing long-term profits, preventing and reducing environmental accident risks and stimulating both the attraction and the keeping of a motivated manpower. Work on this project has already started and, even though many technical actions have not still ended, the results have being extremely valuable. These results can already give to

  19. Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

    1965-10-15

    -Verein' de Rhenanie qui a ete charge de surveiller et de controler la fabrication et le montage des bouilleurs, pour garantir que cet element de la centrale soit aussi exempt que possible de defauts. L'experience acquise dans l'execution de ces travaux peut etre tres utile pour la fabrication et le montage des bouilleurs de n'importe quel type de centrale nucleaire. Le memoire traite des limitations de l'efficacite des essais non destructifs de tubes de bouilleurs. Les auteurs discutent plus particulierement les essais ci-apres: a) Controle automatique par ultrasons de tubes droits dans l'usine de production; b) Controle combine, par ultrasons et par radiographie, de tubes coudes et de soudures; c) Autres controles non destructifs. (author) [Spanish] En la Republica Federal de Alemania se estan construyendo reactores nucleares con generadores de vapor situados en el interior del tanque de presion. Las caracteristicas de este modelo dificultan considerablemente la reparacion de los tubos del generador que puede llegar a paralizar la central nuclear por largos periodos. Como es bien sabido, muchas de las dificultades para mantener en funcionamiento las centrales nucleares de tipo clasico provienen de averias en los tubos del generador de vapor. Por ello, y teniendo tambien en cuenta como razon no menos importante el elevado costo total de esos reactores, es preciso construir los generadores de vapor de tal manera que el factor carga de la central sea lo mas elevado posible. El Technischer Ueberwachungs-Verein Rheinland se encarga de dirigir e inspeccionar la fabricacion y la construccion de generadores de vapor para que esa parte de las instalaciones carezca en lo posible de defectos. La experiencia adquirida a ese respecto ofrece ademas interes para la fabricacion y construccion de los generadores de vapor que se destinan a las centrales nucleares en general. En la presente memoria se examinan los limites de rendimiento del ensayo no destructivo de los tubos para generadores

  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. Monitoring systems online of oil for transformers of nuclear power plants; Sistemas de monitorizacion online del aceite para transformadores de potencia de Centrales

    Energy Technology Data Exchange (ETDEWEB)

    Sarandeses, S.

    2014-07-01

    The nuclear power plants are showing their concern due to the existence of recent failures related to the bulky transformers of power. These transformers are not security, but are important for the production of power as its failure can cause transient on the floor, reactor scram or shooting, that can cause interruptions in the production of energy or might force us to reduce the power of production The analysis of gases dissolved in transformer oil is recognized as a trial key to identify a submerged transformer failure in oil. With this analysis it is not possible to ensure that there is no damage in the transformer, but the probability of risk of this type of failure can be reduced. The industry recommended to equip the new large power transformers with oil online monitoring systems and in some cases also be It recommended its use in existing transformers. (Author)

  2. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

  3. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico. Parte 2

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. de L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

  4. Dose evaluation and establishment of reference levels in activity for nuclear medicine; Avaliação de dose e estabelecimento de níveis de referência em atividade para a medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Julio Cesar de Souza

    2017-07-01

    The International Commission on Radiation Protection (ICRP) has emphasized the importance of accurately determining the mean dose levels, or administered activity, received by the patients for each medical procedure that uses ionizing radiation. However, the number of bibliographic references addressing the need to know and optimize these levels is insufficient, or rather limited, which may lead to non-standardizes techniques, a lack of exposures control, and also the increase of associated radiological risks of these procedures. In this context, a software in Visual Basic® of Microsoft© language was developed whose function is to elaborate a method of obtaining the Reference Levels in Activity (RLA) for nuclear medicine patients by determining the third quartile of the examinations carried out. The program also allows obtaining absorbed dose values in critical organs based on patient specificities as age, sex and Body Mass Index (BMI) in order to evaluate the risk involved in each procedure. The main nuclear medicine diagnostic procedures were evaluated through the database of two public hospitals and a private clinic, obtaining the NRAs of each facility, where the software was validated by comparison with the traditionally accepted calculation methods. Due to the results obtained in each installation, in addition to NRA determination, gaps in treatment capacities and unjustified dose variations for the same procedure were identified, indicating the need for optimization. Thus, the developed program is able to provide the estimated values of effective and absorbed doses involved in each procedure, for each patient, providing reference values for nuclear medicine field, not available in the national scenario so far. (author)

  5. Proficiency tests for evaluation of the {sup 99}Tc{sup m} measurements in the nuclear medicine; Aplicacao de teste de proficiencia para avaliacao da medicao de {sup 99}Tc{sup m} na medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Iwahara, Akira; Tauhata, Luiz; Oliveira, Antonio Eduardo de, E-mail: iwahara@ird.gov.b, E-mail: tauhata@ird.gov.b, E-mail: aedu@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Nicoli, Ieda Gomes, E-mail: ieda@ird.gov.b [Comissao Nacional de Energia Nuclear (CNEN/DF), Brasilia, DF (Brazil). Escritorio de Brasilia; Alabarse, Frederico Gil; Xavier, Ana Maria, E-mail: falabarse@ird.gov.b, E-mail: axavier@ird.gov.b [Comissao Nacional de Energia Nuclear (ESPOA/CNEN-RS), Porto Alegre, RS (Brazil). Escritorio de Porto Alegre

    2009-07-01

    This work performs the performance evaluation of 55 Brazilian nuclear medicine services in activity measurement of radiopharmaceutical containing {sup 99}Tc{sup m}. Proficiency tests based on the acceptance criteria of the Regulation ISO/IEC Guide 43-1 and on the accuracy of the brazilian Regulation CNEN-NN-3.05 were applied in 63 results of activity measurements in radionuclide calibrators used by those services. The performance services has shown that the criteria of the ISO/IEC 43-1, nevertheless to be more restrictive, presents results very consistent with the accuracy criteria requested by the Brazilian regulation

  6. Development of database for spent fuel and special waste from the Spanish nuclear power plants; Desarrollo de la base de datos para el combustible gastado y residuos especiales de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Gandal, R.; Rodriguez Gomez, M. A.; Serrano, G.; Lopez Alvarez, G.

    2013-07-01

    GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

  7. Regulator process for the authorization of an amendment to the operation license of a nuclear power plant in Mexico; Proceso regulador para la autorizacion de una enmienda a la licencia de operacion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Perez, R.; Espinosa V, J.M.; Salgado, J.R.; Mamani, Y.R. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2005-07-01

    The regulator process by which an authorization is granted from an amendment to the License of Operation of a nuclear power station in Mexico is described. It makes an appointment the effective legal mark, the technical characteristics of the modification, the evaluation process and deposition upon oath of tests and finally the elaboration of the Safety report and the Technical Verdict that is a correspondent for the regulator organism to the Secretary of Energy, the one that in turn is the responsible of granting the amendment the License just as it establishes it the Law. (Author)

  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. Developments of STR project in the scope of teleoperation handling robotic for the operation in Spanish nuclear facilities; Desarrollos del proyecto SRT en el area de manipulacion robotica teleoperada para la operacion de las instalaciones nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Bielza, M [ENDESA (Spain); Gomez Santamaria, J [IBERDROLA (Spain); Izquierdo, J A [C.N. COFRENTES (Spain); Martinez, S [C.N. ASCO (Spain); Linares, F [ENSA (Spain); Avello, A [CEIT (Spain); Gago, M J [IBRINCO (Spain)

    1998-12-01

    The main objective of the Teleoperated Robotic Systems project (SRT) is the development of teleoperated robotic systems for use in the inspection, surveillance and maintenance operations in nuclear and radioactive installations. These systems make possible the reduction of the individual and collective doses of the workers that undertake these operations, as well as an increase of plant availability as it is possible to carry out specific tasks of inspection and surveillance in high radiation dose areas without having to reduce the power of the installation. This project started in 1995, deciding to priorize the inspection equipment in a first phase. When this work were advanced, the development of the manipulation activities was carried out to being consider the nuclear installations needs. As a result of this work, the manipulation requirements were elaborated in order to prepare the beginning technical specifications to design the equipment s. These developments are based on a fixed manipulator which is located closed to the equipment that we want to repair, and an arm manipulator which moves by caterpillars, it is easier to control than others; and the navigation system which allows the robot self-locating in the complex area. In this paper the conclusions about the manipulation requirements are described, as well as the state of the manipulation prototype. (Author)

  10. 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.

  11. A methodology for semiautomatic taxonomy of concepts extraction from nuclear scientific documents using text mining techniques; Metodologia para extracao semiautomatica de uma taxonomia de conceitos a partir da producao cientifica da area nuclear utilizando tecnicas de mineracao de textos

    Energy Technology Data Exchange (ETDEWEB)

    Braga, Fabiane dos Reis

    2013-07-01

    This thesis presents a text mining method for semi-automatic extraction of taxonomy of concepts, from a textual corpus composed of scientific papers related to nuclear area. The text classification is a natural human practice and a crucial task for work with large repositories. The document clustering technique provides a logical and understandable framework that facilitates the organization, browsing and searching. Most clustering algorithms using the bag of words model to represent the content of a document. This model generates a high dimensionality of the data, ignores the fact that different words can have the same meaning and does not consider the relationship between them, assuming that words are independent of each other. The methodology presents a combination of a model for document representation by concepts with a hierarchical document clustering method using frequency of co-occurrence concepts and a technique for clusters labeling more representatives, with the objective of producing a taxonomy of concepts which may reflect a structure of the knowledge domain. It is hoped that this work will contribute to the conceptual mapping of scientific production of nuclear area and thus support the management of research activities in this area. (author)

  12. High temperature fast reactor for hydrogen production in Brazil; Reator nuclear rapido de altissima temperatura para producao de hidrogenio no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, Jamil A. do; Ono, Shizuca; Guimaraes, Lamartine N.F. [Centro Tecnico Aeroespacial (CTA-IEAv), Sao Jose dos Campos, SP (Brazil). Inst. de Estudos Avancados]. E-mail: jamil@ieav.cta.br

    2008-07-01

    The main nuclear reactors technology for the Generation IV, on development phase for utilization after 2030, is the fast reactor type with high temperature output to improve the efficiency of the thermo-electric conversion process and to enable applications of the generated heat in industrial process. Currently, water electrolysis and thermo chemical cycles using very high temperature are studied for large scale and long-term hydrogen production, in the future. With the possible oil scarcity and price rise, and the global warming, this application can play an important role in the changes of the world energy matrix. In this context, it is proposed a fast reactor with very high output temperature, {approx} 1000 deg C. This reactor will have a closed fuel cycle; it will be cooled by lead and loaded with nitride fuel. This reactor may be used for hydrogen, heat and electricity production in Brazil. It is discussed a development strategy of the necessary technologies and some important problems are commented. The proposed concept presents characteristics that meet the requirements of the Generation IV reactor class. (author)

  13. Regulatory approach of the monitoring the effectiveness of maintenance at nuclear power plants program; Abordagem regulatoria do programa de monitoracao da eficacia da manutencao para usinas nucleoeletricas

    Energy Technology Data Exchange (ETDEWEB)

    Vajgel, Stefan

    2009-03-15

    The electrical power generation using nuclear power plants requires this installation being safety, reliable and available for the working periods. For this purpose, an adequate, effective and well conducted maintenance program makes an essential and useful tool to the owner of the plant. However, it is necessary to follow the regulatory requirements for this program implementation which monitories this maintenance effectiveness. There are Brazilian norms requirements which must be followed. The international regulatory guides establish these requirements in good details but it is necessary to verify if this methodology for implementing can be totally applied here in Brazil. Then, the american guide NUMARC 93-01 which details how can be implemented a program for this monitoring, shows some methods for using. In this thesis, the Delphi and Probabilistic Safety Analysis were briefly included because they were preferred for implementing this monitoring.in a Brazilian plant. The results which are being obtained show that, looking the regulatory aspects, the NUMARC 93-01 follows our regulations and gives good results for the plant management. (author)

  14. Communication Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material, Software and Related Technology; Comunicacion recibida de algunos Estados Miembros relativa a las directrices para las transferencias de equipos, materiales y programas informaticos de doble uso del ambito nuclear y tecnologia afin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-12

    The Agency has received a Note Verbale from the Permanent Mission of Hungary, dated 14 June 2010, in which it requests that the Agency circulate to all Member States a letter of 7 May 2010 from the Chairman of the Nuclear Suppliers Group, Ambassador Ms. Gyorgyi Martin Zanathy, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America,1 providing further information on those Governments' Guidelines for Nuclear Transfers [Spanish] El Organismo ha recibido una nota verbal de la Mision Permanente de Hungria, de fecha 14 de junio de 2010, en la que le solicita que distribuya a todos los Estados Miembros una carta de 7 de mayo de 2010 enviada al Director General por la Presidenta del Grupo de Suministradores Nucleares, la Sra. Embajadora Gyorgyi Martin Zanathy, en nombre de los Gobiernos de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, China, Chipre, Croacia, Dinamarca, Eslovaquia, Eslovenia, Espana, Estados Unidos de America, Estonia, Federacion de Rusia, Finlandia, Francia, Grecia, Hungria, Irlanda, Islandia, Italia, Japon, Kazajstan, Letonia, Lituania, Luxemburgo, Malta, Noruega, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Rumania, Sudafrica, Suecia, Suiza, Turquia y Ucrania,1 por la que se proporciona mas informacion sobre las Directrices de esos Gobiernos para las transferencias nucleares.

  15. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Comunicacion recibida de la Mision Permanente del Brasil relativa a las directrices de ciertos Estados Miembros para la exportacion de materiales, equipos y tecnologia nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-16

    The Agency has received a Note Verbale from the Permanent Mission of Brazil, dated 22 March 2007, in which it requests that the Agency circulate to all Member States a letter of 12 December 2006 from the Chairman of the Nuclear Suppliers Group, Ambassador Jose Artur Denot Medeiros, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [Spanish] El Organismo ha recibido una nota verbal de la Mision Permanente del Brasil, de fecha 22 de marzo de 2007, en la que le solicita que distribuya a todos los Estados Miembros una carta de 12 de diciembre de 2006 enviada al Director General por el Presidente del Grupo de Suministradores Nucleares, el Embajador Jose Artur Denot Medeiros, en nombre de los Gobiernos de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, Croacia, China, Chipre, Dinamarca, Eslovaquia, Eslovenia, Espana, Estados Unidos de America, Estonia, Federacion de Rusia, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Kazajstan, Letonia, Lituania, Luxemburgo, Malta, Noruega, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Rumania, Sudafrica, Suecia, Suiza, Turquia y Ucrania, por la que se proporciona mas informacion sobre las Directrices de esos Gobiernos para las transferencias nucleares.

  16. Radiation protection requirements necessary for the introduction of the Ga-68 in a Nuclear Medicine Service; Requisitos de protección radiológica necesarios para la introducción del Ga-68 en un Servicio de Medicina Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Campayo, G.; Ibáñez-Roselló, B.; Reinado, D.; Verdú, G.

    2016-07-01

    The new diagnostic technique that use Ga-68 entail a radiation safety review in nuclear medicine service. It will be evaluate the exposure risk of the workers, who actually are exposed to dose associated to labeled radiopharmaceuticals with F-18, and are estimated the risks due to radiopharmaceuticals with Ga-68. A barrier check-up is made in the current location and an increase of dose rate is estimated with the introduction of Ga-68. Two studies have been done, exposure risk and barrier check-up, in a particular installation. The results obtained conclude that the introduction of Ga-68 in a nuclear medicine service is possible taking into account the minimal modifications in the installation. However, the related modifications have to be studied for each different installation. [Spanish] Las nuevas técnicas diagnósticas que hacen uso del Ga-68 implica la revisión de aspectos de protección radiológica en un servicio de medicina nuclear. Se evalúa el riesgo de exposición de los trabajadores, que en la actualidad están expuestos a los riesgos asociados a los radiofármacos marcados con F-18, y se estiman los debidos a radiofármacos con Ga-68. Se realiza una verificación de barreras en la situación actual y se estima el aumento de la tasa de dosis con la introducción del Ga-68. Se han aplicado ambos estudios, de riesgo de exposición y de verificación de barreras, a una instalación concreta. Los resultados obtenidos concluyen que la introducción del Ga-68 en un servicio de medicina nuclear es posible teniendo en cuenta unas modificaciones mínimas de la instalación. No obstante, las modificaciones aplicables deben ser estudiadas para cada instalación concreta.

  17. Methodological proposal for identification and evaluation of environmental aspects and impacts of nuclear facilities of IPEN, Sao Paulo, SP, Brazil: a case study applied to the Nuclear Fuel Center; Proposta metodologica para a identificacao e avaliacao de aspectos e impactos ambientais em instalacoes nucleares do IPEN: estudo de caso aplicado ao Centro do Combustivel Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mattos, Luis Antonio Terribile de

    2013-07-01

    This work presents an application of Failure Mode Effect Analysis (FMEA) to the process of identification of environmental aspects and impacts as a part of implementation and maintenance of an Environmental Management System (EMS) in accordance with the NBR ISO 14001 standard. Also, it can contribute, as a complement, to the evaluation and improvement of safety of the installation focused. The study was applied to the Nuclear Fuel Center (CCN) of Nuclear and Energy Research Institute (IPEN), situated at the Campus of University of Sao Paulo, Brazil. The CCN facility has the objective of promoting scientific research and of producing nuclear fuel elements for the IEA-R1 Research Reactor. To identify the environmental aspects of the facility activities, products, and services, a systematic data collection was carried out by means of personal interviews, documents, reports and operation data records consulting. Furthermore, the processes and their interactions, failure modes, besides their causes and effects to the environment, were identified. As a result of a careful evaluation of these causes it was possible to identify and to classify the major potential environmental impacts, in order to set up and put in practice an Environmental Management System for the installation under study. The results have demonstrated the validity of the FMEA application to nuclear facility processes, identifying environmental aspects and impacts, whose controls are critical to achieve compliance with the environmental requirements of the Integrated Management System of IPEN. It was demonstrated that the methodology used in this work is a powerful management tool for resolving issues related to the conformity with applicable regulatory and legal requirements of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment (IBAMA). (author)

  18. Quantification of tomography images for dose calculation for diagnosis and therapy in nuclear medicine; Quantificacao de imagens tomograficas para calculo de dose em diagnose e terapia em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Massicano, Felipe

    2010-07-01

    The nuclear medicine area has an increasing slope in the therapy of diseases, particularly in the treatment of radiosensitive tumors. Due to the high dose levels in radionuclide therapy, it is very important the accurate quantify of the dose distribution to avoid deleterious effects on healthy tissues. In Brazil, the internal dosimetry system used is the MIRD (Medical Internal Radiation Dose) based on a reference model that does not have adequate patient data to obtain a dose accurate assessment in therapy. However, in recent years, internal radionuclide dosimetry evaluates the spatial dose distribution base ad on information obtained from CT and SPECT or PET images together with the using of Monte Carlo codes. Those systems are called patient-specific dosimetry systems. In the Nuclear Engineering Center at IPEN, this methodology is in development. When the CT images are inserted into the Monte Carlo code MCNP5 through of use of a interface software called SCMS the dosimetry can be accomplished using patient-specific data, resulting in a more accurate energy deposition in organs of interest. This work aim to contribute with the development of part of that patient-specific dosimetry for therapy. To achieve this goal we have proposed three specific objectives: (1) Development of a software to convert images from Computed Tomography (CT) in the tissue parameters ({rho}, {omega}({iota})); (2) Development of a software to perform attenuation correction in nuclear medicine tomographic images (SPECT or PET) and to provide the map of relative activity and (3) Provide data to the SCMS code by these two software. The software developed for the rst specific objective was the Image Converter Computed Tomography (ICCT), which obtained a good accuracy to determine the density and the tissue composition; the elements that had high variation were carbon and oxygen. Fortunately, this variation for the energy range used in radionuclide therapy is not detrimental to the dose

  19. A importância da contra-imunoeletroforese na detecção de antígenos nucleares extraíveis para o diagnóstico de doenças reumáticas sistêmicas The importance of counterimmunoelectrophoresis in the detection of extractable nuclear antigens for the diagnosis of systemic rheumatic diseases

    Directory of Open Access Journals (Sweden)

    Rita de Cassia Siqueira Bruder

    2004-02-01

    Full Text Available Os antígenos nucleares extraíveis (ENAs são encontrados no soro da maioria dos pacientes com doença reumática sistêmica. Os principais ENAs estudados são SS-A/Ro, SS-B/La, RNP, Sm, Scl-70 e Jo-1. Objeti-vou-se neste trabalho: a padronizar a técnica de contra-imunoeletroforese (CIE para a detecção de ENAs; b padronizar o substrato antigênico (ENAs para a CIE a partir de baço de cão; c comparar os resultados da CIE com as técnicas de imunofluorescência indireta (IFI e Elisa para esses antígenos. Para tal foram estudados 40 soros de pacientes com doença reumática sistêmica confirmada por exames clínico e laboratorial (sorológico e biópsia. Como controle negativo foram utilizados dez soros de doadores de sangue normais, e, como controles positivos, seis soros-padrão anti-Ro, anti-La, anti-RNP, anti-Sm, anti-Scl-70, anti-Jo-1, para caracterizar os antígenos presentes no extrato de baço. Neste último foram detectados vários ENAs, exceto RNP e Scl-70. A técnica de CIE apresentou boas sensibilidade (70% e especificidade (100% em relação às outras técnicas (IFI e Elisa. A titulação dos soros pela CIE revelou positividade até diluições de 1:16 em 32,5% dos casos. Concluímos que a CIE e os antígenos extraídos de baço de cão podem ser utilizados na rotina laboratorial para triagem destes ENAs, com a vantagem, em relação à IFI, de poderem ser titulados.Extractable nuclear antigens (ENAs are detected in the sera of the majority of patients with rheumatic systemic disease. The main ENAs studied are SS-A/Ro, SS-B/La, RNP, Sm, Scl-70 and Jo-1. The aim of this work was: a to standardize the counterimmunoelectrophoresis technique (CIE to detect ENAs; b to standardize the extration of ENAs from dog spleen as a substract for CIE test; c to compare the results obtained by CIE with those of indirect immunofluorescence (IFI and Elisa for these antigens. Forty sera from individuals with rheumatic systemic disease confirmed by

  20. Prospective conceptual qualification of hybrid centrifugation/distillatory for {sup 6}LI nuclear fusion technology scaled supply demands; Calificacion conceptual prospectiva de centrifugador/destilador hibrido para produccion de {sup 6}Li a demanda de la tecnologia Nuclear Fusion

    Energy Technology Data Exchange (ETDEWEB)

    Sedano, L.; Herranz, J. L.; Casado, J. L.; Castro, P.; Xiberta, J.

    2013-07-01

    The change in the demand for exploitation of lithium as a resource appears during the last decade, related to the development of the ion-Li batteries market and with the requirements of Nuclear Fusion fuels (deuterium and lithium) as coming energy option. A prospective analysis of synergistic demands of both markets, in its technical and in its economic aspects appears of prospective interest. The civil market {sup 6}Li/{sup 7}Li enrichment demand is analyzed. Specific technological developments permitting on-line production according to demand is discussed. A [centrifugation /thermal diffusion / combined distillation] technique is selected and qualified as technologically viable option for scaled production of litiated-forms. A conceptual design of a production plant is finally proposed according to the new technical capability.

  1. Nuclear energy as culture: a practical process for preparation of the agents responsible for that transformation; Energia nuclear como cultura: um processo pratico para preparacao dos agentes desta transformacao

    Energy Technology Data Exchange (ETDEWEB)

    Aquino, Afonso Rodrigues de; Vieira, Martha Marques Ferreira [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: araquino@ipen.br, e-mail: mmvieira@ipen.br; Soares, Wellington Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: soaresw@cdtn.br

    2008-08-15

    In Brazil research and development are supported mainly by the government, meaning it is public money So it is important to share the knowledge and benefits from the research with the society. Another important question is the scientific analphabetism that raise difficulties for the comprehension of science and technology related matters. One way to improve the understanding process is the creation of workshops for science popularization which presented outstanding results. Participants of a workshop held by the Nuclear Technology Development Center CDTN - BH evaluated with grade 8.8 (from zero to ten) evincing the excellence of the applied model, simple in its essence: a group comprising scientific researchers, journalists and high school teachers attended several specific talks and was asked to prepare material for science divulgation according to the presented criteria. (author)

  2. Shields calculations for teletherapy equipment. Regulatory approach of the National Center of Nuclear Safety; Calculos de blindajes para equipos de teleterapia, enfoque regulatorio del Centro Nacional de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Fuente P, A. de la; Dumenigo G, C.; Quevedo G, J.R.; Lopez F, Y. [Centro Nacional de Seguridad Nuclear, Calle 28 No. 504 e/5 y 7 Ave. Miramar, Playa, Ciudad de la Habana (Cuba)]. e-mail: andres@orasen.co.cu

    2006-07-01

    The evaluation of applications of construction licenses for the new services of radiotherapy has occupied a significant space in the activity developed by the National Center of Nuclear Safety (CNSN) in the last 2 years. Presently work the experiences of the authors in the evaluation of the required shield for the local where cobalt therapy equipment and lineal accelerators of medical use are used its are exposed, the practical problems detected are approached during the application of the methodologies recommended in both cases and its are discussed which have been the suppositions of items accepted by the Regulatory Authority for the realization of these shield calculations. The accumulated experience allows to assure that the realistic application of the item data and the rational use of the engineering logic makes possible to design local for radiotherapy equipment that fulfill the established dose restrictions in the in use legislation in Cuba, without it implies an excessive expense of construction materials. (Author)

  3. 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).

  4. Characterization of a Planetary Boundary Layer model to evaluate radionuclides releases in nuclear installations; Caracterizacao de um modelo de camada limite planetaria para avaliar liberacoes de radionuclideos em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Molnary, Leslie de

    1993-07-01

    A two layer bulk model is used to simulate numerically the time and spatial evolution of concentration of radionuclides in the Planetary Boundary Layer (PBL) for convective and stable conditions. In this model, the closure hypothesis are based on the integrated version of the Turbulent Kinetics Energy (TKE) equation (Smeda,1979). This type of model was adopted here because it is numerically simple to be applied operationally in routine and emergency support systems of atmospheric releases at nuclear power plants, and the hypothesis of the efficiency of the vertical mixing seems to be physically reasonable to simulated PBL evolution for high wind conditions and stable conditions in Subtropical latitudes regions. In order to validate the model to the nuclear power plants of the Centro Experimental Aramar (CEA), located in Ipero, State of Sao Paulo, Brazil, numerical simulations were carried out with initial and boundary conditions based on vertical profiles of temperature and horizontal wind speed and direction obtained from tethered balloon soundings, synoptic charts at 850 hPa and surface observations. Comparisons between a 24 hour long numerical simulation and observations indicate that the model is capable of reproduce the diurnal evolution of temperature and horizontal wind during the convective regime. During stable conditions, the slab model was able to simulate the intensity of the surface inversion as a difference between the mixed layer and surface temperatures. The simulated mixed layer height matches with observations during the convective and stable regime. A daytime release of radionuclides was simulated for CEA region and the results indicated that the maximum relative concentration reaches a distance about 15 Km in 1 hour, varing from 100 times background at the moment of the release to 15 times the background. For night releases, the maximum concentration reaches the same distance in 45 minutes, varing from 100 to 30 times the background values

  5. Analysis of a Multi-Venturi filter for the venting of the primary container of a nuclear reactor; Analisis de un filtro multiventuri para el venteo del contenedor primario de un reactor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Reyes G, A. A.; Sainz M, E.; Ortiz V, J., E-mail: alejandroantonioreyess@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    Since the Chernobyl nuclear accident, European nuclear power plants have opted to install filters in the containment vent pipes, whose function is to help mitigate the consequences of a severe accident, by means of the controlled depressurization of the containment passively through of a containment filtering vent system. These systems are designed to relieve the internal pressure of containment by deliberately opening pressure relief devices, either a valve or rupture disk during a severe accident and being channeled to the filtering unit. In this work, the hydraulic response of a liquid gas washing filtration system is evaluated, since this information is necessary to estimate the effect of the increase of the containment pressure on the venting capacity of the vent pipes. Through CFD simulation, using the programs with open source license CaeLinux-2014 and OpenFoam, the hydrodynamic characteristics of the Multi-Venturi system were obtained for the washing of the gases coming from the containment, which could be included in the general model of the vent pipe. Representative models of the venturi tubes of each concentric sector that are part of the washing system were generated and by parametric calculations the average mass expense established by each venturi was estimated, according to its dimensions and depth to which is located inside the tank. In the same way, the pressure and mass expense required to activate each concentric sector was calculated according to the pressure and mass load from the containment, in order to estimate the maximum expenditure that is established through the filter. The velocity profiles and the characteristic pressure at which each sector operates were also calculated, as well as the local and global discharge pressure drop. (Author)

  6. Elements to evaluate the intention in the non-compliance s or violations to the regulatory framework in the national nuclear facilities; Elementos para evaluar la intencionalidad en los incumplimientos o violaciones al marco regulador en las instalaciones nucleares nacionales

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa V, J. M.; Gonzalez V, J. A., E-mail: jmespinosa@cnsns.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

    Inside the impact evaluation process to the safety of non-compliance s or violations, developed and implanted by the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS), the Guide for the Impact Evaluation to the Safety in the National Nuclear Facilities by Non-compliance s or Violations to the Regulatory Framework was developed, which indicates that in the determination of the severity (graveness level) of a non-compliance or violation, four factors are evaluated: real and potential consequences to the safety, the impact to the regulator process and the intention. The non-compliance s or intentional violations are of particular interest, since the development of the regulatory activities of the CNSNS considers that the personnel of the licensees, as well as their contractors, will act and will communicate with integrity and honesty. The CNSNS cannot tolerate intentional non-compliance s, for what this violations type can be considered of a level of more graveness that the subjacent non-compliance. To determine the severity of a violation that involves intention, the CNSNS also took in consideration factors as the position and the personnel's responsibilities involved in the violation, the graveness level of the non-compliance in itself, the offender's intention and the possible gain that would produce the non-compliance, if exists, either economic or of another nature. The CNSNS hopes the licensees take significant corrective actions in response to non-compliance s or intentional violations, these corrective actions should correspond to the violation graveness with the purpose of generating a dissuasive effect in the organizations of the licensees. The present article involves the legal framework that confers the CNSNS the attributions to impose administrative sanctions to its licensees, establishes the definition of the CNSNS about what constitutes a non-compliance or intentional violation and finally indicates the intention types (deliberate

  7. The implementation and evaluation of physical protection system of the IEA-R1 reactor; Implementacao e avaliacao do sistema de protecao fisica do reator IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Vaz, Antonio Carlos Alves

    2016-11-01

    The September 11, 2001 terrorist attacks in New York, the accident at the Fukushima nuclear power plant on March 2011 and the recent attacks in Paris on November 2015 are examples of events that justify the efforts of the International Agency of Energy Atomic - IAEA to improve security at nuclear facility. The Brazilian government has been collaborating with this project and investing resources to improve the Physical Protection System - PPS of the nuclear research reactor system, technically is associated with the elements of detection, delay and response. The PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. The PPS works to avoid, to mitigate or to minimize the consequences caused by these actions. This study evaluates the PPS of the reactor, identifying the vulnerabilities and suggesting ways to improve the system effectiveness. The analyses were based on the methodology developed by Sandia National Laboratories´ security experts in Albuquerque - USA, allowing the system evaluation through hypothetical and probabilistic analyzes; identifying threats, determining the targets and analyzing the possible adversaries paths. From the methodology adopted was obtained the value around 40% for PE indicator, which shows the need to improve the system to minimizing the vulnerabilities. (author)

  8. Proposal of a methodology to be applied for the characterization of external exposure risk of employees in nuclear medicine services; Proposta de uma metodologia para caracterizacao de risco de exposicao externa de funcionarios de servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Simoes, Rafael Figueiredo Pohlmann

    2010-07-01

    Nuclear medicine procedure requires the administration of radioactive material by injection, ingestion or inhalation. After incorporation, the patient becomes a mobile source of radiation and, after their examination; they can irradiate everyone on their way out of the Nuclear Medicine Service (NMS). A group of workers in this path is considered a critical group, but there are no conviction on this classification, because there are not measurements available. Thus, workers claiming for occupationally exposed individual's (OEI) rights are common. Employers are always in a complex situation, because if they decided to undertake the individual external monitoring of the critical working groups, the Court considers all as OEI and employers are taxed. On the other hand, if they do not provide monitoring, it is impossible to prove that these workers were not exposed to effective doses higher than individual annual public's limit and they lose the actions, too. This work proposes a methodology to evaluate, using TLD environmental monitors, air kerma rate at critical staff points in a NMS. This method provides relevant information about critical groups' exposure. From these results, the clinic or hospital may prove technically, without individual monitoring of employees, the classification of areas and can estimate the maximum flow of patients in the free areas which guarantees exposures below the public individual dose limit. This methodology has been applied successfully to a private clinic in Rio de Janeiro, which operates a NMS. The only critical group that received exposure statistically different from clinic background radiation was that on the antechamber of the NMS. This is a site that should be characterized as a supervised area and the group of workers in this environment as OEI, as the estimated extrapolated annual effective dose in this position was 1.2 +- 0.7 mSv/year, above the public annual limit (1,0 mSv/year). Normalizing by the number of

  9. Application of autoregressive methods and Lyapunov coefficients for instability studies of nuclear reactors; Aplicação de métodos autorregressivos e coeficientes de Lyapunov para estudos de instabilidades em reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Aruquipa Coloma, Wilmer

    2017-07-01

    Nuclear reactors are susceptible to instability, causing oscillations in reactor power in specific working regions characterized by determined values of power and coolant mass flow. During reactor startup, there is a greater probability that these regions of instability will be present; another reason may be due to transient processes in some reactor parameters. The analysis of the temporal evolution of the power reveals a stable or unstable process after the disturbance in a light water reactor of type BWR (Boiling Water Reactor). In this work, the instability problem was approached in two ways. The first form is based on the ARMA (Autoregressive Moving Average models) model. This model was used to calculate the Decay Ratio (DR) and natural frequency (NF) of the oscillations, parameters that indicate if the one power signal is stable or not. In this sense, the DRARMA code was developed. In the second form, the problems of instability were analyzed using the classical concepts of non-linear systems, such as Lyapunov exponents, phase space and attractors. The Lyapunov exponents quantify the exponential divergence of the trajectories initially close to the phase space and estimate the amount of chaos in a system; the phase space and the attractors describe the dynamic behavior of the system. The main aim of the instability phenomena studies in nuclear reactors is to try to identify points or regions of operation that can lead to power oscillations conditions. The two approaches were applied to two sets of signals. The first set comes from signals of instability events of the commercial Forsmark reactors 1 and 2 and were used to validate the DRARMA code. The second set was obtained from the simulation of transient events of the Peach Bottom reactor; for the simulation, the PARCS and RELAP5 codes were used for the neutronic/thermal hydraulic coupling calculation. For all analyzes made in this work, the Matlab software was used due to its ease of programming and

  10. Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine; Desenvolvimento de fontes radioativas seladas imobilizadas em resina epoxi para verificacao de detectores utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tiezzi, Rodrigo

    2016-07-01

    The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and

  11. Results of the evaluation of the radiation protection in several nuclear medicine departments and recommendations for its optimization; Resultados de la evaluacion de la proteccion radiologica en varios departamentos de medicina nuclear y recomendaciones para su optimizacion

    Energy Technology Data Exchange (ETDEWEB)

    Bejerano, Gladys Lopez; Jova Sed, Luis; Diaz, Efren [Centro de Proteccion y Higiene de las Radiaciones, La Habana (Cuba)]. E-mail: gladys@cphr.edu.cu; jova@cphr.edu.cu [and others

    2001-07-01

    For the evaluation of the radiological safety in several Nuclear Medicine departments a survey was processed and applied that gathers the related mainly to: aspect of the licensing and fulfillment of the establish in this, the program of individual radiologic monitoring and his evaluation, functions that serve to the radiologic protection system, program of qualification and training of the personnel, equipment and mean of radiation protection, program of monitoring of the area of work, characteristic of the premises, management of remainder radioactive, program of quality control, aspect related to the radiation protection in the procedure of diagnosis with the investigation; as well as to pregnant patients and those related to the investigation to accidental medical exhibitions. In the work a systematization of the main results had been done, insisting on the evaluation of the doses received by the workers occupational exposed. A comparison of the activities administered to the patients by different departments and the internationally recommended ones, explaining the found differences. In addition the main recommendations were exposed to obtain in these departments an optimization of the radiological safety.

  12. Aid system in the attention direction for accidents diagnosis at nuclear power plants based on artificial intelligence; Sistema de auxilio para o direcionamento da atencao no diagnostico de acidentes em usinas nucleares baseado em inteligencia artificial

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Rafael Gomes da

    2009-07-01

    Transient identification in Nuclear Power Plant (NPP) is often a very hard task and may involve a great amount of human cognition. The early identification of unexpected departures from steady state behavior is an essential step for the operation, control and accident management in NPPs. The bases for the transient identification relay on the evidence that different system faults and anomalies lead to different pattern evolution in the involved process variables. During an abnormal event, the operator must monitor a great amount of information from the instruments that represents a specific type of event Several systems based on specialist systems, neural-networks, and fuzzy logic have been developed for transient identification. In the work, we investigate the possibility of using a Neuro Fuzzy modeling tool for efficient transient identification, aiming to helping the operator crew to take decisions relative to the procedure to be followed in situations of accidents/transients at NPPs. The proposed system uses artificial neural networks (ANN) as first level transient diagnostic After the ANN has done the preliminary transient type identification, a fuzzy-logic system analyzes the results emitting reliability degree of it. A preliminary evaluation of the developed system was made at the Human-System Interface Laboratory (LABIHS). The obtained results show that the system can help the operators to take decisions during transients/accidents in the plant (author)

  13. The project of the Spanish Nuclear Industry Forum to develop an interactive educational material on Radiological Protection; El Proyecto de Foro de la Industria Nuclear espanola para elaborar un material didactico interactivo sobre Proteccion Radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Real, A.; Cruz, T. de la; Girona, L.; Montesinos, L.; Sanchez, P.

    2012-07-01

    The Training Department of the Spanish Nuclear Industry Forum has undertaken a new project to develop an interactive educational material on Radiological Protection. The objective was to develop an attractive, comprehensive and interactive material, to facilitate students and teachers of Elementary, Middle and High schools, to become familiar with ionising radiations. The novelly of the project, is that based on the European framework of key competencies for file long learning, which are defined as a set of knowledge, skills and altitudes that all individuals need for personal fulfilment and employment. The material presented in this paper, is based in an integrated structure of tasks, activities and exercises, which will facilitate the acquisition of as may key competencies as possible. Besides, the material also includes reference texts, links to pertinent web sites and videos. Students, through the development of a specific task (and related activities and exercises), will learn the differences between ionizing and non ionising radiation, the origin, characteristics and types of types of ionising radiation, how to detect and measure them, the potential detrimental health effects, the principles of radiation protection and the beneficial applications can have for man. The material is freely available in www.rinconeducativo.org. (Author) 4 refs.

  14. Application of COMSOL in the solution of the neutron diffusion equations for fast nuclear reactors in stationary state; Aplicacion de COMSOL en la solucion de las ecuaciones de difusion de neutrones para reactores nucleares rapidos en estado estacionario

    Energy Technology Data Exchange (ETDEWEB)

    Silva A, L.; Del Valle G, E., E-mail: evalle@ipn.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

    2012-10-15

    This work shows an application of the program COMSOL Multi physics Ver. 4.2a in the solution of the neutron diffusion equations for several energy groups in nuclear reactors whose core is formed by assemblies of hexagonal transversal cut as is the cas of fast reactors. A reference problem of 4 energy groups is described of which takes the cross sections which are processed by means of a program that prepares the definition of the constants utilized in COMSOL for the generic partial differential equations that this uses. The considered solution domain is the sixth part of the core which is applied frontier conditions of reflection and incoming flux zero. The discretization mesh is elaborated in automatic way by COMSOL and the solution method is one of finite elements of Lagrange grade two. The reference problem is known as the Knk with and without control rod which led to propose the calculation of the effective multiplication factor in function of the control rod fraction from a value 0 (completely inserted control rod) until the value 1 (completely extracted control rod). Besides this the reactivity was determined as well as the change of this in function of control rod fraction. The neutrons scalar flux for each energy group with and without control rod is proportioned. The reported results show a behavior similar to the one reported in other works but using the discreet ordinates S{sub 2} approximation. (Author)

  15. Natural interfaces for interacting with a virtual control desk of a nuclear power plant simulator; Interfaces naturais para interacao com uma mesa de controle virtual de um simulador de uma usina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aghina, Mauricio Alves da Cunha e

    2012-07-01

    Due to very strict standards of safe operation of a nuclear power plant operators must be well trained so they can operate it within the necessary safety procedures. This is done through training simulators, which enable the user operation, as close as possible to the real control desk, and can be inserted accident situations, so they train, how to return the plant to a normal operating condition. Normally is used two types of simulator. Preferred is the full scope simulator, what is a computational dynamics program of the plant used in conjunction with a physical replica of the control desk, but this type of simulator involves a high construction cost. The second type is what uses synoptic windows of various regions of the original control desk, its construction cost is smaller, but it have a little fidelity to the original appearance of the table. Currently, with the use of virtual reality, control desks can be modeled in 3D, making the simulator interface is very similar to the appearance of the real control desk with a low cost construction. This work shows the use of natural interfaces for operator interaction with the virtual control desk, in order that it does not use any mechanical device for displaying and acting with it. For procedures that were used, such as: computer vision to recognize the position of the operator's and observation of their hands to the work of the desk controls and voice recognition. (author)

  16. Study of a fuel assembly for the nuclear reactor of IV generation cooled with supercritical water; Estudio de un ensamble de combustible para el reactor nuclear de generacion IV enfriado con agua supercritica

    Energy Technology Data Exchange (ETDEWEB)

    Barragan M, A.; Martin del Campo M, C.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Espinosa P, G., E-mail: albrm29@yahoo.com [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (MX)

    2011-11-15

    In this work a neutron study is presented about a square assembly design of double line of fuel rods, with moderator box to the center of the arrangement, for a nuclear reactor cooled with supercritical water (SCWR). The SCWR reactor was chosen by the characteristics of its design, mainly because is based in light water reactors (PWR and BWR), and the operational experience that has of them allow to use models and similar programs to simulate the fuel and the nucleus of this type of reactors. To develop the necessary models and to carry out the design and analysis of the SCWR reactor, the neutron codes MCNPX and Helios were used. The reason of using both codes, is because the code MCNPX used thoroughly in the neutron simulation of these reactors, it has been our reference code to analyze the results obtained with the Helios code which results are more efficient because its calculation times are minors. In the nucleus design the same parameters for both codes were considered. The results show that the design with Helios is a viable option to simulate these reactors since their values of the neutrons multiplication factor are very similar to those obtained with MCNPX. On the other hand, it could be corroborated that the CASMO-4 code is inadequate to simulate the fuel to the temperature conditions and water pressure in the SCWR. (Author)

  17. Adaptation of the dynamic model for radiological assessment of nuclear accident in rural area under conditions of tropical climate; Adaptacao do modelo dinamico para avaliacao radiologica de acidente nuclear em area rural nas condicoes de clima tropical

    Energy Technology Data Exchange (ETDEWEB)

    Vinhas, Denise Martins

    2004-07-01

    Following an accidental release of radionuclides to the atmosphere that leads to the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed, in order to estimate radiological consequences and propose and optimize decisions related to the protection of the public. The model ECOSYS has been chosen to integrate the SIEM, the Integrated Emergency System developed by IRD/CNEN, to assess the doses at the short, medium and long term to the public after an accidental contamination of rural areas. The objective of this work is to perform the adaptation of the model ECOSYS to be used in Brazil to assess public exposure and support decision processes regarding the implementation of protective measures but also to guide the need for studies and research aiming to improve the adequacy of estimates to the actual Brazilian situation. The area select for reference to this work consists on the 50 km radius area surrounding the Brazilian nuclear power plants, located at Angra dos Reis County, in the state of Rio de Janeiro. The methodology included the definition of criteria to select agricultural cultures and animals to be simulated, taking into account both the availability of the production at the selected area and the relevance of the food to the population regional diet. Radionuclides included in this study were {sup 137}Cs, {sup 90} Sr and {sup 131} I. A large survey has been performed to gather data related to both agricultural practices and behavior of radionuclides in the selected agricultural-systems. The results of simulation indicated the relevance of the knowledge of local aspects on the estimated doses. Important factors included the kind of products produced, seasonality, agricultural practices, animals feed practices, kind of soil, and ingestion habits of the population. (author)

  18. Protocol for therapy of people who suffered wounds from radioactive material in radiological and nuclear accidents; Protocolo para trato de pessoas que sofreram ferimentos com material radioativo em acidentes radiologicos e nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Amanda Gomes

    2015-07-01

    The handling of glassware in ampoules, containing solution is very common in research or production laboratories. During manipulation, there is a likelihood of occurrence of incidents such as the breaking of ampoules or glass vials containing material in liquid or powdered form which may cause a wound to the possibility of contamination with handled material. When the solution is radioactive there is a concern due to the risk of incorporation of that material. According to NCRP 156, the scientific literature contains over 2100 cases of wounds contaminated with radionuclides and more than 90% of the reported cases occurred in the hands and arms, but mainly on the fingers. Despite having no cases of wounds reported radioactive material in Brazil or a protocol developed by the National Agencies, applications and hence the manipulation of radionuclides is increasing in the country, rising the possibility of wound occurrence contaminated by radionuclides. In this work was proposed a methodology for management of individuals who suffered wounds from radioactive material in cases of nuclear accidents and radiological emergencies that present intake, which consisted of four steps: definition of the accident scenario, individual triage of the public or workers, proper measurements with detectors PRD, IdentiFINDER2 and germanium in different thicknesses material tissue-equivalent, and later adoption of first aid measures consisting of attendance, monitoring of contaminated personnel, evaluation of effective dose and direct to specialized medical center. As an example of results it follows the case of {sup 241}Am where the best performance was obtained by measurements with the shielded HPGe (7%) and the shielded and collimation of 0.5 cm IdentiFINDER2 (10%). While, unshielded PRD, unshielded or shielded side IdentiFINDER2 and unshielded TeCd showed performance ranging from 30 to 70%. In general, the uncertainties obtained had values below 1.5%. In this work a protocol for

  19. Analysis of the implementation of a sand bed type filter for the venting of a nuclear power plant; Analisis de la implementacion de un filtro tipo lecho de arena para el venteo de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas V, D.; Sainz M, E.; Ortiz V, J., E-mail: delfy.cu@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The filtered venting of the containment has been adopted in European countries to mitigate the consequences derived from the excess pressure of the containment during a severe accident. When venting has taken place, the fission products are released directly into the environment, unless a filter is placed in the path of the same, so various types of filters are used to trap the fission products. The containment venting filters currently installed use different filtering technologies that involve more than one medium. Those who use water as the first stage of filtration are called wet systems, are equipped with additional stages to eliminate water drops and emissions of fine aerosols, and may even be equipped with an element that contains certain means of absorption for the gaseous iodine species filtration. Other designs, based on deep bed filtration as the main retention stage, called dry filters; use metal fiber, ceramic or sand filtration media to trap aerosols. The present work evaluates the hydraulic characteristics of the sand bed type filter designed by EDF as a candidate to be installed in the containment of the BWR Mark II (primary containment type of the Laguna Verde nuclear power plant). The evaluation of the sand bed filter was performed using the OpenFOAM open source software package. Models of each zone of the filtering device were generated and by means of a series of parametric calculations of computational fluid mechanics, the relevant hydrodynamic characteristics of the device were obtained, such as pressure drops against mass flow and pressure fields and velocity under different operating conditions. On the other hand, the validation of the sand bed filter model was made when comparing the results of experimental tests carried out in a sand column of the PITEAS program (1985-1986) against the simulation in OpenFOAM. The results obtained are very close to those obtained experimentally. (Author)

  20. 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)

  1. Specification and development of the sharing memory data management module for a nuclear processes simulator; Especificacion y desarrollo del modulo de administracion de datos de memoria compartida para un simulador de procesos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Telesforo R, D. [UNAM, DEPFI, Campus Morelos, Jiutepec, Morelos (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    Actually it is developed in the Engineering Faculty of UNAM a simulator of nuclear processes with research and teaching purposes. It consists of diverse modules, included the one that is described in the present work that is the shared memory module. It uses the IPC mechanisms of the UNIX System V operative system, and it was codified with C language. To model the diverse components of the simulator the RELAP code is used. The function of the module is to generate locations of shared memory for to deposit in these the necessary variables for the interaction among the diverse ones processes of the simulator. In its it will be able read and to write the information that generate the running of the simulation program, besides being able to interact with the internal variables of the code in execution time. The graphic unfolding (mimic, pictorials, tendency graphics, virtual instrumentation, etc.) they also obtain information of the shared memory. In turn, actions of the user in interactive unfolding, they modify the segments of shared memory, and the information is sent to the RELAP code to modify the simulation course. The program has two beginning modes: automatic and manual. In automatic mode taking an enter file of RELAP (indta) and it joins in shared memory, the control variables that in this appear. In manual mode the user joins, he reads and he writes the wanted control variables, whenever they exist in the enter file (indta). This is a dynamic mode of interacting with the simulator in a direct way and of even altering the values as when its don't exist in the board elements associated to the variables. (Author)

  2. 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)

  3. Helium desorption in EFDA iron materials for use in nuclear fusion reactors; Desorcion de helio en materiales de fierro EFDA para su aplicacion en los reactores de fusion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Salazar R, A. R.; Pinedo V, J. L. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico); Sanchez, F. J.; Ibarra, A.; Vila, R., E-mail: arsr2707@hotmail.com [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Av. Complutense No. 40, 28040 Madrid (Spain)

    2015-09-15

    In this paper the implantation with monoenergetic ions (He{sup +}) was realized with an energy of 5 KeV in iron samples (99.9999 %) EFDA (European Fusion Development Agreement) using a collimated beam, after this a Thermal Desorption Spectrometry of Helium (THeDS) was made using a leak meter that detects amounts of helium of up to 10{sup -}- {sup 12} mbar l/s. Doses with which the implantation was carried out were 2 x 10{sup 15} He{sup +} /cm{sup 2}, 1 x 10{sup 16} He{sup +} /cm{sup 2}, 2 x 10{sup 16} He{sup +} /cm{sup 2}, 1 x 10{sup 17} He{sup +} /cm{sup 2} during times of 90 s, 450 s, 900 s and 4500 s, respectively. Also, using the SRIM program was calculated the depth at which the helium ions penetrate the sample of pure ion, finding that the maximum distance is 0.025μm in the sample. For this study, 11 samples of Fe EFDA were prepared to find defects that are caused after implantation of helium in order to provide valuable information to the manufacture of materials for future fusion reactors. However understand the effects of helium in the micro structural evolution and mechanical properties of structural materials are some of the most difficult questions to answer in materials research for nuclear fusion. When analyzing the spectra of THeDS was found that five different groups of desorption peaks existed, which are attributed to defects of He caused in the material, these defects are He{sub n} V (2≤n≤6), He{sub n} V{sub m}, He V for the groups I, II and IV respectively. These results are due to the comparison of the peaks presented in the desorption spectrum of He, with those of other authors who have made theoretical calculations. Is important to note that the thermal desorption spectrum of helium was different depending on the dose with which the implantation of He{sup +} was performed. (Author)

  4. Nuclear law - Nuclear safety

    International Nuclear Information System (INIS)

    Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

    2012-01-01

    This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

  5. para palmito

    Directory of Open Access Journals (Sweden)

    Francisco Paulo Chaimsohn

    2007-01-01

    Full Text Available Densidades de siembra, arreglos espaciales y fertilización en pejibaye (Bactris gasipaes cv Diamantes-10 para palmito. La investigación se llevó a cabo en la Estación Experimental Los Diamantes (Guápiles, Costa Rica, el 3 de octubre del 2003, cuyo objetivo fue la evaluación del efecto de diferentes densidades de siembra (3.333, 5.000 y 6.666 plantas/ha, arreglos espaciales, y diversos métodos de fertilización (química, orgánica, sobre el crecimiento de las plantas de pejibaye para producción de palmito. Se consideraron las variables diámetro y altura del tallo primario y el número de hojas y rebrotes como indicadores de producción. El período de evolución abarcó sólo los primeros 25 meses de crecimiento en el campo. El número de hojas, la altura y el diámetro del tallo no mostraron diferencias de respuesta relevantes. Sólo el número de rebrotes disminuyó al aumentar la densidad de la población, cuando se midió a los 15 meses de edad. El efecto de la fertilización se hizo evidente después de la primera cosecha, realizada a los 20 meses, debido al aumento de la competencia entre plantas, ahora más desarrolladas. Fue entonces cuando la fertilización química indujo la producción de un mayor número y vigor de los rebrotes. Sin embargo, las prácticas evaluadas 25 meses después de la siembra, no habían infl uido hasta ese momento en el número de palmitos cosechados, ni tampoco había afectado las características físicas de los sectores foliar y caulinar del palmito.

  6. Guidance and considerations for the implementation of INFCIRC/225/Rev.4, the physical protection of nuclear material and nuclear facilities; Orientaciones y sugerencias para la aplicacion del documento INFCIRC/225/Rev.4, proteccion fisica de los materiales y las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    This publication is intended to provide guidance and considerations for a State's competent authority to better understand and prescribe appropriate requirements, consistent with INFCIRC/225/Rev.4 for the protection of nuclear material and nuclear facilities which are compatible with accepted international practice. This report, together with a more detailed report, Handbook on the Physical Protection of Nuclear Material and Facilities, which addresses to the licensee or designer of physical protection systems who has specific implementation and compliance responsibilities, should be used in conjunction to each other to provide better and comprehensive guidance on physical protection.

  7. Statistical analysis in the design of nuclear fuel cells and training of a neural network to predict safety parameters for reactors BWR; Analisis estadistico en el diseno de celdas de combustible nuclear y entrenamiento de una red neuronal para predecir parametros de seguridad para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Jauregui Ch, V.

    2013-07-01

    In this work the obtained results for a statistical analysis are shown, with the purpose of studying the performance of the fuel lattice, taking into account the frequency of the pins that were used. For this objective, different statistical distributions were used; one approximately to normal, another type X{sup 2} but in an inverse form and a random distribution. Also, the prediction of some parameters of the nuclear reactor in a fuel reload was made through a neuronal network, which was trained. The statistical analysis was made using the parameters of the fuel lattice, which was generated through three heuristic techniques: Ant Colony Optimization System, Neuronal Networks and a hybrid among Scatter Search and Path Re linking. The behavior of the local power peak factor was revised in the fuel lattice with the use of different frequencies of enrichment uranium pines, using the three techniques mentioned before, in the same way the infinite multiplication factor of neutrons was analyzed (k..), to determine within what range this factor in the reactor is. Taking into account all the information, which was obtained through the statistical analysis, a neuronal network was trained; that will help to predict the behavior of some parameters of the nuclear reactor, considering a fixed fuel reload with their respective control rods pattern. In the same way, the quality of the training was evaluated using different fuel lattices. The neuronal network learned to predict the next parameters: Shutdown Margin (SDM), the pin burn peaks for two different fuel batches, Thermal Limits and the Effective Neutron Multiplication Factor (k{sup eff}). The results show that the fuel lattices in which the frequency, which the inverted form of the X{sup 2} distribution, was used revealed the best values of local power peak factor. Additionally it is shown that the performance of a fuel lattice could be enhanced controlling the frequency of the uranium enrichment rods and the variety of

  8. Development of a computer program of fast calculation for the pre design of advanced nuclear fuel 10 x 10 for BWR type reactors; Desarrollo de un program de computo de calculo rapido para el prediseno de celdas de combustible nuclear avanzado 10 x 10 para reactores de agua en ebullicion

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Montes, J.L.; Ortiz, J.J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: mrpc@nuclear.inin.mx

    2005-07-01

    In the National Institute of Nuclear Research (ININ) a methodology is developed to optimize the design of cells 10x10 of assemble fuels for reactors of water in boil or BWR. It was proposed a lineal calculation formula based on a coefficients matrix (of the change reason of the relative power due to changes in the enrichment of U-235) for estimate the relative powers by pin of a cell. With this it was developed the computer program of fast calculation named PreDiCeldas. The one which by means of a simple search algorithm allows to minimize the relative power peak maximum of cell or LPPF. This is achieved varying the distribution of U-235 inside the cell, maintaining in turn fixed its average enrichment. The accuracy in the estimation of the relative powers for pin is of the order from 1.9% when comparing it with results of the 'best estimate' HELIOS code. With the PreDiCeldas it was possible, at one minimum time of calculation, to re-design a reference cell diminishing the LPPF, to the beginning of the life, of 1.44 to a value of 1.31. With the cell design with low LPPF is sought to even design cycles but extensive that those reached at the moment in the BWR of the Laguna Verde Central. (Author)

  9. Analysis of conditions to safety and radiological protection of Brazilian research particle accelerators facilities; Analise das condicoes de protecao e seguranca radiologicas das instalacoes com aceleradores de particulas na area de pesquisa no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Lourenco, Manuel Jacinto Martins

    2010-07-01

    Eleven institutions of education and research in Brazil use particle accelerators, which fulfill different functions and activities. Currently, these institutions employ a total of fifteen accelerators. In this paper, the object of study is the radiological protection of occupationally exposed individuals, the general public and the radiation safety of particle accelerators. Research facilities with accelerators are classified in categories I and II according to the International Atomic Energy Agency or groups IX and X in accordance with the Brazilian National Commission of Nuclear Energy. Of the 15 accelerators in use for research in Brazil, four belong to category I or group X and eleven belong to category II or group IX. The methodology presented and developed in this work was made through the inspection and assessment of safety and radiological protection of thirteen particle accelerators facilities, and its main purpose was to promote safer use of this practice by following established guidelines for safety and radiological protection. The results presented in this work showed the need to create a program, in our country, for the control of safety and radiological protection of this ionizing radiation practice. (author)

  10. Optimization programs of radiation protection applied to post-graduation and encouraging research; Programas de otimizacao da protecao radiologica aplicados a pos-graduacao e o incentivo a pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Levy, Denise S., E-mail: denise@omiccron.com.br [Omiccron Programacao Grafica, Sao Paulo, Atibaia, SP (Brazil); Sordi, Gian Maria A.A., E-mail: adelia@atomo.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    In 2011 we started the automation and integration of radiological protection optimization programs, in order to offer unified programs and inter-related information in Portuguese, providing Brazilian radioactive facilities a complete repository for research, consultation and information. The authors of this project extended it to postgraduate education, in order to encourage postgraduate students researches, expanding methods for enhancing student learning through the use of different combined resources, such as educational technology, information technology and group dynamics. This new methodology was applied in a postgraduate discipline at Instituto de Pesquisas Energeticas e Nucleares (IPEN), Brazil, in the postgraduate discipline entitled Fundamental Elements of Radiological Protection (TNA-5732). Students have six weeks to assimilate a complex content of optimization, considering national and international standards, guidelines and recommendations published by different organizations over the past decades. Unlike traditional classes, in which students receive prompt responses, this new methodology stimulates discussion, encouraging collective thinking processes and promoting ongoing personal reflection and researches. Case-oriented problem-solving permitted students to play different roles, promoting whole-group discussions and cooperative learning, approaching theory and practical applications. Students discussed different papers, published in international conferences, and their implications according to current standards. The automation of optimization programs was essential as a research tool during the course. The results of this experience were evaluated in two consecutive years. We had excellent results compared to the previous 14 years. The methodology has exceeded expectations and will be also applied in 2013 to ionizing radiation monitoring postgraduate classes. (author)

  11. Immunohistochemical detection of the latent nuclear antigen-1 of the human herpesvirus type 8 to differentiate cutaneous epidemic Kaposi sarcoma and its histological simulators Detecção imuno-histoquímica do antígeno nuclear latente-1 do herpesvirus tipo 8 para diferenciar o sarcoma de Kaposi epidêmico cutâneo de seus simuladores histológicos

    Directory of Open Access Journals (Sweden)

    Patricia Fonseca Pereira

    2013-04-01

    Full Text Available Kaposi's sarcoma is the most common neoplasia diagnosed in AIDS patients and the expression of the human herpesvirus-8 (HHV-8 latent nuclear antigen-1 has been useful for its histological diagnosis. The aim of this study is to confirm that immunohistochemistry is a valuable tool for differentiating KS from its simulators in skin biopsies of HIV patients. Immunohistochemical and histological analyses were performed in 49 Kaposi's sarcoma skin biopsies and 60 of its histological simulators. Positivity was present in the 49 Kaposi's sarcoma skin biopsies and no staining was observed in the 60 simulators analyzed, resulting in sensibility and specificity of 100%. HHV-8 immunohistochemical detection is an effective tool for diagnosing Kaposi's sarcoma, especially in early lesions in which neoplastic features are not evident. It also contributes to its histological differential diagnosis.O sarcoma de Kaposi é a neoplasia mais diagnosticada em pacientes com SIDA e a expressão do antígeno nuclear latente-1 do herpesvírus humano tipo-8 (HHV-8 tem se mostrado útil no seu diagnóstico histológico. O objetivo deste estudo é confirmar que o método imuno-histoquímico é uma ferramenta útil para diferenciar o sarcoma de Kaposi cutâneo de seus simuladores histológicos em pacientes HIV positivos. Análise histológica e imuno-histoquímica foram realizadas em 49 casos de sarcoma de Kaposi cutâneo e 60 casos de seus simuladores histológicos. Positividade à imuno-histoquímica para o antígeno nuclear latente 1 do HHV-8 foi observada nos 49 casos de sarcoma de Kaposi e nenhuma reação foi detectada nos 60 simuladores analisados, resultando em 100% de sensibilidade e especificidade. A detecção do HHV-8 por imuno-histoquímica é uma ferramenta útil para o diagnóstico de sarcoma de Kaposi, especialmente na lesão inicial cujo caráter neoplásico não é evidente, e contribui para seu diagnóstico diferencial histológico.

  12. Nuclear Medicine

    Science.gov (United States)

    ... Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive tracers? ... funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that uses ...

  13. Nuclear safety. Seguranca nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

    1981-01-01

    What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

  14. Non-Destructive Methods for Determining Burn-Up in Nuclear Fuel; Methodes Non Destructives d'Evaluation du Taux de Combustion dans le Combustible Nucleaire; Metody opredeleniya vygoraniya v yadernom toplive bez razrusheniya obraztsa; Metodos No Destructivos para Determinai el Grado de Combustion de los Elementos Combustibles Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    McGonnagle, W. J. [Illinois Institute of Technology, Chicago, IL (United States)

    1966-02-15

    gamma emis par les matieres radioactives qui se forment au cours du processus de fission, en particulier le spectrometre a cristal courbe, le spectrometre Compton magnetique, le spectrometre Compton a coiencidence et le spectrometre a scintillation. Parmi les autres methodes non destructives, on peut citer l'activation de feuilles, la transmission des neutrons, l'analyse par activation, la mesure des rayonnements gamma de capture et la mesure des neutrons instantanes et differes. Le memoire etudie les principes essentiels des differents appareils et procedes ci-dessus, leur precision et leurs limitations. Le memoire presente des methodes non destructives utilisant les isotopes stables produits au cours du processus de fission. Dans les mesures au moyen de ces isotopes, le schema d'irradiation n'a qu'une importance secondaire et le temps de refroidissement ne joue aucun role. De plus, on dispose de donnees nucleaires plus precises sur les produits stables de la fission. Il semble que les plus utiles de tous les isotopes stables produits au cours du processus de fission soient ceux du zirconium, du molybdene, du ruthenium et du neodyme. Le memoire etudie l'interet de ces methodes d'analyse non destructive. (author) [Spanish] Los metodos no destructivos son de gran utilidad para medir cuantitativamente el grado de combustion. El metodo ideal seria el que no requiriese datos especiales sobre los espectros neutrtfni- cos, las irradiaciones precedentes o el tiempo de enfriamiento. Los elementos combustibles irradiados llevan en cierto modo el registro de su grado de combustion. Este registro consiste en el conjunto de los isotopos radiactivos y estables resultantes del proceso de fision. Desgraciadamente, tanto con los metodos no destructivos como con los destructivos el espectro neutronico, las irradiaciones precedentes y el tiempo de enfriamiento influyen sobre dicho registro. Analogamente, la falta de datos nucleares precisos tales como las secciones eficaces nucleares

  15. Invisible nuclear; converting nuclear

    International Nuclear Information System (INIS)

    Park, Jongmoon

    1993-03-01

    This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

  16. Model of a Nuclear Security Naval Agency for radiation control of the Industrial Complex of of Submarine Construction and Maintenance Ship with Nuclear Propulsion; Modelo de uma Agência Naval de Segurança Nuclear para o controle radiológico do complexo industrial de construção e manutenção do submarino com propulsão nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lins Junior, Amilton de Sousa

    2017-07-01

    Due to the construction, by Brazilian Navy, of a Submarine Construction and Maintenance Ship with Nuclear Propulsion, where, among other activities, the commissioning and exchange of the fuel elements of the reactor in the future Nuclear Submarine, and of a Naval Base where the Nuclear Submarine and the Conventional Submarines, it is necessary the establishment of a Nuclear Security Naval Agency to monitor activities involving ionizing radiation sources and nuclear materials aimed at the radiological protection of exposed occupationally individuals (IOE), the general public and the environment. It should be noted that nuclear and radioactive material will be present only in a part of the yard called Radiological Complex. Therefore, the development of a structure for the control of the Radiological Complex is fundamental, considering that the future licensing process will be unprecedented in Brazil and will face several difficulties. This work presents a model of a structure for the radiological control of the industrial complex for the construction and maintenance of the submarine with nuclear propulsion, as well as the fundamental concepts of the activities, such as inspection, regulations and authorizations, to be carried out by the various component sectors of the Nuclear Security Naval Agency. (author)

  17. Reactors licensing: proposal of an integrated quality and environment regulatory structure for nuclear research reactors in Brazil; Licenciamento de reatores: proposta de uma estrutura regulatoria integrada com abordagem em qualidade e meio ambiente para reatores de pesquisa no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Serra, Reynaldo Cavalcanti

    2014-07-01

    A new integrated regulatory structure based on quality and integrated issues has been proposed to be implemented on the licensing process of nuclear research reactors in Brazil. The study starts with a literature review about the licensing process in several countries, all of them members of the International Atomic Energy Agency. After this phase it is performed a comparative study with the Brazilian licensing process to identify good practices (positive aspects), the gaps on it and to propose an approach of an integrated quality and environmental management system, in order to contribute with a new licensing process scheme in Brazil. The literature review considered the following research nuclear reactors: Jules-Horowitz and OSIRIS (France), Hanaro (Korea), Maples 1 and 2 (Canada), OPAL (Australia), Pallas (Holand), ETRR-2 (Egypt) and IEA-R1 (Brazil). The current nuclear research reactors licensing process in Brazil is conducted by two regulatory bodies: the Brazilian National Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA). CNEN is responsible by nuclear issues, while IBAMA by environmental one. To support the study it was applied a questionnaire and interviews based on the current regulatory structure to four nuclear research reactors in Brazil. Nowadays, the nuclear research reactor’s licensing process, in Brazil, has six phases and the environmental licensing process has three phases. A correlation study among these phases leads to a proposal of a new quality and environmental integrated licensing structure with four harmonized phases, hence reducing potential delays in this process. (author)

  18. [Nuclear theory

    International Nuclear Information System (INIS)

    Haxton, W.

    1990-01-01

    This report discusses research in nuclear physics. Topics covered in this paper are: symmetry principles; nuclear astrophysics; nuclear structure; quark-gluon plasma; quantum chromodynamics; symmetry breaking; nuclear deformation; and cold fusion

  19. Nuclear topics

    International Nuclear Information System (INIS)

    Lukner, C.

    1982-07-01

    The pamphlet touches on all aspects of nuclear energy, from the world energy demands and consumption, the energy program of the Federal Government, nuclear power plants in the world, nuclear fusion, nuclear liability up to the nuclear fuel cycle and the shutdown of nuclear power plants. (HSCH) [de

  20. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    Vaughen, V.C.A.

    1983-01-01

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

  1. Development of Nb{sub 2}O{sub 5}|Cu composite as AISI 1020 steel thermal spray coating for protection against corrosion by soil in buried structures; Desenvolvimento e uso do composito de Nb{sub 2}O{sub 5}|Cu como revestimento aplicado por aspersao termica sobre o aco AISI 1020 para protecao contra a corrosao pelo solo em estruturas enterradas

    Energy Technology Data Exchange (ETDEWEB)

    Regis Junior, Oscar [Universidade Tecnologica Federal do Parana, Ponta Grossa, PR (Brazil). Dept. de Mecanica; Silva, Jose Maurilio da; Portella, Kleber Franke [Instituto de Tecnologia para o Desenvolvimento, Curitiba, PR (Brazil). Dept. de Pesquisa em Engenharia Civil; Paredes, Ramon Sigifredo Cortes, E-mail: regis@utfpr.edu.br [Universidade Federal do Parana, Curitiba, PR (Brazil). Dept. de Mecanica

    2012-07-01

    An Nb{sub 2}O|Cu corrosion-resistant coating was developed and applied onto AISI 1020 steel substrate by Powder Flame Spray. A galvanostatic electrochemical technique was employed, with and without ohmic drop, in four different soils (two corrosively aggressive and two less aggressive). Behavior of coatings in different soils was compared using a cathodic hydrogen reduction reaction (equilibrium potential, overvoltage and exchange current density) focusing on the effect of ohmic drop. Results allow recommendation of Nb{sub 2}O{sub 5}|Cu composite for use in buried structure protection. (author)

  2. Nuclear Materials Management in a Recovery Facility for Unirradiated Enriched Uranium; Gestion des Matieres Nucleaires dans une Installation de Recuperation d'Uranium Enrichi Non Irradie; Administrativno-khozyajstvennyj uchet yadernykh materialov na ustanovke po regeneratsii neobluchennogo obogashchennogo urana; Administracion de Materiales Nucleares en una Planta de Recuperacion para Uranio Enriquecido No Irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Jasny, G. R. [Union Carbide Corporation, Oak Ridge, TN (United States)

    1966-02-15

    mediante las tecnicas siguientes: 1. Diseno cuidadoso del equipo para facilitar la limpieza y el muestreo y reducir al minimo el atascamiento del material; 2. Control continuo de todas las corrientes de desechos y residuos, incluidos los efluentes li'quidos y gaseosos, y los desechos contaminados. 3. Inventarios fisicos periodicos; 4. Muestreo y analisis minuciosos de todos los materiales que entran en la planta y de todos los productos que salen de ella; 5. Control estricto de la calidad de las mediciones analiticas y del muestreo; 6. Asignacion de la responsabilidad del control de los materiales al personal tecnico y no a los servicios de contabilidad; 7. Adecuado adiestramiento del personal tecnico. El suministro de datos a los servicios de contabilidad se logra estableciendo una corriente de informacion practicamente paralela a la corriente fi'sica del material; la identidad de cada partida se mantiene mediante una serie de fichas individuales y la salida de una partida se indica pasando la ficha correspondiente al departamento de contabilidad de material nuclear. La mayor parte de las operaciones contables se llevan a cabo con un equipo electronico de sistematizacion de datos. Ademas de los registros y de los calculos necesarios para los balances de material, se llevan registros de carga y concentracion que facilitan la deteccion de anomalias en la relacion entrada-salida o en la evaluacion de las existencias. El analisis estadistico se emplea en gran medida para el control de las mediciones y para reducir al minimo el numero de los analisis quimicos. De todas formas, la aplicacion de la estadistica a la evaluacion de las discrepancias de inventario no ha dado buenos resultados. En la memoria se discuten todos estos detalles de la tecnica de control de materiales y algunos de los problemas que plantea la aplicacion de esta tecnica. (author) [Russian] Na ustanovke Y-12 Komissii po atomnoj jenergii v Okridzhe, Tennessi, uzhe bolee 20 let pererabatyvajutsja i

  3. 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.

  4. Protection coordination program - PCP; Programa de coordenacao de Protecao - PCP

    Energy Technology Data Exchange (ETDEWEB)

    Koehler, Marcos; Pinto, Jose Molinari; Shigueoka, Olimpio Sadao [Companhia Paranaense de Energia (COPEL), Curitiba, PR (Brazil); Sciammarella, Salvatore Filippo; Klimkowski, Mario [Instituto de Tecnologia para o Desenvolvimento (LACTEC), Curitiba, PR (Brazil); Niederheitmann Junior, Heinz Arthur [Universidade Federal do Parana (UFPR), Curitiba, PR (Brazil)

    2000-07-01

    This paper presents the potential of this tool and also the advantages obtained by the implantation of this new procedure in the COPEL. This paper approaches the elaboration of program modeling, the data bank, the types of equipment, and the various available functions, and a real case as an example.

  5. Nuclear rights - nuclear wrongs

    Energy Technology Data Exchange (ETDEWEB)

    Paul, E.F.; Miller, F.D.; Paul, J.; Ahrens, J.

    1986-01-01

    This book contains 11 selections. The titles are: Three Ways to Kill Innocent Bystanders: Some Conundrums Concerning the Morality of War; The International Defense of Liberty; Two Concepts of Deterrence; Nuclear Deterrence and Arms Control; Ethical Issues for the 1980s; The Moral Status of Nuclear Deterrent Threats; Optimal Deterrence; Morality and Paradoxical Deterrence; Immoral Risks: A Deontological Critique of Nuclear Deterrence; No War Without Dictatorship, No Peace Without Democracy: Foreign Policy as Domestic Politics; Marxism-Leninism and its Strategic Implications for the United States; Tocqueveille War.

  6. Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants; Optimizacion y mejora de las especificaciones tecnicas de funcionamiento para las centrales de Santa Maria de Garona y Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Norte Gomez, M D [Empresarios Agrupados, A.I.E., Madrid (Spain); Alcantud, F [Iberdrola C.N., Cofrentes, (Spain); Hoyo, C del [Nuclenor C.N., Santa Maria de Garona (Spain)

    1993-12-15

    Technical Specifications (TS) form one of the basic documents necessary for licensing nuclear power plants and are required by the Government in accordance with Article 26 of the Regulation for Nuclear and Radioactive Facilities. They contain specific plant characteristics and operating limits to provide adequate protection for the safety and health of operators and the general public. For operator actuation, TS include all the surveillance requirements and limiting operating conditions (operation at full power, startup, hot and cold shutdown, and refueling outage) of safety-related systems. They also include the conventional support systems which are necessary to keep the plant in a safe operating conditioner to bring it to safe shutdown in the event of incidents or hypothetical accidents. Because of the large volume of information contained in the TS, the NRC and American utility owners began to simplify and improve the initial standard TS, which has given way to the development of a TS Optimization Program in the USA under the auspices of the NRC. Empresarios Agrupados has been contracted by the BWR Spanish Owners' Group (GPE-BWR) to develop optimized TS for the Santa Maria de Garona and Cofrentes Nuclear Power Plants. The optimized and improved TS are simplified versions of the current ones and facilitate the work of plant operators. They help to prevent risks, and reduce the number of potential transients caused by the large number of tests required by current TS. Plant operational safety is enhanced and higher effective operation is achieved. The GPE-BWR has submitted the first part of the optimized TS with their corresponding Bases to the Spanish Nuclear Council (CSN), for comment and subsequent approval. Once the TS are approved by the Spanish Nuclear Council, the operators of the Santa Maria de Garona and Cofrentes Nuclear Power Plants will be given a training and adaptation course prior to their implementation. (author)

  7. Nuclear moments

    CERN Document Server

    Kopferman, H; Massey, H S W

    1958-01-01

    Nuclear Moments focuses on the processes, methodologies, reactions, and transformations of molecules and atoms, including magnetic resonance and nuclear moments. The book first offers information on nuclear moments in free atoms and molecules, including theoretical foundations of hyperfine structure, isotope shift, spectra of diatomic molecules, and vector model of molecules. The manuscript then takes a look at nuclear moments in liquids and crystals. Discussions focus on nuclear paramagnetic and magnetic resonance and nuclear quadrupole resonance. The text discusses nuclear moments and nucl

  8. A model for environmental scanning oriented for the strategic planning of the Brazilian Nuclear Energy Commission (CNEN); Um modelo de monitoramento ambiental (environmental scanning) orientado para o planejamento estrategico da CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Braga, Fabiane dos Reis

    1997-07-01

    Presently, all the organizations involved with nuclear activities must be one step ahead of what happens in the specific activity areas in order to avoid surprises, to guarantee their activity continuity and the objective extents, and taking into account the external environment influence exercised by the organization on their activities. So, it is necessary a continuous follow up of their transformations. This paper aims to structure a model of the environmental monitoring system oriented to the strategic planning of the Brazilian Nuclear Energy Commission, as function of that new informational needs viewing the fulfilment of that observed gap. (author)

  9. Estrategias para negociaciones exitosas.

    OpenAIRE

    José B. Parra V; Evelinda Santiago J.; Misael Murillo M.; Candy Atonal N.

    2010-01-01

    Las estrategias de negociación son herramientas para disminuir conflictos o para intercambiar bienes y servicios. Una negociación exitosa crea relaciones de solidaridad y propicia reciprocidad, cooperación y confianza para quienes tendrán relaciones permanentes de negociación con beneficios para ambas partes. Una estrategia de negociación exitosa requiere manejar el desarrollo del ambiente social del grupo de personas, con la finalidad de tener presente las fronteras que no pueden irrumpirse....

  10. Subvenciones para instituciones Directrices para gastos de ...

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

    IDRC CRDI

    División de Administración de Subvenciones ... En la Parte 2 del Acuerdo de Subvención estándar de IDRC se incluyen los límites ... pagar los costos de sustitución (tiempo libre para personal académico) de los investigadores principales.

  11. IAEA Technical co-operation. A partner in development. Nuclear science serving people; La cooperation technique de l`AIEA. Un partenariat pour le developpement. La science nucleaire au service de l`humanite; La cooperacion tecnica del OIEA. Un socio para el desarrollo. La ciencia nuclear al servicio de la gente; Tekhnicheskoe sotrudnichestvo magateh. Partner v tselyakh razvitiya. Yadernaya nauka na sluzhbe chelovechestva

    Energy Technology Data Exchange (ETDEWEB)

    Kinley, D; Perez Vargaz, J

    1998-12-31

    This issue contains descriptions of IAEA technical cooperation programs in a variety of disciplines and locations. It includes articles on the eradication of Tsetse flies in Africa, biofertilizers for agriculture, new strains of rice, water resource management, pollution control for a sustainable environment, nuclear medicine, and ensuring nuclear reactor safety

  12. Thermoluminescent Dosimeter as the Gamma Component of a Nuclear Accident Dosimeter; Utilisation du Dosimetre Thermoluminescent Comme Element Detecteur Gamma d'un Dosimetre pour les cas d'Accident Nucleaire; 0422 0415 0420 041c 0414 ; Los Detectores de Termoluminiscencia Como Elemento Gammametrico de un Dosimetro para Casos de Accidente Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Handloser, J. S. [Edgerton, Germeshausen and Grier, Inc., Santa Barbara, CA (United States)

    1965-06-15

    ) [Spanish] En los dosimetros para caso de accidente nuclear se han empleado como gammametro diversos tipos de detectores gamma, tales como dosimetros de vidrio, dosimetros de pelicula, dosimetros quimicos y dosimetros de polimerizacion. Pero el autor llego a la conclusion de que el dosimetro de termoluminiscencia ofrece notables ventajas sobre todos esos tipos. El amplio intervalo de medicion del dosimetro de termoluminiscencia permite, en efecto, su empleo como aparato de control radiologico cotidiano y como dosimetro para caso de accidente. Esta duplicidad elimina la necesidad de disponer de instrumentos especiales para la dosimetria en caso de accidente, y permite utilizar con tal objeto los instrumentos, de uso diario, bien calibrados. Por regla general, el intervalo de medicion propio del dosimetro de termoluminiscencia abarca desde 5 mr a 100 000 r, con reproducibilidad de {+-}10%. El autor ha disenado y construido un dosimetro de fluoruro de calcio, de tipo unico, asi como el correspondiente equipo para su lectura, cuyo intervalo de medicion es de 5 mr a 5000 r. La lectura del dosimetro se efectua calentando el fosforo y midiendo la luz emitida. Se dispone de instrumentos para lecturas que abarcan seis potencias de diez y se han disenado sistemas totalmente automatizados. La lectura con ayuda de estos aparatos solo exige 20 s por dosimetro. Otra ventaja del dosimetro de termoluminiscencia es su baja respuesta neutronica. Esta respuesta variara con el tipo de envoltura y con la naturaleza del fosforo empleados. Un determinado tipo de dosimetro de fluoruro de calcio tiene una respuesta neutronica de 0,27 *10{sup -9} rad/n * cm{sup 2}. El autor describe dos modelos de dosimetros de termoluminiscencia. El primero consiste en un dosimetro de calentamiento interno encerrado en una capsula de vidrio en cuyo interior se ha hecho el vacio; sus dimensiones aproximadas son: 1 cm de diametro y 6 cm de longitud. El segundo modelo esta formado por un tubo de vidrio de pequeno

  13. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  14. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2005-01-01

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  15. Ionizing radiation dose control for workers in a nuclear plant working with unsealed sources; Controle da dose de radiacao ionizante para trabalhadores em uma instalacao radiativa com fontes nao seladas

    Energy Technology Data Exchange (ETDEWEB)

    Gerulis, Eduardo

    2006-07-01

    With the liberation of the use of the nuclear energy for peaceful applications, International Commission Radiological Protection, ICRP, founded in 1928, created a system of protection of the undesirable doses of ionizing radiation in 1958. This has been received by workers, members of the public and environment and hence it became possible for the introduction of these applications. This protection system is adopted by the International Agency of Energy Atomic, IAEA, that publishes recommendations in safety series, 88 and by the Comissao Nacional de Energia Nuclear, CNEN, which publishes these regulations. The international recommendations and national regulations were adapted and they need to be applied in this way. The present paper uses recommendations of the publication 75 from ICRP, of the publication 115 from 88 and regulations of the regulation NN 3.01 from CNEN to present, through radiological protection measures, the ionizing radiation dose control for workers in a nuclear plant that works in the research, production, division and packing of unsealed sources to be used in clinical applications. In that way it is possible to prevent appropriately the undesirable doses and to confirm the received doses. (author)

  16. Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis; Analisis de Eventos Internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Analisis de sistemas

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A; Aguilar T, O; Nunez C, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant{sup ,} CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

  17. Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Cuantificacion de secuencias de accidente y resultados

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A; Aguilar T, O; Nunez C, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1994-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

  18. Nuclear science

    International Nuclear Information System (INIS)

    1989-01-01

    This fact sheet answers specific questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant number sign 1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  19. Nuclear science

    International Nuclear Information System (INIS)

    1989-04-01

    This report answers questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant No.1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  20. Nuclear medicine

    International Nuclear Information System (INIS)

    Lentle, B.C.

    1986-01-01

    Several growth areas for nuclear medicine were defined. Among them were: cardiac nuclear medicine, neuro-psychiatric nuclear medicine, and cancer diagnosis through direct tumor imaging. A powerful new tool, Positron Emission Tomography (PET) was lauded as the impetus for new developments in nuclear medicine. The political environment (funding, degree of autonomy) was discussed, as were the economic and scientific environments

  1. Nuclear option

    Energy Technology Data Exchange (ETDEWEB)

    Kemm, K R

    1978-05-01

    The global outlook is that nuclear reactors are here to stay and South Africa has already entered the nuclear power stakes. This article discusses the rocketing oil prices, and the alternatives that can be used in power generation, the good safety record of the nuclear industry and the effect that South Africa's first nuclear power station should have on the environment.

  2. Nuclear resisters

    International Nuclear Information System (INIS)

    1981-01-01

    The booklet contains six papers by different authors, under the headings: dangers along the nuclear fuel cycle; the nuclear profiteers; the nuclear state is a police state; a non-disposable future (renewable energy sources, energy conservation); nuclear weapons - out of control; man made madness. (U.K.)

  3. Nuclear links

    International Nuclear Information System (INIS)

    1981-01-01

    The subject is dealt with in sections: introduction; energy and the third world; world energy consumption 1978; oil -the energy dilemma; nuclear chains - introduction; uranium; Namibia; enrichment and reprocessing; countries with enrichment and reprocessing facilities; waste; conclusion; why take the nuclear option; third world countries with nuclear reactors; the arms connection; government spending and human resources 1977 (by countries); nuclear power - the final solution; the fascists; world bank; campaigns; community action in Plogoff; Australian labour movement; NUM against nuclear power; Scottish campaign; students against nuclear energy; anti-nuclear campaign; partizans; 3W1 disarmament and development; campaign ATOM; CANUC; 3W1; SANE. (U.K.)

  4. Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II; Revision de documentos guia para obtener la renovacion de licencia de la Central Nuclear Laguna Verde Unidades 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ 52750 La Marquesa, Estado de Mexico (Mexico); Fernandez S, G. [CFE, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin s/n (Km. 7.5), Dos Bocas, 54270 Veracruz (Mexico)]. e-mail: giarvio@yahoo.com.mx

    2008-07-01

    Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

  5. Application of CSN Safety Guide on the content and criteria for the development of waste management plans at nuclear facilities; Aplicacion de la Guia de Seguridad del CSN sobre el contenido y criterio para la elaboracion de los planes de gestion de residuos en las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez Alonso, M. A.; Simon Cirujano, M. I.

    2011-07-01

    The guide was developed with the joint participation and consensus of representatives of all Spanish companies who hold nuclear facilities and was implemented through a pilot project in the CN Jose Cabrera.

  6. 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).

  7. Oro para Colombia

    OpenAIRE

    Rubio Forero, María Claudia

    2016-01-01

    Las mujeres han debido atravesar un largo camino partiendo de la discriminación hasta empezar un proceso de equidad en la sociedad y en el deporte, de esta manera llegar a ser parte de un evento como los Juegos Olímpicos. Esta tesis toma el caso de tres atletas colombianas y describe su proceso de formación para lograr dos medallas de oro para el país.

  8. Estrategias para negociaciones exitosas.

    Directory of Open Access Journals (Sweden)

    José B. Parra V

    2010-01-01

    Full Text Available Las estrategias de negociación son herramientas para disminuir conflictos o para intercambiar bienes y servicios. Una negociación exitosa crea relaciones de solidaridad y propicia reciprocidad, cooperación y confianza para quienes tendrán relaciones permanentes de negociación con beneficios para ambas partes. Una estrategia de negociación exitosa requiere manejar el desarrollo del ambiente social del grupo de personas, con la finalidad de tener presente las fronteras que no pueden irrumpirse. Otro aspecto importante, es el lenguaje corporal utilizado por las personas y las tácticas que se practican. El manejo de esta información permite diseñar diferentes modelos de negociaciones para cada caso específico. Este documento propone la utilización de la herramienta MONACO, diseñada por los autores, que es un software útil para encontrar los mejores tácticas posibles dentro de una negociación; basándose en el lenguaje corporal que muestra el negociante oponente durante cada oferta monetaria. El uso de este software da al negociador la oportunidad de manejar las negociaciones con mayor control, el negociador que usa el software puede elegir una estrategia de acuerdo a las relaciones que espera mantener con el negociador oponente.

  9. New wireless system for fire protection (detection) during dismantling works in Jose Cabrera NPP (CNJC); Nuevo Sistema Inalámbrico de detección contraincendios para el desmantelamiento de a Central Nuclear José Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Núñez, F.J.; Gómez Rodríguez, C.A.

    2016-07-01

    José Cabrera Nuclear Power Plant is currently in an advanced stage in the process of dismantling and decommissioning. As part of that process, it is necessary to remove the maximum possible interference with operating systems, which are still needed to support the works ongoing or to ensure the safety. With that goal it has been installed a new wireless fire detection system that substitutes the old wired one. The coverage of this new system was initially focused on the containment building, establishing a first phase of analysis of signal coverage, and location of the different components in the building and a second phase of implementation (monitoring and testing) to demonstrate the reliability and robustness of the system in a building with such a complex geometry configuration. Currently the WIFI system is in operation, providing coverage to the containment building and other external facilities (laundry, control room, etc) that have been incorporated to support the process of dismantling.

  10. Validation of dose-response curve of CRCN-NE - Regional Center for Nuclear Sciences from Northeast Brazil for {sup 60}Co: preliminary results; Validacao da curva dose-resposta do CRCN-NE para {sup 60}Co: resultados preliminares

    Energy Technology Data Exchange (ETDEWEB)

    Mendonca, Julyanne C.G.; Mendes, Mariana E.; Hwang, Suy F.; Lima, Fabiana F. [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil); Santos, Neide, E-mail: july_cgm@yahoo.com.br [Universidade Federal de Pernambuco (CCB/UFPE), Recife, PE (Brazil). Departamento de Genetica

    2014-07-01

    The cytogenetic study has the chromosomal alterations as biomarkers in absorbed dose estimation by the body of individuals involved in exposure to ionizing radiation by interpreting a dose response calibration curve. Since the development of the technique to the analysis of data, you can see protocol characteristics, leading the International Atomic Energy Agency indicate that any laboratory with intention to carry out biological dosimetry establish their own calibration curves. The Biological Dosimetry Laboratory of the Centro Regional de Ciencias Nucleares (CRCN-NE/CNEN), Brazil, recently established the calibration curve related to gamma radiation ({sup 60}Co). Thus, this work aimed to start the validation of this calibration curve from samples of three different blood donors which were irradiated with an absorbed known single dose of 1 Gy. Samples were exposed to {sup 60}Co source (Glaucoma 220) located in the Department of Nuclear Energy (DEN/UFPE). After fixation with methanol and acetic acid and 5% Giemsa staining, the frequency of chromosomal alterations (dicentric chromosomes, acentric rings and fragments) were established from reading of 500 metaphases per sample and doses were estimated using Dose Estimate program. The results showed that, using the dose-response curve calibration for dicentrics, the dose absorbed estimated for the three individuals ranged from 0.891 - 1,089Gy, taking into account the range of confidence of 95%. By using the dose-response curve for dicentrics added to rings and for the same interval of confidence the doses ranged from 0,849 - 1,081Gy. Thus, the estimative encompassed known absorbed dose the three individuals in confidence interval of 95%. These preliminary results seems to demonstrate that dicentric dose-response curves and dicentrics plus rings established by CRCN-NE / CNEN are valid for dose estimation in exposed individuals. This validation will continue with samples from different individuals at different doses.

  11. The Public Health Problems of Nuclear Waste Disposal; L'Elimination des Dechets Radioactifs et la Sante Publique; 041f 0420 041e 0414 ; Problemas que Presenta para la Salud Publica la Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Dunster, H. J. [United Kingdom Atomic Energy Authority, Health and Safety Branch (United Kingdom)

    1960-07-01

    problemes que pose la fixation d'un taux maximum en ce qui concerne l'evacuation des dechets dans les rivieres, leur enfouissement' dans le sol ou leur immersion dans les eaux profondes de la mer. L'auteur conclut qu'il est possible de demontrer sans difficulte que la plupart des solutions proposees offrent toutes les garanties de securite voulues, mais qu'une enquete et un controle rigoureux sont necessaires lorsque des doses substantiefles de radioactivite peuvent se repandre dans une zone d'habitat humain. (author) [Spanish] Los principios en que se base la solucion de los problemas que presenta para la salud publica la evacuacion de desechos radiactivos son las recomendaciones de la Comision Internacional para la Proteccion Radiologica. Estas recomendaciones no pueden ser aplicadas directamente a Ja evacuacion de desechos debido a que la radiactividad producida no alcanza casi nunca al hombre en forma directa. Asi pues, para establecer las cifras maximas de descarga radiactiva admisibles es preciso conocer no solamente la forma en que el hombre emplea el medio que le rodea sino tambien los distintos procesos que rigen el comportamiento de las materias radiactivas en ese medio precisamente. Como ejemplo de la forma en que el Reino Unido ha tratado estos problemas, el autor de la memoria hace un estudio de la descarga de desechos liquidos de baja actividad en el mar y se refiere brevemente a los problemas similares que plantea el control de las descargas en rios y de la evacuacion en el suelo o en alta mar. Llega a la conclusion de que es posible demostrar sin dificultad el grado de seguridad de la mayoria de las operaciones propuestas para evacuacion de desechos, pero que es necesaria una investigacion y un control meticulosos siempre que haya que evacuar desechos de alto nivel radiactivo en las proximidades de habitaciones humanas. (author) [Russian] Rekomendacii Mezhdunarodnoj komissii po zashhite ot radioaktivnogo obluchenija javljajutsja fundamental'noj osnovoj

  12. Nuclear Power

    International Nuclear Information System (INIS)

    Douglas-Hamilton, J.; Home Robertson, J.; Beith, A.J.

    1987-01-01

    In this debate the Government's policy on nuclear power is discussed. Government policy is that nuclear power is the safest and cleanest way of generating electricity and is cheap. Other political parties who do not endorse a nuclear energy policy are considered not to be acting in the people's best interests. The debate ranged over the risks from nuclear power, the UK safety record, safety regulations, and the environmental effects of nuclear power. The Torness nuclear power plant was mentioned specifically. The energy policy of the opposition parties is strongly criticised. The debate lasted just over an hour and is reported verbatim. (UK)

  13. Experimental study of para- and ortho-H3+ recombination

    International Nuclear Information System (INIS)

    Plasil, R; Varju, J; Hejduk, M; Dohnal, P; KotrIk, T; Glosik, J

    2011-01-01

    Recombination of H 3 + with electrons is a key process for many plasmatic environments. Recent experiments on storage ring devices used ion sources producing H 3 + with enhanced populations of H 3 + ions in the para nuclear spin configuration to shed light on the theoretically predicted faster recombination of para states. Although increased recombination rates were observed, no in situ characterization of recombining ions was performed. We present a state selective recombination study of para- and ortho-H 3 + ions with electrons at 77 K in afterglow plasma in a He/Ar/H 2 gas-mixture. Both spin configurations of H 3 + have been observed in situ with a near infrared cavity ring down spectrometer (NIR-CRDS) using the two lowest energy levels of H 3 + . Using hydrogen with an enhanced population of H 2 molecules in para states allowed us to influence the [para-H 3 + ]/[ortho-H 3 + ] ratio in the discharge and in the afterglow. We observed an increase in the measured effective recombination rate coefficients with the increase of the fraction of para-H 3 + . Measurements with different fractions of para-H 3 + at otherwise identical conditions allowed us to determine the binary recombination rate coefficients for pure para-H 3 + p α bin (77 K) = (2.0±0.4)x10 -7 cm 3 s -1 and pure ortho-H 3 + o α bin (77 K) = (4±3)x10 -8 cm 3 s -1 .

  14. Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities; Analise de requisitos normativos para o desenvolvimento e a implementacao de um sistema de gestao da qualidade em instalacoes e atividades nucleares brasileiras

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo

    2008-07-01

    The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

  15. Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities; Analise de requisitos normativos para o desenvolvimento e a implementacao de um sistema de gestao da qualidade em instalacoes e atividades nucleares brasileiras

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo

    2008-07-01

    The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

  16. JPRS Report, Nuclear Developments

    National Research Council Canada - National Science Library

    1991-01-01

    Partial Contents: Medium Range Missiles, Rocket Engine, Nuclear Submarine, Nuclear Reactor, Nuclear Inspection, Nuclear Weapons, Transfer Technology, Scud, Safety, Nuclear Power, Chernobyl Trial, ,CHemical Weapons...

  17. Standardization of {sup 123}I and {sup 18}F for providing traceability of activity meters performed in the Radiopharmaceutical Production Service of the Instituto de Engenharia Nuclear, RJ, Brazil; Padronizacao do Iodo-123 e Fluor-18 para provimento de rastreabilidade das medicoes de atividade realizadas no Servico de Producao de Radiofarmacos do Instituto de Engenharia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, E.A.L., E-mail: erica@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Delgado, J.U.; Iwahara, A.; Contic, C.C., E-mail: delgado@ird.gov.br, E-mail: iwahara@ird.gov.br, E-mail: ccconti@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The commercialization and use of radiopharmaceuticals in Brazil are regulated by Sanitary Vigilance National Agency which requiring Good Manufacturing Practices certification for all segments within the Nuclear Medicine. Quality Assurance Programmes should implement the standard requirements to ensure that radiopharmaceuticals have requirements quality to proving its efficiency. Several aspects should be controlled, and one of them is the traceability of the Radionuclides Activity Measurement in radiopharmaceuticals doses. This paper aims to provide traceability to dose calibrators (well type ionization chambers) used for {sup 123}I and {sup 18}F activity measurements in Radiopharmaceuticals Production Service placed in Institute of Nuclear Engineering, Rio de Janeiro, RJ, Brazil. (author)

  18. Projects of Modifications of design for mitigation of accidents outside the design Bases on nuclear Central PWR Siemens-KWU and Westinghouse; Proyectos de Modificaciones de Sieno para Mitigacion de Accidentes fuera de la Bases de Diseno en Centrales Nucleares PWR Siemens-KWU y Westinghouse

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez Gonzalez, G.; Cano Rodriguez, L. A.; Arguello Tara, A.

    2014-07-01

    Following the accident at the Japanese Fukushima-Daiichi NPP, the different regulators of nuclear power generation have required numerous reports regarding the evaluation and modification of the capacity of the plants to face accidents with severities beyond that established in their Design Bases. Under this new scenario, with multiple new demands and commitments, EA has carried out the required works for the implementation of strategies to mitigate the consequences of beyond Design Basis accidents for utilities owning Siemens-KWU and Westinghouse PWR nuclear power plants. (Author)

  19. Nuclear forensics

    International Nuclear Information System (INIS)

    Venugopal, V.

    2010-01-01

    Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone activity

  20. Nuclear power

    International Nuclear Information System (INIS)

    1987-01-01

    ''Nuclear Power'' describes how a reactor works and examines the different designs including Magnox, AGR, RBMK and PWR. It charts the growth of nuclear generation in the world and its contributions to world energy resources. (author)

  1. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  2. Tiempo para un cambio

    Science.gov (United States)

    Woltjer, L.

    1987-06-01

    En la reunion celebrada en diciembre dei ano pasado informe al Consejo de mi deseo de terminar mi contrato como Director General de la ESO una vez que fuera aprobado el proyecto dei VLT, que se espera sucedera hacia fines de este aAo. Cuando fue renovada mi designacion hace tres aAos, el Consejo conocia mi intencion de no completar los cinco aAos dei contrato debido a mi deseo de disponer de mas tiempo para otras actividades. Ahora, una vez terminada la fase preparatoria para el VLT, Y habiendose presentado el proyecto formalmente al Consejo el dia 31 de marzo, y esperando su muy probable aprobacion antes dei termino de este ano, me parece que el 10 de enero de 1988 presenta una excelente fecha para que se produzca un cambio en la administracion de la ESO.

  3. Nuclear energy

    International Nuclear Information System (INIS)

    Kuhn, W.

    1986-01-01

    This loose-leaf collection is made up of five didactically prepared units covering the following subjects: basic knowledge on nuclear energy, nuclear energy in relation to energy economy, site issues, environmental compatibility of nuclear energy, and nuclear energy in the focus of political and social action. To this was added a comprehensive collection of material: specific scientific background material, a multitude of tables, diagrams, charts etc. for copying, as well as 44 transparent charts, mostly in four colours. (orig./HP) [de

  4. Nuclear structure

    International Nuclear Information System (INIS)

    Eastham, D.A.; Joy, T.

    1986-01-01

    The paper on 'nuclear structure' is the Appendix to the Daresbury (United Kingdom) Annual Report 1985/86, and contains the research work carried out at the Nuclear Structure Facility, Daresbury, within that period. During the year a total of 74 experiments were scheduled covering the main areas of activity including: nuclear collective motion, nuclei far from stability, and nuclear collisions. The Appendix contains brief reports on these experiments and associated theory. (U.K.)

  5. A NIM (Nuclear Instrumentation Module) system conjugated with optional input for pHEMT amplifier for beta and gamma spectroscopy; Um sistema de modulos NIM conjugados com entrada opcional por amplificador pHEMT para espectroscopia beta e gama

    Energy Technology Data Exchange (ETDEWEB)

    Konrad, Barbara; Lüdke, Everton, E-mail: barbarakonradmev@gmail.com, E-mail: eludke@smail.ufsm.br [Universidade Federal de Santa Maria (LAE/UFSM), RS (Brazil). Lab. de Astrofisica e Eletronica

    2014-07-01

    This work presents a high speed NIM module (Nuclear Instrumentation Module) to detect radiation, gamma and muons, as part of a system for natural radiation monitoring and of extraterrestrial origin. The subsystem developed consists of a preamplifier and an integrated SCA (Single Channel Analyzer), including power supplies of ± 12 and ± 24V with derivations of +3.6 and ± 5V. The single channel analyzer board, consisting of discrete logic components, operating in window modes, normal and integral. The pulse shaping block is made up of two voltage comparators working at 120 MHz with a response time > 60 ns and a logic anticoincidence system. The preamplifier promotes a noise reduction and introduces the impedance matching between the output of anode / diode photomultiplier tubes (PMTs) and subsequent equipment, providing an input impedance of 1MΩ and output impedance of 40 to 140Ω. The shaper amplifier is non-inverting and has variable input capacitance of 1000 pF. The upper and lower thresholds of the SCA are adjustable from 0 to ± 10V, and the equipment is compatible with various types of detectors, like PMTs coupled to sodium iodide crystals. For use with liquid scintillators and photodiodes with crystals (CsI: Tl) is proposed to include a preamplifier circuit pHEMT (pseudomorphic High Electron Mobility Transistor) integrated. Yet, the system presents the possibility of applications for various purposes of gamma spectroscopy and automatic detection of events producing of beta particles.

  6. Synthesis and characterization of inorganic materials to be employees as adsorbents of toxic metals; Sintesis y caracterizacion de materiales inorganicos para ser empleados como adsorbentes de metales toxicos y de interes nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Granados C, F.; Serrano G, J.; Bonifacio M, J., E-mail: francisco.granados@inin.gob.m [ININ, Departamento de Quimica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    In this chapter is described the development of the studies realized in the Instituto Nacional de Investigaciones Nucleares (ININ) by researchers of the Chemistry Department in the area of water decontamination. The study of the metals separation in aqueous solution through inorganic adsorbents, was initiated in the Chemistry Department, using zeolites for to adsorb metal cations like the cobalt and cadmium. In the year 1995, the separation studies of Co and Cd were realized using zeolite X. On the other hand, the adsorption capacity of the natural clinoptilolite to retain to the cobalt was also studied. With the natural evolution of these works, it began to study the effect of the organic compounds presence in the metals adsorption in zeolites. Apart from the Co and Cd the removal of Ni, Cd and Zn of the water has been investigated using clinoptilolite, heulandite and Hg, also using zeolites like adsorbent material. In the last years, they have been carried out studies on the separation of Cr in form of chromate (CrO{sub 4}{sup 2-}) as of dichromate ions (Cr{sub 2}O{sub 7}{sup 2-}), using pouzzolane modified with Fe and tricalcic phosphate. In these works were found that both materials are highly efficient to separate the chromium of aqueous solutions. (Author)

  7. Nuclear terrorism

    International Nuclear Information System (INIS)

    2002-01-01

    Recent reports of alleged terrorist plans to build a 'dirty bomb' have heightened longstanding concerns about nuclear terrorism. This briefing outlines possible forms of attack, such as: detonation of a nuclear weapon; attacks involving radioactive materials; attacks on nuclear facilities. Legislation addressing these risks and the UK's strategy for coping with them are also considered

  8. Nuclear power

    International Nuclear Information System (INIS)

    d'Easum, Lille.

    1976-03-01

    An environmentalist's criticism of nuclear energy is given, on a layman's level. Such subjects as conflict of interest in controlling bodies, low-level radiation, reactor safety, liability insurance, thermal pollution, economics, heavy water production, export of nuclear technology, and the history of the anti-nuclear movement are discussed in a sensationalistic tone. (E.C.B.)

  9. Nuclear alerts

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    Anti-nuclear demonstrations against the deployment of new US missiles were held in Nato Europe. As no agreement has yet been reached at the US-Soviet Intermediate Nuclear Forces talks in Geneva, the deployment of nuclear missiles in Europe has started

  10. Nuclear questions

    International Nuclear Information System (INIS)

    Berg, Eugene

    2012-01-01

    Civilian and military nuclear questions fill a multitude of publications these days, especially after the Japanese tsunami and the Fukushima disaster. The author analyses some of them and highlights the links between civil and military nuclear industries, the realities of the nuclear cycle and related industrial questions before concluding on the controversial issue of weapons and their proliferation potential

  11. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The paper on nuclear decommissioning was presented by Dr H. Lawton to a meeting of the British Nuclear Energy Society and Institution of Nuclear Engineers, 1986. The decommissioning work currently being undertaken on the Windscale advanced gas cooled reactor (WAGR) is briefly described, along with projects in other countries, development work associated with the WAGR operation and costs. (U.K.)

  12. Nuclear electronics

    International Nuclear Information System (INIS)

    Friese, T.

    1981-09-01

    A short survey is given on nuclear radiation detectors and nuclear electronics. It is written for newcomers and those, who are not very familiar with this technique. Some additional information is given on typical failures in nuclear measurement systems. (orig.) [de

  13. JRODOS system: a modern and efficient tool for the management and preparation of nuclear and radiological emergencies and rehabilitation. Implementation in Spain; El sistema JRODOS: una herramienta moderna y eficaz para la gestion y preparacion de emergencias nucleares y radiologicas y la rehabilitacion. Implementacion en Espana

    Energy Technology Data Exchange (ETDEWEB)

    Montero Prieto, M.; Dvirzhark, A.; Acero, A.; Gallego Diaz, E.

    2011-07-01

    JRODOS system is revealed as an efficient, flexible and user-approved at European level to assist in the management of nuclear and radiological emergencies and the subsequent rehabilitation of contaminated environments, both at the national response in the first phase emergence as a regional / local level in emergency preparedness and recovery environment with the help of the social partners concerned.

  14. Evaluation of the aptitude for the service of the pool of the TRIGA Mark III reactor of the National Institute of Nuclear Research of Mexico; Evaluacion de la aptitud para el servicio de la piscina del reactor TRIGA Mark III del Instituto Nacional de Investigaciones Nucleares de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Merino C, J.; Gachuz M, M.; Diaz S, A.; Arganis J, C.; Gonzalez R, C.; Nava G, T.; Medina R, M.J. [Departamento de Sintesis y Caracterizacion de Materiales del ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2001-07-01

    This work describes the evaluation of the structural integrity of the pool of the TRIGA Mark III reactor of the National Institute of Nuclear Research of Mexico, which was realized in July 2001, as an element to determine those actions for preventive and corrective maintenance which owner must do it for a safety and efficient operation of the component in the next years. (Author)

  15. BORILAIN. Mobile device for automatic continuous supply of liquid injection system backup of a nuclear plant in emergency; BORILAIN. Dispositivo movil para el abastecimiento automatico en continuo del sistema de inyeccion del liquido de reserva de una central nuclear en situacion de emergencia

    Energy Technology Data Exchange (ETDEWEB)

    Lacalle, J.; Traino, J.; Troeung, J.; Arnaldos, A.; Alcaraz, D. A.; Lopez, B.; Ponce, A. T.

    2014-07-01

    This paper presents the design and development of the first automatic mobile device for the preparation of a neutron absorbing solution, and providing continuous, 30 days, of the injection system liquid reserve of a nuclear emergency. The work has been developed by GD Energy Services (GDES) for Electricite de France (EDF). (Author)

  16. Computerized system to perform a general radiological evaluation of the persons that live in areas affected by the nuclear accident of Chernobyl; Sistema computarizado para la evaluacion radiologica general de personas que habitan areas afectadas por el accidente nuclear de Chernobil

    Energy Technology Data Exchange (ETDEWEB)

    Cruz Suarez, R; Valdes, M [Centro de Proteccion e Higiene de las Radiaciones, La Habana (Cuba)

    1994-12-31

    A computer program (EVACID) was developed with the purpose of performing a general radiological evaluation. EVACID system allows to automate an important group of dosimetric calculations, as well as to store, codify analyze and relate among them the medical information of the persons affected by the nuclear accident of Chernobyl.

  17. Study of phase transformation of U-2,5Zr-7,5Nb e U-3Zr-9Nb alloys for application in advanced nuclear fuel; Estudo das transformacoes de fases nas ligas U-2,5Zr-7,5Nb e U-3Zr-9Nb para aplicacao em combustivel nuclear avancado

    Energy Technology Data Exchange (ETDEWEB)

    Pais, Rafael Witter Dias

    2015-07-01

    Metal fuels are relevant in the nuclear area due to the versatility of its use in the nuclear fuel cycle. Among the alloys of uranium investigated with high potential for use in nuclear power reactors, U-Zr-Nb alloys appear as an important alternative because of their superior physico-chemical and metallurgical properties. These alloys have also potential for use in nuclear testing, research and production radioisotopes of high performance nuclear reactors. Therefore, the development of these alloys is strategic since they are planned to be used in national reactors as RMB (Brazilian Multipurpose Reactor) and LABGENE (Electrical Generation Core Laboratory), currently under development in Brazil. In this work it was realized a extensive study in the scope of the manufacturing, heat treatment and phase transformations of U-2,5Zr-7,5Nb (m/m%) and U-3ZR-9NB (m/m%) fuel alloys. Ingots of both alloys were produced employing a specific methodology developed in this study. This methodology comprised the melting process in a vacuum induction furnace at high temperatures (1500 °C) and thermal-mechanical processing to break the as-cast structure. Samples with typical dimensions (17 x 7 x 2.5 mm) free from macrostructural defects were homogenized at 1000 °C in vacuum of 10{sup -5} torr for 17.5 hours with a 10°C/min cooling rate until to 820 °C and, subsequently, quenched in water. The samples, randomly selected, were subjected to isothermal treatment tests under different conditions of time and temperature. Isothermal treatments for transformation and retention phases were carried out in a special assembly designed for this work. After the tests, the samples were characterized by the usual phase characterization techniques with particular emphasis for the X-ray diffraction technique. In this way, the Rietveld refinement method was applied. In the case of uranium based alloys it is quite challenging due to the lack of data in the literature. In this work a strategy for the

  18. Disclosure of the peaceful use of nuclear energy to the lay audience of elementary school children; Divulgação do uso pacífico da energia nuclear para o público leigo de crianças do ensino básico

    Energy Technology Data Exchange (ETDEWEB)

    Batista, M.R.; Neder, D.L.S.M. [Secretaria Municipal de Educação, Santa Luzia, MG (Brazil); Batista, A.S.M., E-mail: adriananuclear@yahoo.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Faculdade de Medicina

    2017-07-01

    The peaceful use of nuclear energy, both to obtain safe energy and in medical applications, need to be disseminated among lay public so that fear is not expressed as risk due to lack of knowledge. For this, it is valid the training effort among children of Basic Education, in the instigation to the conscious knowledge that must be consolidated throughout their school career. Thus, in the context of an extension project with a partnership between the Federal University of Minas Gerais (UFMG) and the Municipal Department of Education of the city of Santa Luzia, Minas Gerais, was worked, between the public school students, the theme 'Energy: knowing to understand', using as background the Disney Monsters S / A movie (2001). In the movie the monsters use the energy of the children's shout, but they know them little, considering them toxic and serves in the project to establish analogy with the fear of Nuclear Energy. Methods: The project was developed in twelve public schools in the city of Santa Luzia, Minas Gerais. The film Monstro S / A and Gnose book (produced for the project) were used between October and December 2016. Classroom activities, lectures, model construction and distribution of children's magazines granted by Eletronuclear were the instruments used to observe the appropriation of concepts. Results: Speech records, filming and photographs included a survey of impressions that confirmed a demystification of the association between nuclear energy and unsafety. Conclusion: The elementary school children involved in the research had a mystified view of the use of nuclear energy, with immediate correlations with the atomic bomb. With the development of the project, a critical knowledge formation was demonstrated regarding the safe use of nuclear energy, through new correlations now turned to a plausible comparison with other sources of energy.

  19. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  20. Nuclear energy

    International Nuclear Information System (INIS)

    2007-01-01

    This digest document was written by members of the union of associations of ex-members and retired people of the Areva group (UARGA). It gives a comprehensive overview of the nuclear industry world, starting from radioactivity and its applications, and going on with the fuel cycle (front-end, back-end, fuel reprocessing, transports), the nuclear reactors (PWR, BWR, Candu, HTR, generation 4 systems), the effluents from nuclear facilities, the nuclear wastes (processing, disposal), and the management and safety of nuclear activities. (J.S.)

  1. Nuclear orientation and nuclear structure

    International Nuclear Information System (INIS)

    Krane, K.S.

    1988-01-01

    The present generation of on-line nuclear orientation facilities promises to revolutionize the gathering of nuclear structure information, especially for the hitherto poorly known and understood nuclei far from stability. Following a brief review of the technological developments that have facilitated these experiments, the nuclear spectroscopic information that can be obtained is summarized. Applications to understanding nuclear structure are reviewed, and challenges for future studies are discussed. (orig.)

  2. Nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The committee concludes that the nature of the proliferation problem is such that even stopping nuclear power completely could not stop proliferation completely. Countries can acquire nuclear weapons by means independent of commercial nuclear power. It is reasonable to suppose if a country is strongly motivated to acquire nuclear weapons, it will have them by 2010, or soon thereafter, no matter how nuclear power is managed in the meantime. Unilateral and international diplomatic measures to reduce the motivations that lead to proliferation should be high on the foreign policy agenda of the United States. A mimimum antiproliferation prescription for the management of nuclear power is to try to raise the political barriers against proliferation through misuse of nuclear power by strengthening the Non-Proliferation Treaty, and to seek to raise the technological barriers by placing fuel-cycle operations involving weapons-usable material under international control. Any such measures should be considered tactics to slow the spread of nuclear weapons and thus earn time for the exercise of statesmanship. The committee concludes the following about technical factors that should be considered in formulating nuclear policy: (1) rate of growth of electricity use is a primary factor; (2) growth of conventional nuclear power will be limited by producibility of domestic uranium sources; (3) greater contribution of nuclear power beyond 400 GWe past the year 2000 can only be supported by advanced reactor systems; and (4) several different breeder reactors could serve in principle as candidates for an indefinitely sustainable source of energy

  3. Nuclear physics

    International Nuclear Information System (INIS)

    Kamal, Anwar

    2014-01-01

    Explains the concepts in detail and in depth. Provides step-by-step derivations. Contains numerous tables and diagrams. Supports learning and teaching with numerous worked examples, questions and problems with answers. Sketches also the historical development of the subject. This textbook explains the experimental basics, effects and theory of nuclear physics. It supports learning and teaching with numerous worked examples, questions and problems with answers. Numerous tables and diagrams help to better understand the explanations. A better feeling to the subject of the book is given with sketches about the historical development of nuclear physics. The main topics of this book include the phenomena associated with passage of charged particles and radiation through matter which are related to nuclear resonance fluorescence and the Moessbauer effect., Gamov's theory of alpha decay, Fermi theory of beta decay, electron capture and gamma decay. The discussion of general properties of nuclei covers nuclear sizes and nuclear force, nuclear spin, magnetic dipole moment and electric quadrupole moment. Nuclear instability against various modes of decay and Yukawa theory are explained. Nuclear models such as Fermi Gas Model, Shell Model, Liquid Drop Model, Collective Model and Optical Model are outlined to explain various experimental facts related to nuclear structure. Heavy ion reactions, including nuclear fusion, are explained. Nuclear fission and fusion power production is treated elaborately.

  4. Nuclear chemistry

    International Nuclear Information System (INIS)

    Vertes, A.; Kiss, I.

    1987-01-01

    This book is an introduction to the application of nuclear science in modern chemistry. The first group of chapters discuss the basic phenomena and concepts of nuclear physics with emphasis on their relation to chemical problems, including the main properties and the composition of atomic nuclei, nuclear reactions, radioactive decay and interactions of radiation with matter. These chapters provide the basis for understanding the following chapters which encompass the wide scope of nuclear chemistry. The methods of the investigation of chemical structure based on the interaction of nuclear radiation with matter including positronium chemistry and other exotic atoms is elaborated in particular detail. Separate chapters are devoted to the use of radioactive tracers, the chemical consequences of nuclear processes (i.e. hot atom chemistry), radiation chemistry, isotope effects and their applications, and the operation of nuclear reactors

  5. Nuclear chemistry

    International Nuclear Information System (INIS)

    Vertes, A.; Kiss, I.

    1987-01-01

    This book is an introduction to the application of nuclear science in modern chemistry. The first group of chapters discuss the basic phenomena and concepts of nuclear physics with emphasis on their relation to chemical problems, including the main properties and the composition of atomic nuclei, nuclear reactions, radioactive decay and interactions of radiation with matter. These chapters provide the basis for understanding the following chapters which encompass the wide scope of nuclear chemistry. The methods of the investigation of chemical structure based on the interaction of nuclear radiation with matter including positronium chemistry and other exotic atoms is elaborated in particular detail. Separate chapters are devoted to the use of radioactive tracers, the chemical consequences of nuclear processes (i.e. hot atom chemistry), radiation chemistry, isotope effects and their applications, and the operation of nuclear reactors. (Auth.)

  6. Nuclear forensics

    International Nuclear Information System (INIS)

    Karadeniz, O.; Guenalp, G.

    2010-01-01

    This review discusses the methodology of nuclear forensics and illicit trafficking of nuclear materials. Nuclear forensics is relatively new scientific branch whose aim it is to read out material inherent from nuclear material. Nuclear forensics investigations have to be considered as part of a comprehensive set of measures for detection,interception, categorization and characterization of illicitly trafficking nuclear material. Prevention, detection and response are the main elements in combating illicit trafficking. Forensics is a key element in the response process. Forensic science is defined as the application of a broad spectrum of sciences to answer questions of interest to the legal system. Besides, in this study we will explain age determination of nuclear materials.

  7. Nuclear fuels

    International Nuclear Information System (INIS)

    Gangwani, Saloni; Chakrabortty, Sumita

    2011-01-01

    Nuclear fuel is a material that can be consumed to derive nuclear energy, by analogy to chemical fuel that is burned for energy. Nuclear fuels are the most dense sources of energy available. Nuclear fuel in a nuclear fuel cycle can refer to the fuel itself, or to physical objects (for example bundles composed of fuel rods) composed of the fuel material, mixed with structural, neutron moderating, or neutron reflecting materials. Long-lived radioactive waste from the back end of the fuel cycle is especially relevant when designing a complete waste management plan for SNF. When looking at long-term radioactive decay, the actinides in the SNF have a significant influence due to their characteristically long half-lives. Depending on what a nuclear reactor is fueled with, the actinide composition in the SNF will be different. The following paper will also include the uses. advancements, advantages, disadvantages, various processes and behavior of nuclear fuels

  8. Nuclear networking.

    Science.gov (United States)

    Xie, Wei; Burke, Brian

    2017-07-04

    Nuclear lamins are intermediate filament proteins that represent important structural components of metazoan nuclear envelopes (NEs). By combining proteomics and superresolution microscopy, we recently reported that both A- and B-type nuclear lamins form spatially distinct filament networks at the nuclear periphery of mouse fibroblasts. In particular, A-type lamins exhibit differential association with nuclear pore complexes (NPCs). Our studies reveal that the nuclear lamina network in mammalian somatic cells is less ordered and more complex than that of amphibian oocytes, the only other system in which the lamina has been visualized at high resolution. In addition, the NPC component Tpr likely links NPCs to the A-type lamin network, an association that appears to be regulated by C-terminal modification of various A-type lamin isoforms. Many questions remain, however, concerning the structure and assembly of lamin filaments, as well as with their mode of association with other nuclear components such as peripheral chromatin.

  9. Para-Hermitian and para-quaternionic manifolds

    International Nuclear Information System (INIS)

    Ivanov, S.; Zamkovoy, S.

    2003-10-01

    A set of canonical para-Hermitian connections on an almost para-Hermitian manifold is defined. A Para-hermitian version of the Apostolov-Gauduchon generalization of the Goldberg-Sachs theorem in General Relativity is given. It is proved that the Nijenhuis tensor of a Nearly para-Kaehler manifolds is parallel with respect to the canonical connection. Salamon's twistor construction on quaternionic manifold is adapted to the para-quaternionic case. A locally conformally hyper-para-Kaehler (hypersymplectic) flat structure with parallel Lee form on the Kodaira-Thurston complex surfaces modeled on S 1 x SL (2, R)-tilde is constructed. Anti-self-dual locally conformally hyper-para-Kaehler (hypersymplectic) neutral metrics with non vanishing Weyl tensor are obtained on the Inoe surfaces. An example of anti-self-dual neutral metric which is not locally conformally hyper-para-Kaehler (hypersymplectic) is constructed. (author)

  10. Para-Hermitian and para-quaternionic manifolds

    Energy Technology Data Exchange (ETDEWEB)

    Ivanov, S [University of Sofia ' St. Kl. Ohridski' , Faculty of Mathematics and Informatics, Sofia (Bulgaria) and Abdus Salam International Centre for Theoretical Physics, Trieste (Italy); Zamkovoy, S [University of Sofia ' St. Kl. Ohridski' , Faculty of Mathematics and Informatics, Sofia (Bulgaria)

    2003-10-01

    A set of canonical para-Hermitian connections on an almost para-Hermitian manifold is defined. A Para-hermitian version of the Apostolov-Gauduchon generalization of the Goldberg-Sachs theorem in General Relativity is given. It is proved that the Nijenhuis tensor of a Nearly para-Kaehler manifolds is parallel with respect to the canonical connection. Salamon's twistor construction on quaternionic manifold is adapted to the para-quaternionic case. A locally conformally hyper-para-Kaehler (hypersymplectic) flat structure with parallel Lee form on the Kodaira-Thurston complex surfaces modeled on S{sup 1} x SL (2, R)-tilde is constructed. Anti-self-dual locally conformally hyper-para-Kaehler (hypersymplectic) neutral metrics with non vanishing Weyl tensor are obtained on the Inoe surfaces. An example of anti-self-dual neutral metric which is not locally conformally hyper-para-Kaehler (hypersymplectic) is constructed. (author)

  11. 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”.

  12. Polarographic determination of Iodide and Iodate, in Solutions Coming from Aerosols in Fission Products Containment Studies in Nuclear Power Stations; Determinacion Polarografica de Especies de Iodo (Ioduro y Iodato) en Soluciones Procedentes de Aerosoles, para Estudios de Contencion de Productos de Fision en Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, M.; Ballesteros, O.; Fernandez, M.; Clavero, M.; Gonzalez, A. M. [Ciemat, Madrid (Spain)

    2000-07-01

    A polarographic method is described for the iodine species determination, iodide and iodate in water solutions. the iodate can be determined by differential pulse polarography. Calibration curves and the detection and determination limits have been obtained. Iodides is oxidized to iodate with sodium hypochlorite and the excess of oxidizing agent is destroyed with sodium sulphide. The concentration of iodide is calculated as the difference between the concentration of iodate in the sample before and after the oxidation. As an application, species of iodine in samples coming from the experimental plants GIRS (Gaseous Iodine Removal by Sprays) of Nuclear Fission Department of the CIEMAT, dedicated to fission products containment studies in nuclear power station, were determined. (Author) 10 refs.

  13. Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques; Proyecto Incremento de infraestructura: 'Establecimiento de un laboratorio para estudios de contaminantes en aire, agua y suelo mediante tecnicas atomicas y nucleares'

    Energy Technology Data Exchange (ETDEWEB)

    Aldape U, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1993-10-15

    In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

  14. Evaluation of the use of a Business Intelligence system for management of patient radiation dose undergone to nuclear medicine exams; Avaliação do uso de um sistema de Business Intelligence para gerenciamento da dose de pacientes submetidos a exames de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, A.C.F.S.; Capaverde, A.S.; Moreira, M.N.; Moraes, A.L.; Andrade, J.R.M.; Bacelar, A., E-mail: acfischer@hcpa.edu.br [Hospital de Clínicas de Porto Alegre (HCPA), RS (Brazil). Serviço de Física Médica e Radioproteção

    2017-07-01

    The feasibility of using a Business Intelligence (BI) system, IMPAX BI (Agfa), to manage the effective radiation dose of patients undergoing Nuclear Medicine exams was evaluated. The evaluation was divided into four stages, using retrospective data from the activity administered to adult patients in the year 2016. It was possible with the system to create panels to filter the data by date and display them in table and / or graphs, indicating the estimated doses and established limits. The IMPAX BI system proved to be a tool capable of assisting in dose management in Nuclear Medicine since it facilitates the identification of cases in which the patient is submitted to doses higher than those defined in the protocols of exams.

  15. Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques; Proyecto Incremento de infraestructura: 'Establecimiento de un laboratorio para estudios de contaminantes en aire, agua y suelo mediante tecnicas atomicas y nucleares'

    Energy Technology Data Exchange (ETDEWEB)

    Aldape U, F [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1993-10-15

    In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

  16. Upgrade in the CNSNS of the determination process about the importance for the impact evaluation to the safety of defaults or violations in the national nuclear facilities; Actualizacion en la CNSNS del proceso de determinacion de la importancia para la evaluacion de impacto a la seguridad de incumplimientos o violaciones en las instalaciones nucleares mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa V, J. M.; Jauregui Ch, V., E-mail: jmespinosa@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2014-10-15

    Inside the process of Impact Evaluation to the Safety of the Direccion General Adjunta de Seguridad Nuclear of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the Significance Determination Process (SDP) is used, developed by the United States Nuclear Regulatory Commission (US NRC), to evaluate the violations or defaults to the regulatory framework and to determine its importance to the risk by means of a fixed color: Green (Very low impact to the safety), White (Low impact to moderate to the safety), Yellow (Substantial impact to the safety) or Red (High impact to the safety). All this inside the seven safety foundations of the Reactor Oversight Process: Initiator Events, Mitigation Systems, Integrity of the Barriers, Preparation for Emergencies, Occupational Radiological Safety, Radiological Safety of the Public and Physical Safety. At present the US NRC has developed a new version of the SDP, which presents changes in its structure and the opportunity of carrying out informed evaluations in risk, with more detail about the violations or defaults that happen in different areas. The CNSNS carries out the adaptation of this last version of the SDP in order to have an updated tool for the violations and defaults characterization to the regulatory framework happened in the nuclear power plant of Laguna Verde. In this article is mentioned the legal framework that confers the CNSNS the attributions to impose urgency measures and administrative sanctions to its licensees, also is established the definition of the different colors that the SDP contemplates in function of the increased risk (ΔCdf), a description of the SDP objectives and the elements that conform it is presented, in the same way some examples to illustrate its application are raised. Finally, the steps to continue for their implementation are mentioned. (Author)

  17. Technical cooperation for the pacific uses of nuclear technology in Latin America and Caribbean: the experience of regional agreement ARCAL; Cooperacao tecnica para os usos pacificos da tecnologia nuclear na America Latina e no Caribe: a experiencia do acordo regional ARCAL

    Energy Technology Data Exchange (ETDEWEB)

    Rondinelli Junior, Francisco

    2017-11-01

    This thesis studies the international technical cooperation in the field of peaceful applications of the nuclear technology, focusing on the experience of Latin American countries, where the Cooperation Agreement for the Promotion of Nuclear Science and Technology in Latin America and the Caribbean, also known as ARCAL, is in force. The study adopts as theoretical approach the concept of state capacities, particularly with regard to the institutional capacities applicable to the ARCAL Agreement. Within this approach, three dimensions of analysis are adopted: the institutional dimension, the governance dimension and the focus on outcomes. The evaluation of the ARCAL Agreement is carried out in order to confirm if the intended role to promote regional technical cooperation in the nuclear sector is being implemented. The methodological approach adopted the case study model. It starts with the analysis of the institutional evolution of the Agreement, and identifies variables articulating with the three dimensions above mentioned. The empirical data were collected in two stages. In the first stage it were performed 29 interviews carried out by the author with the technical and staff members of the Department of Technical Cooperation of IAEA, in Vienna, Austria, headquarter of IAEA. The other stage involved an electronic questionnaire submitted to the national coordinator of ARCAL in 14 countries, in a universe of 21 member states. The conclusion of the research points to the fact that the ARCAL Agreement has incorporated, throughout its trajectory, elements of the institutional capacities which are still in the process of development. They give to the Agreement the potential to induce the development of the state capacities of the respective countries in the field of peaceful applications of nuclear technology. (author)

  18. Construction of sustainability indicators for Nuclear Area Innovation and Research Institutes in Brazil; Construção de indicadores de sustentabilidade para institutos de pesquisa e inovação da área de tecnologia nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Simone Fonseca

    2017-07-01

    The dissertation consists of a construction of appropriate sustainability indicators for nuclear area innovation and research institutes in Brazil. In order to do so, the results of the construction process, as well as, the perception of the population that resides in the area surrounding this type of institute are presented and discussed. As reference for this case study, the Nuclear Technology Development Center (CDTN) was chosen. It is located in Pampulha, more specifically, on the campus of the Federal University of Minas Gerais (UFMG), Belo Horizonte, MG, Brazil. One of the methodological processes present in this research is the Delphi method, because it is the most used in the construction of indicators. Its application in this work allowed obtaining the of specialist group opinions collected through a questionnaire. Initially, sixty-nine sustainability indicators were considered. They were distributed among the environmental, economic, socio cultural and institutional dimensions, some of which were obtained through lists of indicators pointed by literature review. Other indicators were built through discussions with groups from the nuclear, environmental, economic and socio cultural areas. Among the set of indicators investigated, twenty-six were selected as being the most relevant. A questionnaire was then applied to one hundred and twenty individuals living in the vicinity of the CDTN. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed, as well as, indicators of the same dimensions were varied. However, the opinion of the population and the opinion of the experts had similar results. Finally, this study is the first proposal for the nuclear sector to construct this kind of indicator that takes into account the evaluation of experts and the opinion of the community that resides around these institutions. (author)

  19. Guidelines for implementation of an environmental management system in the nuclear fuel cycle: a case study of USEXA-CEA; Diretrizes para implantacao de um sistema de gestao ambiental no ciclo do combustivel nuclear: estudo de caso da USEXA-CEA

    Energy Technology Data Exchange (ETDEWEB)

    Mattiolo, Sandra Regina

    2012-07-01

    The environmental management standards are intended to provide to the organizations the elements needed for the implementation of an Environmental Management System (EMS) that can be effectively integrated to another management requirements and assist them to achieve their environmental and economic goals. The Uranium Hexafluoride Production Unit - USEXA, located at the Navy Technological Center in Sao Paulo, will be the first Brazilian industrial plant responsible for the conversion stage in the nuclear fuel cycle (production of uranium hexafluoride - UF6), allowing added-value to the uranium ore. The EMS proposed to USEXA in this project allows to regulate its interfaces with the environment, since the Standards of CNEN - National Commission of Nuclear Energy and of the IAEA - International Atomic Energy Agency for Nuclear Installations, aim, mostly, to attend the security criteria for the population and the environment, concerning ionizing radiation. This model of EMS fills the gaps in standards of IAEA and CNEN, since it takes into account the environmental impacts from the use of chemicals in the manufacturing process of UF6, and general aspects of sustainability. It can be considered an original contribution within the complex activities that includes the uranium processing in the nuclear fuel cycle. This research proposes, as result, the use of a filter of significance to evaluate the environmental impacts depending on the installation location. It is also presented the Management System Manual for USEXA and models for training in personnel management are suggested, such as coaching and neuro linguistic programing, which can be applied to any Management System. The training can be considered a preventive action as they considerably decreased incidents related to equipment maintenance and thus the occurrence of environmental impacts. (author)

  20. Nuclear blackmail and nuclear balance

    International Nuclear Information System (INIS)

    Betts, R.K.

    1987-01-01

    This book raises pointed questions about nuclear saber rattling. More than a dozen cases since the bombing of Hiroshima and Magasaki in which some sort of nuclear threat was used as a sparring technique in tense confrontations are cited. Each incident is described and analyzed. Two theories offered to explain America's use of nuclear threats, the balance of interest theory and the balance of power theory, are contrasted throughout the book. This book helps to fill the gap in the understanding of nuclear weapons and their uses, while pointing out that nuclear bravado could lead to an unintended unleashing of these weapons

  1. Development of a computational database for application in Probabilistic Safety Analysis of nuclear research reactors; Desenvolvimento de uma base de dados computacional para aplicação em Análise Probabilística de Segurança de reatores nucleares de pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Macedo, Vagner dos Santos

    2016-07-01

    The objective of this work is to present the computational database that was developed to store technical information and process data on component operation, failure and maintenance for the nuclear research reactors located at the Nuclear and Energy Research Institute (Instituto de Pesquisas Energéticas e Nucleares, IPEN), in São Paulo, Brazil. Data extracted from this database may be applied in the Probabilistic Safety Analysis of these research reactors or in less complex quantitative assessments related to safety, reliability, availability and maintainability of these facilities. This database may be accessed by users of the corporate network, named IPEN intranet. Professionals who require the access to the database must be duly registered by the system administrator, so that they will be able to consult and handle the information. The logical model adopted to represent the database structure is an entity-relationship model, which is in accordance with the protocols installed in IPEN intranet. The open-source relational database management system called MySQL, which is based on the Structured Query Language (SQL), was used in the development of this work. The PHP programming language was adopted to allow users to handle the database. Finally, the main result of this work was the creation a web application for the component reliability database named PSADB, specifically developed for the research reactors of IPEN; furthermore, the database management system provides relevant information efficiently. (author)

  2. Development of the user Interface of digital simulation system of the operational parameters of the TRIGA IPR-R1 Nuclear Research Reactor; Desenvolvimento da interface para usuário do sistema digital de simulação dos parâmetros operacionais do reator nuclear de pesquisa Triga IPR-R1

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-07-01

    The development of simulation systems has been increasingly improved to ensure security and reliability to the systems being associated. Computational tools, simulation systems and programming languages increasingly allow the diversification of control systems. With increasing concern about monitoring the key parameters involved in chain reactions inside a nuclear reactor, new technologies are being developed to ensure operations safety. This paper deals with a practical application of a work that is being developed in the Center for the Development of Nuclear Technology - CDTN, which intends to simulate the operation of the TRIGA-IPR-R1 nuclear research reactor using the LabVIEW® software, evaluating the evolution of the neutron flux and other related events. In this paper, the visual interface of the reactor control table, developed through virtual instruments that allow, in a vast repertoire of tools, replicating the panels of the control table in modern screens that can be operated by a user of an analogous form, but still more practical and complete. Since the innovations developed for research reactors can be replicated in power reactors, and because of their lower operating and maintenance costs, projects in this area allow the development of several technologies.

  3. Response of monitors of surface contamination to internal exposition control from {sup 131}I in the 'nuclear medicine services'; Respuesta de monitores de contaminacion superficial para el control de la exposicion interna a {sup 131}I en servicios de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Puerta, Nancy; Rojo, Ana M.; Villella, Adrian; Gossio, Sebastian; Parada, Ines Gomez, E-mail: info@arn.gov.br [Autoridad Regulatoria Nuclear (ARN), Buenos Aires (Argentina); Acosta, Norma; Arenas, German, E-mail: nacosta@fuesmen.edu.ar [Fundacion Escuela de Medina Nuclear (FUESMEN), Mendoza (Argentina)

    2013-11-01

    The IAEA, in its publication RS-G-1.2, proposes individual control of workers occupationally exposed with risk of internal exposure when the potential exposure provided by incorporation leads to a value of annual committed effective dose equal to or greater than 1 mSv. Because the radionuclide {sup 131}I is the most important to control internal exposure in Nuclear Medicine Services, it is evaluated if the surface contamination monitors, commonly used in nuclear medicine centers of Argentina, would implement individual control of internal exposure to {sup 131}I. Selected detectors were calibrated with a dummy neck and thyroid with calibrated sources of {sup 131}I and {sup 133}Ba reference. For each detector is was estimated the detection efficiency for {sup 131}I and its detection limit. Each instrument was evaluated for the lowest effective dose possible to detect compromised by individual routine monitoring with different measurement intervals . We analyzed the response of each team for determining conditions that may be effective for the control of internal exposure of {sup 131}I. Finally , we conclude that the daily individual monitoring surface contamination detectors available in the Nuclear Medicine Services is feasible to implement and ensures detection of significant additions of {sup 131}I.

  4. Use of thin layer chromatography for the determination of radiochemical purity of radiopharmaceuticals in nuclear medicine services of Paraiba and Rio Grande do Norte, Brazil; Utilizacao da cromatografia em camada delgada para determinacao da pureza radioquimica de radiofarmacos em servicos de medicina nuclear da Paraiba e Rio Grande do Norte, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, W.G.; Santos, P.A.L.; Lima, F.R.A. [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Programa de Pos-Graduacao em Tecnologia Energetica; Lima, F.F., E-mail: wellington.gandrade@gmail.com [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

    2012-07-01

    The paper chromatography and the thin layer chromatography are separation techniques in which the radioactive components migrate because of their affinity with the eluent (mobile phase) or stationary phase, respectively. In radiopharmaceuticals labeled with {sup 99m}Tc, besides its own radiopharmaceutical, {sup 99m}TcO{sup 4-} free and TcO{sub 2} can be identified and quantified. The evaluation of radiochemical purity of radiopharmaceuticals is essential to produce images free of artifacts as well as avoid unnecessary absorbed dose to the patient. Once they are managed in humans it is important and necessary that they undergo to strict quality control. Because of this, ANVISA in its 'Resolucao da Diretoria Colegiada (RDC) 38 of June 4th, 2008 states the obligation of performing a minimum of tests in nuclear medicine services routine prior to human administration. This work evaluated, by the method of thin layer chromatography (TLC), radiochemical purity, determined the pH of the radiopharmaceutical DEXTRAN- 500, DMSA, DTPA, PHYTATE, MDP, MIBI and Sn-Col used in nuclear medicine services in the states of Paraiba and Rio Grande do Norte - Brazil. The results show that the use of thin layer chromatography (TLC) as a standard method in routine of nuclear medicine services is possible, because it provides important data for the evaluation of radiochemical purity, allowing the exclusion of a radiopharmaceutical poorly marked. (author)

  5. Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants; Interfase visual para la automatizacion del pendulo instrumentado de pruebas Charpy utilizado en el programa de vigilancia de la vasija de reactores de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A. [ININ, Carretera Mexico-Toluca Km.36.5, Mpio. de Ocoyoacac, Estado de Mexico (Mexico)]. E-mail: asrs@nuclear.inin.mx; esm@nuclear.inin.mx; jare@nuclear.inin.mx

    2004-07-01

    Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)

  6. Development of a dynamical model of a nuclear processes simulator for analysis and training in classroom based in the RELAP/SCDAP codes; Desarrollo del modulo dinamico del simulador de procesos nucleares para analisis y entrenamiento en aula basado en los codigos RELAP/SCDAP

    Energy Technology Data Exchange (ETDEWEB)

    Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [UNAM, Fac. de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, DEPFI Campus Morelos, Cuernavaca (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    The present work illustrates the application of the concept of a simulator for analysis, design, instruction and training in a classroom environment associated to a nuclear power station. Emphasis is made on the methodology used to incorporate the best estimate codes RELAP/SCDAP to a prototype under development at the Nuclear Reactor Engineering Analysis Laboratory (NREAL). This methodology is based on a modular structure where multiple processes can be executed in an independent way and where the generated information is stored in shared memory segments and distributed by means of communication routines developed in the C programming language. The utility of the system is demonstrated using highly interactive graphics (mimic diagrams, pictorials and tendency graphs) for the simultaneous dynamic visualization of the most significant variables of a typical transient event (feed water controller failure in a BWR). A fundamental part of the system is its advanced graphic interface. This interface, of the type of direct manipulation, reproduces instruments and controls whose functionality is similar to those found in the current replica simulator for the Laguna Verde Nuclear Power Station. Finally the evaluation process is described. The general behavior of the main variables for the selected transitory event is interpreted, corroborating that they follow the same tendency that those reported for a BWR. The obtained results allow to conclude that the developed system works satisfactorily and that the use of al 1 x 1 real time visualization tools offers important advantages regarding other traditional methods of analysis. (Author)

  7. Project for the adaptation of the Instituto Nacional de Investigaciones Nucleares (ININ) to work as companies incubator, and the business plan as support device in the achievement of successful base technological companies; Proyecto para la adecuacion del Instituto Nacional de Investigaciones Nucleares (ININ) para trabajar como incubadora de empresas y el plan de negocios como instrumento de apoyo en el logro de empresas de base tecnologicas exitosas

    Energy Technology Data Exchange (ETDEWEB)

    Rubio A, C R

    1996-09-01

    The purpose of this project is to study an option to reduce technology dependence by taking advantage of the technology based companies generated by the organisms called `Companies Incubators`. The first point given, is an introduction about incubation applied to national companies and the experiences had about them. There are also suggested some indicators which can be used to develop the incubator tasks. Once it has been defined the topic about incubation in the country, it is provided information about the items determining the company performance within an incubator. In order to do this, it is shown the way the Instituto Nacional de Investigaciones Nucleares can provide not only its facilities but also qualified personnel working for them. Thus it is given a scheme along with a brief organization description and key personnel for the incubator, stating the functions and responsibilities per each one of the persons who are part of the project direction and leading. The bases for the incubator are stated, as well as the requirements to start-up a company being supported by a company incubator. The key points to have a succesful development for the incubator are: the service it can give as well as the guidelines for companies entrance, which are classified into two sorts of customers, external and internal. It is also included a market research about the main product derived from creating a company incubator, as well as the sub-products, the market area, this is directed to the people who will benefit from it, the supply and demand involved with ININ. The main tool used was Business Plan, which defines its importance within the organization and activities guide, it is also included the Business Plan structure.

  8. Proposal to improve quality in the sale process of products and services through the implementation of the post-sale service, in the National Institute of Nuclear Research (ININ) for year 2000; Propuesta para mejorar la calidad en el proceso de venta de productos y servicios mediante la implementacion del servicio post-venta en el Instituto Nacional de Investigaciones Nucleares (ININ) para el anio 2000

    Energy Technology Data Exchange (ETDEWEB)

    Pliego R, M.T

    2000-07-01

    In the National Institute of Nuclear Research (ININ) it has been able to identify a series of problems in the commercial area just as: lack of publicity, new competitors, customers, loss by the unsatisfied services which are supplied, lack of personnel which dedicates to the sales activity among others. Therefore it has been decided to carry out the implementation of a post-sale service to assure the success of sales through the constant contracting products and services for part of customers totally satisfied, achieving so the fulfilment of the ININ commercialization objectives. Therefore, it was carried out a study which includes: theoretical frame on marketing making emphasis on the management process in this Institute. Also was necessary to know the study object about some aspects such as: its constitution, mission, politics, sales procedures, with the purpose to find their deficiencies and obtaining a scope about ININ products and services which it provides. Therefore was carried out a marketing research with some customers of the Institute obtaining their commentaries. With these analysis elements it has been possible to propose an implementation of a post-sale service and concluding that with this manner, it will be able to assure the complete satisfaction of the customers establishing in the service contract a guarantee with legal sustenance for the fulfilment of this. The services and products offered are: production and sales of radionuclides, radiopharmaceuticals, for diagnostic and theory. Elemental analysis (PIXE, PGE, RbS, NMR,NAA), atomic absorption, X-ray diffraction, X-ray fluorescence, plasma spectroscopy, high resolution mass spectroscopy, gas and mass chromatography, as well as in radiological protection, electron microscopy, irradiation of finished products and raw materials, study of materials and documentation among others. (Author)

  9. Nuclear energy and nuclear weapons

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1983-06-01

    We all want to prevent the use of nuclear weapons. The issue before us is how best to achieve this objective; more specifically, whether the peaceful applications of nuclear energy help or hinder, and to what extent. Many of us in the nuclear industry are working on these applications from a conviction that without peaceful nuclear energy the risk of nuclear war would be appreciably greater. Others, however, hold the opposite view. In discussing the subject, a necessary step in allaying fears is understanding some facts, and indeed facing up to some unpalatable facts. When the facts are assessed, and a balance struck, the conclusion is that peaceful nuclear energy is much more part of the solution to preventing nuclear war than it is part of the problem

  10. Nuclear spin conversion in formaldehyde

    OpenAIRE

    Chapovsky, Pavel L.

    2000-01-01

    Theoretical model of the nuclear spin conversion in formaldehyde (H2CO) has been developed. The conversion is governed by the intramolecular spin-rotation mixing of molecular ortho and para states. The rate of conversion has been found equal 1.4*10^{-4}~1/s*Torr. Temperature dependence of the spin conversion has been predicted to be weak in the wide temperature range T=200-900 K.

  11. Nuclear materials

    International Nuclear Information System (INIS)

    1996-01-01

    In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

  12. Nuclear Law

    International Nuclear Information System (INIS)

    Wiesbauer, Bruno

    1978-01-01

    This book is the first attempt of a comprehensive compilation of national Austrian Nuclear Law (Nuclear Liability Act; Radiation protection Act, Radiation Protection Ordinance, Security Control Act, Act on the uses of Nuclear Energy - Zwentendorf Nuclear Power Plant) and the most important international agreements to which Austria is a party. Furthermore, the book contains the most important Nuclear Liability Conventions to which Austria is not yet a party, but which are applicable in neighbouring; the Paris Convention served as a model for the national Nuclear Liability Act and may be used for its interpretation. The author has translated a number of international instruments into German, such as the Expose des Motifs of the Paris Convention. (NEA) [fr

  13. Nuclear nonproliferation

    International Nuclear Information System (INIS)

    Neubert, M.

    1992-01-01

    The following motion was put before the United Kingdom House of Commons on 3rd February 1992 and agreed; that this House, recognising the potential dangers of the rapidly changing world order, welcomes the recent proposals for substantial reductions in nuclear weaponry, the growing support for the non-proliferation treaty and progress in the implementation of the United Nations Security Council Resolutions concerning the dismantling of Iraqi nuclear, chemical and biological capabilities; urges the Government to play their full part in helping the relevant authorities in the Commonwealth of Independent States to dismantle their nuclear devices, to safeguard their nuclear components and to discourage the proliferation of nuclear expertise; and believes it is of the first importance that Britain retains an effective and credible minimum nuclear deterrent as security in a world where there remain many sources of instability. The record of arguments for and against the motion in the debate is presented. (author)

  14. Nuclear energy

    International Nuclear Information System (INIS)

    Panait, A.

    1994-01-01

    This is a general report presenting the section VII entitled Nuclear Power of the National Conference on Energy (CNE '94) held in Neptun, Romania, on 13-16 June 1994. The problems addressed were those relating to electric power produced by nuclear power plant, to heat secondary generation, to quality assurance, to safety, etc. A special attention was paid to the commissioning of the first Romanian nuclear power unit, the Cernavoda-1 reactor of CANDU type. The communications were grouped in four subsections. These were: 1. Quality assurance, nuclear safety, and environmental protection; 2. Nuclear power plant, commissioning, and operation; 3. Nuclear power plant inspection, maintenance, and repairs, heavy water technology; 4. Public opinion education. There were 22 reports, altogether

  15. Nuclear power

    International Nuclear Information System (INIS)

    King, P.

    1990-01-01

    Written from the basis of neutrality, neither for nor against nuclear power this book considers whether there are special features of nuclear power which mean that its development should be either promoted or restrained by the State. The author makes it dear that there are no easy answers to the questions raised by the intervention of nuclear power but calls for openness in the nuclear decision making process. First, the need for energy is considered; most people agree that energy is the power to progress. Then the historicalzed background to the current position of nuclear power is given. Further chapters consider the fuel cycle, environmental impacts including carbon dioxide emission and the greenhouse effect, the costs, safety and risks and waste disposal. No conclusion either for or against nuclear power is made. The various shades of opinion are outlined and the arguments presented so that readers can come to their own conclusions. (UK)

  16. Nuclear power

    International Nuclear Information System (INIS)

    Porter, Arthur.

    1980-01-01

    This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

  17. ParaChoice Model.

    Energy Technology Data Exchange (ETDEWEB)

    Heimer, Brandon Walter [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Levinson, Rebecca Sobel [Sandia National Lab. (SNL-CA), Livermore, CA (United States); West, Todd H. [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

    2017-12-01

    Analysis with the ParaChoice model addresses three barriers from the VTO Multi-Year Program Plan: availability of alternative fuels and electric charging station infrastructure, availability of AFVs and electric drive vehicles, and consumer reluctance to purchase new technologies. In this fiscal year, we first examined the relationship between the availability of alternative fuels and station infrastructure. Specifically, we studied how electric vehicle charging infrastructure affects the ability of EVs to compete with vehicles that rely on mature, conventional petroleum-based fuels. Second, we studied how the availability of less costly AFVs promotes their representation in the LDV fleet. Third, we used ParaChoice trade space analyses to help inform which consumers are reluctant to purchase new technologies. Last, we began analysis of impacts of alternative energy technologies on Class 8 trucks to isolate those that may most efficaciously advance HDV efficiency and petroleum use reduction goals.

  18. Nuclear astrophysics

    International Nuclear Information System (INIS)

    Haxton, W.C.

    1992-01-01

    The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized

  19. Nuclear physics

    International Nuclear Information System (INIS)

    Patel, S.B.

    1991-01-01

    This book is a simple and direct introduction to the tools of modern nuclear physics, both experimental and mathematical. Emphasizes physical intuition and illuminating analogies, rather than formal mathematics. Topics covered include particle accelerators, radioactive series, types of nuclear reactions, detection of the neutrino, nuclear isomerism, binding energy of nuclei, fission chain reactions, and predictions of the shell model. Each chapter contains problems and illustrative examples. Pre-requisites are calculus and elementary vector analysis

  20. Nuclear energy

    International Nuclear Information System (INIS)

    Hesketh, Ross.

    1985-01-01

    The subject is treated under the headings: nuclear energy -what is it; fusion (principles; practice); fission (principles); reactor types and systems (fast (neutron) reactors as breeders; fast reactors; thermal reactors; graphite-moderated thermal reactors; the CANDU reactor; light water reactors - the BWR and the PWR); the nuclear fuel cycle (waste storage; fuel element manufacture; enrichment processes; uranium mining); safety and risk assessment; the nuclear power industry and the economy (regulating authorities; economics; advantages and disadvantages). (U.K.)

  1. Universidades accesibles para todos

    Directory of Open Access Journals (Sweden)

    Roxana Stupp Kupiec

    2001-01-01

    Full Text Available Este trabajo pretende hacer conciencia sobrelos factores que inciden en la construcción colectiva deuniversidades dispuestas a innovar y transformar suideología, sus políticas, el currículum, los servicios estu-diantiles, la infraestructura física y administrativa y lasestrategias de comunicación e información, bajo el para-digma de la accesibilidad en el entorno. Se hace referen-cia al marco legal internacional y nacional que orientalas acciones que deben planificarse e implementarse enlas instituciones de Educación Superior.En la construcción de universidades accesibles para to-dos se requiere de un cambio en la concepción curricu-lar. Se analizan conceptos como la flexibilidad en la for-mación y el acceso a los planes de estudio para respondera las necesidades educativas de todos los estudiantes. Para promover estas transformaciones se proponen prin-cipios y prácticas tales como la interdisciplinareidad y lainclusión del tema de la discapacidad en todas las carre-ras. Además, se presentan ejemplos de aplicación en dife-rentes áreas del perfil profesional, en la formación deldocente universitario y en actividades de proyección so-cial, vida estudiantil e investigación. En el ámbito estu-diantil, se describen algunos servicios y procesos que sehan desarrollado en la Universidad de Costa Rica

  2. Educando para la ignorancia

    Directory of Open Access Journals (Sweden)

    Miguel Durán

    1996-06-01

    Full Text Available Más que describir una situación particular, los autores buscan con este escrito motivar al estudiante para que asuma posiciones críticas; así como dar un campanazo de alerta a los profesores, en relación a los conocimientos que transmiten a sus alumnos y la forma en que lo hacen; todo con el ánimo de generar verdaderos espacios de reflexión en la universidad.

  3. Nuclear Asia

    National Research Council Canada - National Science Library

    Ferguson, Joseph; Tarleton, Gael

    2004-01-01

    .... This event was an opportunity for policy makers, security analysts, nuclear scientists and engineers, regional experts, and military planners to share perspectives and identify those issues requiring...

  4. Nuclear cardiology

    International Nuclear Information System (INIS)

    Fish, M.B.

    2002-01-01

    Recent advances in nuclear medicine instrumentation and software, including myocardial perfusion imaging, offer increased accuracy in the detection, diagnosis and prognosis of coronary artery disease. (orig.)

  5. Nuclear medicine

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The area of nuclear medicine, the development of artificially produced radioactive isotopes for medical applications, is relatively recent. Among the subjects covered in a lengthy discussion are the following: history of development; impact of nuclear medicine; understanding the most effective use of radioisotopes; most significant uses of nuclear medicine radioimmunoassays; description of equipment designed for use in the field of nuclear medicine (counters, scanning system, display systems, gamma camera); description of radioisotopes used and their purposes; quality control. Numerous historical photographs are included. 52 refs

  6. Nuclear Law

    International Nuclear Information System (INIS)

    Pascal, Maurice.

    1979-01-01

    This book on nuclear law is the first of a series of analytical studies to be published by the French Energy Commission (CEA) concerning all the various nuclear activities. It describes national and international legislation applicable in France covering the following main sectors: the licensing procedure for nuclear installations, the law of the sea and nuclear law, the legal system governing radioisotopes, the transport of radioactive materials, third party liability and insurance and radiation protection. In each chapter, the overall analysis is supplemented by the relevant regulatory texts and by organisation charts in annex. (NEA) [fr

  7. Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1989-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  8. Nuclear power

    International Nuclear Information System (INIS)

    Bupp, I.C.

    1991-01-01

    Is a nuclear power renaissance likely to occur in the United States? This paper investigates the many driving forces that will determine the answer to that question. This analysis reveals some frequently overlooked truths about the current state of nuclear technology: An examination of the issues also produces some noteworthy insights concerning government regulations and related technologies. Public opinion will play a major role in the unfolding story of the nuclear power renaissance. Some observers are betting that psychological, sociological, and political considerations will hod sway over public attitudes. Others wager that economic and technical concerns will prevail. The implications for the nuclear power renaissance are striking

  9. INICIATIVAS PARA EL CAMBIO

    Directory of Open Access Journals (Sweden)

    César Alfonso Defrancisco-Larrañaga

    2013-07-01

    Full Text Available El planeta no atraviesa por su mejor momento en materia de conservación y renovación de sus recursos naturales. Claramente en los últimos tiempos los recursos hídricos han venido haciéndose cada vez menores; el hombre ha notado con preocupación y vivido en carne propia este fenómeno, que de no ser tratado a tiempo, podría atentar contra la existencia misma. Esto lo ha alentado a buscar métodos que sirvan como solución para contrarrestar éste mal y crear conciencia entre sus iguales, para así poder garantizar su permanencia y la de su entorno durante muchas generaciones. En países desarrollados del continente europeo y en algunos lugares de América del norte, el uso de sistemas de reutilización y tratamiento de aguas grises y aprovechamiento de las aguas lluvias se ha convertido en una constante y nos están dando las pautas para poder seguir el ejemplo y así de esta manera poder aportar a la causa ambiental y a su vez crear un ahorro en nuestros gastos mensuales de consumo.

  10. Evaluation of the ICRU operational magnitudes implantation for the photon radiation at the Angra I and Angra II nuclear power plants; Avaliacao da implantacao das grandezas operacionais do ICRU para a radiacao de fotons nas usinas nucleares Angra I e II

    Energy Technology Data Exchange (ETDEWEB)

    Viana, Ronaldo do Nascimento

    2006-07-01

    The measurements of photon radiation field intensity are usually performed by a radiation protection technician trained and having skill in using radiation rate meters. Nowadays, these measurements are reported on exposure quantity and used to protect exposed individuals against the radiation risks while executing their activities. The International Commission on Radiation Units and Measurements - ICRU - defined the operational quantity ambient equivalent dose H{sup *}(10). This quantity is accepted by the scientific community as the best estimative of the protection quantity effective dose, which can not be directly measured. The operational quantity H{sup *}(10) was introduced in Brazilian rules by the National Commission of Nuclear Energy - CNEN (2005a), although its adoption was conditioned to studies of convenience and applicability of implementation. The present work may contribute to these studies, as it presents the evaluation of H{sup *}(10)'s implementation at the Nuclear Central Almirante Alvaro Alberto - CNAAA. The evaluation involved radiological tests - the energy dependence and angular dependence - applied to six types of photon radiation rate meters utilized at the CNAAA, with represent around 83% of the total number of rate meters in use by CNAAA. The result of this evaluation is favorable to the quantity H{sup *}(10)'s implementation. Suggestions are presented in order to update de rate meters and the technical and administrative procedures related to the Laboratory of Calibration of Rate Meters - LCMR, belonging to CNAAA. Thus, it could be possible to perform the calibration of the rate meters at the nuclear installation. The results obtained allows to carry out new evaluations of H{sup *}(10)'s implementation on installations that perform measurements with radiation rate meters on the practice of radiation protection, in order to adopt the H{sup *}(10) quantity in our country. (author)

  11. Methodology for the identification of the factors that can influence the performance of operators of nuclear power plants control room under emergency situations; Metodologia para identificacao dos fatores que afetam o desempenho dos operadores de salas de controle de plantas nucleares, em situacoes de emergencia

    Energy Technology Data Exchange (ETDEWEB)

    Paiva, Bernardo Spitz; Santos, Isaac J.A. Luquetti, E-mail: bernardo_spitz@hotmail.co, E-mail: luquetti@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2009-07-01

    In order to minimize the human errors of the operators in a nuclear power plan control room, during emergency situations, it has to be considered the factors which affect the human performance. Work situations adequately projected, compatible with the necessities, capacities and human limitations, taking into consideration the factors which affect the operator performance . This paper aims to develop a methodology for identification of the factors affecting the operator performance under emergency situation, using the aspects defined by the human reliability analysis focusing the judgment done by specialists

  12. DTN and international cooperation of the Spanish Nuclear Sector in nuclear technology development processes

    International Nuclear Information System (INIS)

    Acero, M.

    1995-01-01

    The Spanish electrical utilities with interests in the Nuclear Sector-IBERDROLA, ENDESA,FUERZAS ELECTRICAS DE CATALU=A5A (FECSA), UNION ELECTRICA FENOSA S.A., COMPA=A5IA SEVILLANA DE ELECTRICIDAD S.A., AND HIDROELECTRICA DEL CANTABRICO S.A.-created on September 26, 1994 the ''Agrupacion Electrica para el Desarrollo Tecnologico Nuclear, A.I.E. (DTN)'' (Electrical Society for Nuclear technology Development A.I.E.) for the purpose of promoting and managing Nuclear Nechnology Development, and integrating and coordinating the efforts of the Nuclear Electrical Sector with industrial companies and other related institutions in spain and abroad. This mission is primarily accomplished by establinhing a common strategy for the Nuclear Electrical Sector in the different areas of responsibility of DTN, centralizing actions by implementing a clear and coherent policy, and ensuring the presence of the entire Electrical Sector in all those fora deemed to be strategic to the Nuclear Sector

  13. Nuclear stress test

    Science.gov (United States)

    ... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

  14. 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.

  15. Communication received from the Permanent Mission of Denmark to the Agency regarding Guidelines for the Export of Nuclear Material, Equipment and Technology; Comunicacion recibida de la Mision Permanente de Dinamarca ante el Organismo relativa a las directrices para la exportacion de materiales, equipos y tecnologia nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-01-02

    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 ha recibido una nota verbal de la Mision Permanente de Dinamarca, de fecha 1 de diciembre de 2005, en la que se facilita informacion sobre las politicas y practicas del Gobierno de Dinamarca con respecto a la exportacion de materiales, equipos y tecnologia nucleares. Atendiendo a los deseos expresados al final de la nota verbal, se adjunta al presente documento el texto de dicha nota. El apendice a que se hace referencia en la nota verbal se publico previamente como INFCIRC/254/Rev.7/pt.1.

  16. Use of Gray code in PBIL algorithm for application in recharge of nuclear fuels; Utilização do código Gray no algoritmo PBIL para aplicação na recarga de combustíveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Nast, Fernando N.; Silva, Patrick V.; Meneses, Anderson A. M., E-mail: anderson.meneses@pq.cnpq.br [Universidade Federal do Oeste do Para (UNIOESTE), Santarem, PA (Brazil). Lab. de Inteligencia Computacional; Schirru, Roberto, E-mail: schirru@lmp.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Lab. de Monitoracao de Processos

    2017-07-01

    The In-Core Fuel Management Optimization (OGCIN) problem, or design optimization of Load Patterns (PCs) are denominations for the optimization problem associated with the refueling operation in a reactor nuclear. The OCGIN is considered a problem of difficult resolution, considering aspects of combinatorial optimization and calculations of analysis and physics of reactors. In order to validate algorithms for the OGCIN solution, we use benchmark problems such as the Travelling Salesman Problem (TSP), because it is considered, like OGCIN, an NP-difficult problem. In the present work, we implemented the Population-Based Incremental Learning (PBIL) algorithm with binary coding and Gray coding and applied them to the optimization of the symmetric PCV Oliver30 and Rykel48 asymmetric PCV and implemented only the Gray coding in the OGCIN application of the cycle 7 of the Angra-1 Nuclear Plant, where we compared its performance with binary coding in. The results on average were 1311 and 1327 ppm of Boron for the binary and Gray codifications respectively, emphasizing that the binary codification obtained a maximum value of 1330 ppm, while the Gray code obtained a value of 1401 ppm, showing superiority, since the Boron concentration is an indicator of the PC cycle extension.

  17. 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).

  18. Nuclear physics for nuclear fusion

    International Nuclear Information System (INIS)

    Li Xingzhong; Liu Bin; Wei Qingming; Ren Xianzhe

    2004-01-01

    The D-T fusion cross-section is calculated using quantum mechanics with the model of square nuclear potential well and Coulomb potential barrier. The agreement between ENDF data and the theoretically calculated results is well in the range of 0.2-280 keV. It shows that the application of Breit-Wigner formula is not suitable for the case of the light nuclei fusion reaction. When this model is applied to the nuclear reaction between the charged particles confined in a lattice, it explains the 'abnormal phenomena'. It implies a prospect of nuclear fusion energy without strong nuclear radiations

  19. Nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  20. Nuclear safety

    International Nuclear Information System (INIS)

    1991-02-01

    This book reviews the accomplishments, operations, and problems faced by the defense Nuclear Facilities Safety Board. Specifically, it discusses the recommendations that the Safety Board made to improve safety and health conditions at the Department of Energy's defense nuclear facilities, problems the Safety Board has encountered in hiring technical staff, and management problems that could affect the Safety Board's independence and credibility

  1. Nuclear violence

    International Nuclear Information System (INIS)

    Mullen, R.K.

    1987-01-01

    A great deal of attention has been paid in the past decade or so to the characteristics of terrorists and their apparent goals and objectives, capabilities, and evolving strategy and tactics with respect to nuclear terrorism. In contrast, little has been said about the procedural aspects of nuclear terrorism, and even less about the way in which such endeavors can fail. This latter omission is important because it bears directly on the ability to evaluate credibly the potential for nuclear terrorism. Here, the author addresses the requirements inherent in acquiring a nuclear explosive capability by three routes: separation of plutonium from irradiated light or heavy water reactor (LWR or HWR) fuel, processing, or use of separated fissile material, and theft of a nuclear weapon. In addition, he deals with other potential acts of nuclear terrorism: sabotage of power reactors, uranium enrichment facilities and spent nuclear fuel in transport, and dispersal of radioactive materials, in particular, plutonium. He specifically does not look at the design or production of a nuclear weapon. Finally, the discussion here assumes that the terrorist is subnational; that is, a nation is not involved. Also, the discussion of subnational participation does not address the possibility of collusion with insiders

  2. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  3. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2003-01-01

    This chapter discuss on nuclear power and its advantages. The concept of nucleus fission, fusion, electric generation are discussed in this chapter. Nuclear power has big potential to become alternative energy to substitute current conventional energy from coal, oil and gas

  4. Nuclear energy

    International Nuclear Information System (INIS)

    1978-01-01

    This brochure is intended as a contribution to a better and more general understanding of one of the most urgent problems of present society. Emphasis is laid on three issues that are always raised in the nuclear debate: 1) Fuel cycle, 2) environmental effects of nuclear power plants, 3) waste disposal problems. (GL) [de

  5. Nuclear pollution

    International Nuclear Information System (INIS)

    Ramade, Francois

    1979-01-01

    In this chapter devoted to nuclear pollution the following topics were studied: fundamentals of radiobiology (ecological importance of the various radioisotopes, biological effects of ionizing radiations); ecological effects of radioactive fallout (contamination of atmosphere, terrestrial ecosystems, oceans). The electronuclear industry and its environmental impact. PWR type reactors, fuel reprocessing plants, contamination of trophic chains by radionuclides released in the environment from nuclear installations [fr

  6. Nuclear lifetimes

    International Nuclear Information System (INIS)

    Caraca, J.M.G.

    1976-01-01

    The importance of the results obtained in experiments of measurement of lifetimes for a detailed knowledge of nuclear structure is referred. Direct methods of measurement of nuclear lifetimes are described, namely, electronic methods, recoil-distance method, doppler shift atenuation method and blocking-method. A brief reference is made to indirect methods for measurement of life-times

  7. Nuclear facts

    International Nuclear Information System (INIS)

    1982-01-01

    The subject is discussed as follows: the case for using nuclear energy (Britain's energy needs; energy policy); safety; transport of spent fuel; radiation (natural radioactivity); environment (land use of nuclear power plants; storage and disposal of radioactive wastes). (U.K.)

  8. Nuclear measurements

    International Nuclear Information System (INIS)

    Schenkel, R.

    2005-01-01

    Nuclear measurements play a fundamental role in the development of nuclear technology and the assurance of its peaceful use. They are also required in many non-power nuclear applications such as in nuclear medicine, agriculture, environmental protection, etc. This presentation will show examples of most recent advances in measurement methodology or technology in the areas described below. The Generation IV International Forum has selected six innovative reactor systems as candidates for a next generation of sustainable, economic and safe nuclear energy systems. The choice of the best options relies heavily on the availability of accurate nuclear data that can only be obtained, in an international effort, using highly specialised facilities. Significant efforts are being directed towards the partitioning and transmutation of highly active nuclear waste. Different concepts involving fast reactors or accelerator-driven systems are being studied in view of their transmutation capabilities. State of the art equipment has been developed to assess basic properties of nuclear fuel at very high burn-up; some fine examples of this work will be shown. Physical and chemical methods play a crucial role in the detection and identification of radioisotopes used in various stages of the nuclear fuel cycle. Radiation measurement techniques are used, for example, to monitor the quantities of uranium, plutonium and other actinide elements in fuel enrichment and reprocessing facilities. Another field of application of physical and chemical methods is the characterisation of nuclear material seized from illicit trafficking. Seized material has to be analysed in order to obtain clues on its origin and intended use and to prevent diversion of nuclear material from the same source in the future. A recent highlight in basic physics relates to nuclear fission and transmutation with high intensity lasers. Ultra-fast high intensity lasers can produce high energy (tens of MeV) photons through

  9. Nuclear rockets

    International Nuclear Information System (INIS)

    Sarram, M.

    1972-01-01

    Nuclear energy has found many applications in space projects. This article deals with these applications. The first application is the use of nuclear energy for the production of electricity in space and the second main application is the use of nuclear energy for propulsion purposes in space flight. The main objective is to develop a 75000 pound thrust flight engine call NERVA by heating liquid hydrogen, in a nuclear reactor, from 420F to 4000 0 F. The paper describes in detail the salient features of the NERVA rocket as well as its comparison with the conventional chemical rockets. It is shown that a nuclear rocket using liquid hydrogen as medium is at least 85% more efficient as compared with the chemical rockets such as those used for the APOLLO moon flight

  10. Nuclear rockets

    Energy Technology Data Exchange (ETDEWEB)

    Sarram, M [Teheran Univ. (Iran). Inst. of Nuclear Science and Technology

    1972-02-01

    Nuclear energy has found many applications in space projects. This article deals with these applications. The first application is the use of nuclear energy for the production of electricity in space and the second main application is the use of nuclear energy for propulsion purposes in space flight. The main objective is to develop a 75000 pound thrust flight engine called NERVA by heating liquid hydrogen in a nuclear reactor. The paper describes in detail the salient features of the NERVA rocket as well as its comparison with the conventional chemical rockets. It is shown that a nuclear rocket using liquid hydrogen as medium is at least 85% more efficient as compared with the chemical rockets such as those used for the APOLLO moon flight.

  11. Nuclear haematology

    International Nuclear Information System (INIS)

    Masjhur, J.S.

    1992-01-01

    Nuclear techniques have been applied to study diagnose and treat various haematological disorders for more than five decades. Two scientists are regarded as pioneers in this field, i.e. John Lawrence who in 1938 used 32 P to treat chronic myeloid leukaemia and George Hevessy who used 32 P labelled erythrocytes to measure blood volume in 1939. At present, many nuclear medicine procedures are available for diagnosis and therapy of a variety of haematological disorders. Although nuclear techniques are somewhat complex, they give direct and quantitative assessment of the kinetics of blood elements as compared to other non-isotopic haematological tests. Basically, equipment required for nuclear haematology is very simple such as well scintillation counters to measure radioactivity in blood samples. More sophisticated equipment like rectilinear scanner or gamma camera is required when imaging is necessary. An overview of the basic principles and clinical applications of nuclear haematology is given

  12. Nuclear forensics

    International Nuclear Information System (INIS)

    Venugopal, V.

    2010-01-01

    Increasing threat by terrorists for a possible nuclear attack is particularly alarming in recent years. The likelihood of such an event is highly uncertain but cannot be ruled out. The consequence of such an event would be highly disastrous and the implications could be far-reaching both socially and politically. It is feared that significant amount of nuclear weapons materials may be kept under poor security. Therefore, there is a greater demand with utmost priority to curb nuclear terrorism by adapting proper security measures. One of the most important measures is to stop illicit trafficking of nuclear materials which are the source of building nuclear explosive devices. According to the IAEA illicit trafficking database (ITDB) report, a total number of 252 incidents were reported in 2006, of which 150 occurred in 2006 and the remaining 102 had taken place prior to that year, mainly in 2005

  13. Nuclear Safety

    International Nuclear Information System (INIS)

    1978-09-01

    In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

  14. Nuclear proliferation

    International Nuclear Information System (INIS)

    Stencel, S.

    1978-01-01

    The terms and reactions to President Carter's nuclear policy, culminating in the 1978 Nuclear Non-Proliferation Act, are reviewed and analyzed. The new law increases restrictions on nuclear exports, encourages continued use of light water reactors in preference to plutonium-fueled reactors, and emphasizes technical solutions to proliferation problems. Critics of the law point out that it will hurt U.S. trade unfairly, that other countries do not have as many fuel options as the U.S. has, and that nuclear sales have as many political and economic as technical solutions. Compromise areas include new international safety guidelines, the possibility of an international nuclear fuel bank, and a willingness to consider each case on its merits. 21 references

  15. Nuclear privatization

    International Nuclear Information System (INIS)

    Jeffs, E.

    1995-01-01

    The United Kingdom government announced in May 1995 plans to privatize the country's two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain's nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross

  16. Nuclear haematology

    Energy Technology Data Exchange (ETDEWEB)

    Masjhur, J S

    1993-12-31

    Nuclear techniques have been applied to study diagnose and treat various haematological disorders for more than five decades. Two scientists are regarded as pioneers in this field, i.e. John Lawrence who in 1938 used {sup 32}P to treat chronic myeloid leukaemia and George Hevessy who used {sup 32}P labelled erythrocytes to measure blood volume in 1939. At present, many nuclear medicine procedures are available for diagnosis and therapy of a variety of haematological disorders. Although nuclear techniques are somewhat complex, they give direct and quantitative assessment of the kinetics of blood elements as compared to other non-isotopic haematological tests. Basically, equipment required for nuclear haematology is very simple such as well scintillation counters to measure radioactivity in blood samples. More sophisticated equipment like rectilinear scanner or gamma camera is required when imaging is necessary. An overview of the basic principles and clinical applications of nuclear haematology is given

  17. para mejorar el %R

    Directory of Open Access Journals (Sweden)

    Alfredo Díaz Mata

    2001-01-01

    Full Text Available En este trabajo se revisan dos indicadores técnicos bursátiles que están estrechamente relacionados, el oscilador estocástico %K de Lane y el oscilador %R de Williams; asimismo, se evalúa el uso de dos mecanismos asociados con el primero y que no suelen utilizarse con el %R: el proceso de frenado (slowing y el uso de un promedio móvil del propio oscilador estocástico como disparadores de señales de compra y de venta. Realizando simulaciones con 27 acciones y el Índice de Precios y Cotizaciones de la Bolsa Mexicana de Valores se verifica la hipótesis principal y se comprueba que, efectivamente, en muchos casos, el uso del proceso de frenado con el oscilador %R de Williams permite tomar mejores decisiones. Por otro lado, se concluye que de los dos disparadores de señales el que mejor funciona, tanto para %K como para %R es el uso de cotas inferior y superior. Este artículo surgió en el curso de una investigación sobre el análisis técnico bursátil de acciones que se puede realizar en su totalidad por computadora y que, esencialmente, excluye el análisis gráfico. Uno de los propósitos del estudio es determinar si es posible, y bajo qué mecanismos, establecer un sistema de análisis bursátil que le permita al inversionista tomar decisiones de inversión en acciones en la Bolsa Mexicana de Valores sin tener que emplear la considerable cantidad de tiempo que es necesario para el análisis gráfico tradicional. Durante este estudio se realizó un análisis preliminar de unos 120 indicadores técnicos para, por un lado, conocerlos con cierto detalle y, por otra parte, aislar aquellos que prometían ser de utilidad para el objetivo de la investigación. Fue en este proceso cuando se detectó que existen dos indicadores que están relacionados y que permiten un análisis por separado que tiene, cuando menos, dos ventajas. En primer lugar está el placer que da a quien gusta de estos temas encontrarse con indicadores que, de acuerdo

  18. Inmunopotenciadores para la acuicultura

    Directory of Open Access Journals (Sweden)

    Rocmira Pérez

    2014-04-01

    Full Text Available La acuicultura es una de las actividades económicas de mayor crecimiento para la producción de alimentos. Uno de sus principales retos es la obtención de grandes volúmenes de producción con la mayor calidad posible. Esto conlleva a una reducción de la aplicación de antibióticos y productos quimioterapéuticos. Una de las estrategias más prometedoras es la aplicación de inmunopotenciadores, principalmente en los cultivos intensivos. El objetivo de este trabajo fue revisar los principales inmunopotenciadores, así como las tendencias y retos de su uso mundial. Se resumen las particularidades moleculares y funcionales de los mismos y se hace énfasis en los más estudiados: levamisol, ß-glucanos, lipopolisacárido, vitamina C, extractos de plantas y hormonas. Todos estos compuestos de naturaleza heterogénea inciden mayoritariamente en los componentes de la inmunidad innata de los peces, fortaleciendo y potenciando la resistencia a enfermedades; adicionalmente algunos de ellos tienen funciones antiestrés y favorecen su crecimiento. Se concluye que los inmunopotenciadores constituyen una estrategia viable para reducir las pérdidas por problemas sanitarios en el sector de la acuicultura; pero aún quedan por solucionar aspectos como la vía de administración y la etapa de inmunización adecuada para cada especie y tipo de cultivo.

  19. Ha vuelto para mirarnos

    OpenAIRE

    Casalderrey, Francisco

    2008-01-01

    En cada entrega analizaremos un cuadro, mirándolo con ojos matemáticos. Con esa particular mirada, fruto de nuestra propia (de)formación. Y desde ese punto de vista haremos paseos por el arte y las matemáticas. Espero que el lector, como hago yo mismo, disfrute descubriendo más allá de lo que a simple vista distinguiría cualquiera. Al fin de cuentas, el arte, como las matemáticas, han sido creados para hacernos disfrutar.

  20. Interfaces para control cerebral

    OpenAIRE

    Spinelli, Enrique Mario

    2000-01-01

    La función de una interfaz para control cerebral basada en señales de electroencefalograma (EEG), en forma general denominada BCI (Brain control Interface), es establecer un enlace directo entre el cerebro y una máquina, sin utilizar acciones motoras directas. Una BCI permite realizar operaciones simples a partir de la interpretación de las señales de EEG. Su desarrollo está principalmente orientado hacia la ayuda a personas con discapacidades motoras severas, que poseen deterioros en el sist...

  1. Comunicar para la salud

    Directory of Open Access Journals (Sweden)

    Lic. Eva Bocco

    1998-01-01

    Full Text Available Con este trabajo quiero plantearles una inquietud en torno al rol que nos cabe a los comunicadores en el área de la salud desde la perspectiva de la comunicación para la salud. ¿Se puede pensar la salud pública desvinculada de la comunicación? ¿La comunicación es posible sin la existencia de salud en la comunidad? ¿Qué puede hacer un comunicador en el ministerio de salud? ¿Puede un estado desarrollar políticas de salud sin la presencia de la comunicación?

  2. Democracia para ciudadanos ciborgs

    Directory of Open Access Journals (Sweden)

    Juan Varela

    2007-07-01

    Full Text Available Enumera los instrumentos imprescindibles de la ciberpolítica para campañas electorales en España, cuando se renovaron los cargos municipales. La política vuelve a ser personal cuando ciudadanos y políticos se hablan cara a cara y cita varios ejemplos, reconociendo la recuperación de la comunicación directa. La ciberdemocracia es muy exigente. Los políticos prefieren la magia de la imagen. La sociedad no sabe como detener la propaganda viral que bombardea a los buscadores de red.

  3. Democracia para ciudadanos ciborgs

    OpenAIRE

    Juan Varela

    2007-01-01

    Enumera los instrumentos imprescindibles de la ciberpolítica para campañas electorales en España, cuando se renovaron los cargos municipales. La política vuelve a ser personal cuando ciudadanos y políticos se hablan cara a cara y cita varios ejemplos, reconociendo la recuperación de la comunicación directa. La ciberdemocracia es muy exigente. Los políticos prefieren la magia de la imagen. La sociedad no sabe como detener la propaganda viral que bombardea a los buscadores de red.

  4. Nuclear questions

    Energy Technology Data Exchange (ETDEWEB)

    Durrani, M. [Physics World (United Kingdom)

    2006-01-01

    The future of nuclear power has returned to centre stage. Freezing weather on both sides of the Atlantic and last month's climate-change talks in Montreal have helped to put energy and the future of nuclear power right back on the political agenda. The issue is particularly pressing for those countries where existing nuclear stations are reaching the end of their lives. In the UK, prime minister Tony Blair has commissioned a review of energy, with a view to deciding later this year whether to build new nuclear power plants. The review comes just four years after the Labour government published a White Paper on energy that said the country should keep the nuclear option open but did not follow this up with any concrete action. In Germany, new chancellor and former physicist Angela Merkel is a fan of nuclear energy and had said she would extend the lifetime of its nuclear plants beyond 2020, when they are due to close. However, that commitment has had to be abandoned, at least for the time being, following negotiations with her left-wing coalition partners. The arguments in favour of nuclear power will be familiar to all physicists - it emits almost no carbon dioxide and can play a vital role in maintaining a diverse energy supply. To over-rely on imported supplies of oil and gas can leave a nation hostage to fortune. The arguments against are equally easy to list - the public is scared of nuclear power, it generates dangerous waste with potentially huge clean-up costs, and it is not necessarily cheap. Nuclear plants could also be a target for terrorist attacks. Given political will, many of these problems can be resolved, or at least tackled. China certainly sees the benefits of nuclear power, as does Finland, which is building a new 1600 MW station - the world's most powerful - that is set to open in 2009. Physicists, of course, are essential to such developments. They play a vital role in ensuring the safety of such plants and developing new types of

  5. Use of microcontroller in gamma-ray spectrometer construction using NaI(Tl) sensor, with emphasis in multichannel analyzer, to applications in nuclear and environmental geophysics; Uso de microcontrolador na construcao de espectrometro gama com sensor de NaI(Tl), com enfase em analisador multicanal, para aplicacao em geofisica nuclear e ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Nilton

    2005-07-01

    In this work of nuclear geophysical instrumentation the main purpose was the development of a gamma-ray spectrometer prototype with multi channel analyzer, since the spectroscopic amplifier until your firmware. The heart of the digital part was an ATMEL 8 bits microcontroller (AT89S8252). All circuits were made and assembled in the Laboratory of Applied Geophysical Instrumentation (LIGA) of IAG-USP. A microcontroller software was completely developed in C ANSI language using the Small Device C Compiler version 2.4.8, that is a free software distributed under General Public License (GPL). At first, microcontroller was used to change all digital circuit of one classic SCINTREX GAD-6 differential gamma-ray spectrometer. Measurement times with order of 2 days became possible, and it could work in non climate ambient. Then, after this stage, had been started the development of a multichannel analyzer (MCA) working in pulse height analyzer mode with 4096 channels capacity, to use in many kinds of nuclear detection. Besides it, was developed an automatic gain system for photopeak stabilization, by the use of one radioactive source ({sup 133}Ba). This automatic gain system is very important in the case of NaI(Tl) scintillometric detectors, due PMT sensitivity with temperature and aging of some laboratory electronic circuits. Two power supplies with high stability, using pulse width modulation (PWM) techniques were developed, in order to all system became free of electrical line break off. One PWM power polarizes a photo multiplier tube (PMT) with high voltage and another supplies remaining developed circuits. Calibration in energy using standards sources {sup 137}Cs and {sup 60}Co showed that gamma detector developed has a good linearity and low thermal drift, even working in absent of air-conditioned. Concentrations measurements of K, U and Th were made in samples of soils, vegetables, etc. (author)'

  6. Investigation on the use digital controls instead of PID analog controls in the level control of steam generators of nuclear power PWR; Investigacao sobre o uso de controladores digitais em substituicao aos controladores analogicos PID para o controle de nivel de geradores de vapor de centrais nucleares PWR

    Energy Technology Data Exchange (ETDEWEB)

    Alvarenga, Marco Antonio Bayout

    2012-07-01

    The aim of this study is to identify current alternatives for the implementation of digital controllers in the level control of steam generators of nuclear power PWR (Pressurized Water Reaetor). It is intended to identify the types of digital controls that are available from the theoretical and conceptual viewpoints for this purpose. We investigate the advantages and disadvantages of each controller model. From this assessment are pointed the most suitable models in hierarchical scale. This evaluation also serves to suggest possible types of control installation as a whole, where the level control of the steam generators becomes just one of many controls that are part of the plant. In this case, the use of digital controls allows the non-linear and multivariable treatment which is characteristic of complex systems, such as the nuclear power generation. The treatment of nonlinearities and multivariable aspects allows a more detailed study of the stability of these plants when they are subject to transients or several accidents, such as the case of losing external power of transients. In the specific case of steam generators, the instabilities result from the emergence of the shrink and swell phenomenas, depending on the load variations of thermonuclear plant. The application of several types and digital controllers, considering these inherent characteristics of the level control of steam generators, allows to infer which types of controllers are more appropriate to treat instabilities of this type and to make conjectures in its use for the cases of more complex instabilities, considering the integration of all nucleus-plant controls.

  7. Nuclear energy

    International Nuclear Information System (INIS)

    Rippon, S.

    1984-01-01

    Do we need nuclear energy. Is it safe. What are the risks. Will it lead to proliferation. The questions are endless, the answers often confused. In the vigorous debates that surround the siting and operation of nuclear power plants, it is all too easy to lose sight of the central issues amid the mass of arguments and counter-arguments put forward. And there remains the doubt, who do we believe. This book presents the facts, simply, straightforwardly, and comprehensibly. It describes the different types of nuclear reactor, how they work, how energy is produced and transformed into usable power, how nuclear waste is handled, what safeguards are built in to prevent accident, contamination and misuse. More important, it does this in the context of the real world, examining the benefits as well as the dangers of a nuclear power programme, quantifying the risks, and providing an authoritative account of the nuclear industry worldwide. Technically complex and politically controversial, the contribution of nuclear energy to our future energy requirements is a crucial topic of our time. (author)

  8. Serie: Madera para construcción Acabados para madera

    OpenAIRE

    Sáenz-Muñoz, Marta; Instituto Tecnológico de Costa Rica

    2012-01-01

    Durante mucho tiempo, la madera ha sido utilizada como material de construcción para resolver principalmente objetivos estructurales; sin embargo, actualmente, el uso de la madera ha tomado mucho auge en la estética de las construcciones, para brindar apariencia y calidez. En la actualidad, el mercado ofrece una amplia gama productos para dar diversos “acabados” a la madera, los cuales sirven para resaltar la belleza de algunas de ellas, realzar características como el color y la veta, o bien...

  9. Nuclear Hostages

    International Nuclear Information System (INIS)

    Cooper, C.L.

    1978-01-01

    The global spread of nuclear reactors for the production of energy seems inevitable. Nuclear power plants will be supplied--if not by the United States, then by one of several other exporters. But other aspects of this development are less certain. One is the relationship between proliferation of nuclear energy plants and that of nuclear weapons. Another is the actual constraint that such vulnerable potential targets as nuclear power plants would have on would-be aggressors. In the last analysis, this would depend on the rationality of a nation's leadership. What can be said for the concept of nuclear power plants as potential hostages is that by installing a reactor on its territory, a country increases its vulnerability to grave, possibly unacceptable damage in the event of war. As a result, that nation's leaders might be inclined to raise the threshold of their sensitivity to provocation by neighbors and to restrain their own inclinations toward aggression. Admittedly this is a frail substitute for robust international agreements, but in the present order of things it is not a trivial consideration. Many incidents once regarded by the great powers as easi belli have more recently been either resolved by diplomacy or ignored altogether. The idea must not be pressed too far. The export of a nuclear power plant to a Third World country cannot be advocated simply as a means to constrain its own military adventurism. Aside from the promise of a vast increase in energy supply for developing nations, nuclear powered generating stations could actually improve relations among countries. The risk of widespread radioactive contamination by nuclear power plants hit by even conventional bombs could introduce a positive new element into the military calculations of powers outside the NATO-Warsaw Pact arena. As they balance military and diplomatic solutions to local conflicts, moderation rather than bellicosity might become the better part of valor

  10. Nuclear medicine

    International Nuclear Information System (INIS)

    Kand, Purushottam

    2012-01-01

    Nuclear medicine is a specialized area of radiology that uses very small amounts of radioactive materials to examine organ function and structure. Nuclear medicine is older than CT, ultrasound and MRI. It was first used in patients over 60-70 years ago. Today it is an established medical specialty and offers procedures that are essential in many medical specialities like nephrology, pediatrics, cardiology, psychiatry, endocrinology and oncology. Nuclear medicine refers to medicine (a pharmaceutical) that is attached to a small quantity of radioactive material (a radioisotope). This combination is called a radiopharmaceutical. There are many radiopharmaceuticals like DTPA, DMSA, HIDA, MIBI and MDP available to study different parts of the body like kidneys, heart and bones etc. Nuclear medicine uses radiation coming from inside a patient's body where as conventional radiology exposes patients to radiation from outside the body. Thus nuclear imaging study is a physiological imaging, whereas diagnostic radiology is anatomical imaging. It combines many different disciplines like chemistry, physics mathematics, computer technology, and medicine. It helps in diagnosis and to treat abnormalities very early in the progression of a disease. The information provides a quick and accurate diagnosis of wide range of conditions and diseases in a person of any age. These tests are painless and most scans expose patients to only minimal and safe amounts of radiation. The amount of radiation received from a nuclear medicine procedure is comparable to, or often many times less than, that of a diagnostic X-ray. Nuclear medicine provides an effective means of examining whether some tissues/organs are functioning properly. Therapy using nuclear medicine in an effective, safe and relatively inexpensive way of controlling and in some cases eliminating, conditions such as overactive thyroid, thyroid cancer and arthritis. Nuclear medicine imaging is unique because it provides doctors with

  11. Nuclear inheritance

    International Nuclear Information System (INIS)

    Delpech, Therese

    1997-01-01

    Since the end of the East-West confronting, the nuclear weapon issue has been focused in an international debate with obvious repercussions in Europe, because it is the European continent which indicated first the significance of nuclear deterrence. This debate refers first upon the past, as the German unification allowed capturing numerous documents of Warsaw treaty which revealed the intentions and the plans of Soviet Union during the cold war, and secondly concerns the future, since the role of nuclear weapons must be re-thought in a new context. This is the subject of this book, which refers also to the problem of the nuclear proliferation in the world and evolution of different countries in a political and regional context. The extension of the non-proliferation treaty for an undefined duration, in May 1995, is a incontestable victory because this treaty rules the renouncement to nuclear weapons of 185 countries. However, it does not solve most sensible problems like the Iraq case, for which a specific inspection regime has been instituted, or the case of Iran, which is suspected to acquire the bomb, although no clear evidence has been provided up to now. This is also the case of Israel, India and Pakistan which allege plainly their willingness of keeping open, from security reasons, their nuclear option. The content is displayed in five chapters: 1. Introduction; 2. The role of the nuclear weapons after the cold war; 3. The nuclear proliferation at crossroads; 4. Undefined extension of the NPT, a striking but fragile victory; 5. Conclusions. An appendix containing the text of the Nuclear Weapon Non-Proliferation Treaty and a chronology are added

  12. "Colaborar para Competir"

    Directory of Open Access Journals (Sweden)

    Martha Liliana Hijuelos-Cárdenas

    2015-06-01

    Full Text Available De acuerdo con Michael Porter, los Clusters se definen como “Una agrupación de empresas e instituciones relacionadas entre sí, pertenecientes a un mismo sector o segmento de mercado, que se encuentran próximas geográficamente y que colaboran para ser más competitivas”. Los Clusters son en última instancia una herramienta de competitividad basada en la cooperación de sus miembros, y es una de las estrategias recientes, en el país, para incrementar la productividad y competitividad y las apuestas productivas desde el nivel local. Y es precisamente esta cercanía geográfica de las empresas de un mismo sector, lo que a la vez que genera la competencia entre ellas, también les facilita el acceso a insumos y a conocimientos específicos y en última instancia les permite promover la innovación.

  13. Principios teatrales para docentes

    Directory of Open Access Journals (Sweden)

    R. Irene Arroyo Zúñiga

    2005-01-01

    Full Text Available Este trabajo pretende dar herramientas a los docentes para que puedan utilizarlas como parte de las actividades dentro de un plan de elección, en cualquier disciplina. Además encontrará una exposición de los elementos que componen el arte de la representación escénica, como son: 1. Expresión corporal; es la capacidad de expresar emociones partiendo únicamente de nuestro cuerpo. 2. Impostación; es la habilidad de proyectar la voz sin lastimar las cuerdas vocales. 3. Dicción; es la pronunciación correcta de las palabras. 4. Actuación; es la posibilidad de crear un personaje partiendo de los recursos expresivos y de la forma natural en que el alumno acostumbra a reaccionar. Técnica de improvisación, en éste artículo propongo una serie de seis pasos que pueden ser de gran ayuda a la hora de usar el teatro como recurso didáctico. El teatro a lo largo de la historia ha sido usado para transmitir conocimientos, valores, creencias y todo aspecto inherente a los individuos y su entorno social. Por lo tanto debemos aprovechar al máximo los beneficios que nos ofrece el teatro como educadores

  14. Nuclear energy

    International Nuclear Information System (INIS)

    Hladky, S.

    1985-01-01

    This booklet appeared in a series on technical history. It tries to communicate some of the scientific, technical and social stresses, which have been connected with the application of nuclear energy since its discovery. The individual sections are concerned with the following subjects: the search for the 'smallest particles'; the atomic nucleus; nuclear fission; the 'Manhattan Project'; the time after this - from the euphoria of the 1950's via disillusionment and change of opinion to the state of nuclear energy at the start of the 1980's. The booklet contains many details and is generously illustrated. (HSCH) [de

  15. Nuclear transport

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    During january and february 2003, a unique event concerning nuclear transport was reported and rated 1 on the INES scale. This event concerns the absence of a maintenance operation on a shipping cask. This shipping cask was used for several years for nuclear transport inside La-hague site before being re-assigned to transport on public thoroughfare. The re-assignment of the cask should have been preceded and conditioned by a maintenance operation whose purpose is to check the efficiency of its radiation shield. During this period 2 on-site inspections concerning the transport of nuclear materials were performed. (A.C.)

  16. Nuclear energy

    International Nuclear Information System (INIS)

    Luxo, Armand.

    1977-01-01

    The reasons and conditions of utilizing nuclear power in developing countries are examined jointly with the present status and future uses already evaluated by some organizations. Some consequences are deduced in the human, financial scientific and technological fields, with provisional suggestions for preparing the nuclear industry development in these countries. As a conclusion trends are given to show how the industrialized countries having gained a long scientific and technological experience in nuclear energy can afford their assistance in this field, to developing countries [fr

  17. Nuclear questions

    International Nuclear Information System (INIS)

    Hohlfeld, W.

    1977-01-01

    This brochure 'nuclear problems' deals with the attitude of the protestant church in the region around the northern Elbe towards further quantitative economic growth, esp. nuclear energy, with the following essays: preaching the Gospel in an environment in danger: the Christian occident and the problems of the third world, facing the problems of exhausted supplies, the role of the prophet, problem of environment - a problem of theology, the political dimension, against ATW, signal Brokdorf, strange effects (defense of the church from unqualified teachings by non-professionals), Christian liberty, church and nuclear energy, violence and robes. (HP) [de

  18. Rotterdam Nuclear

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    In 1965 Rotterdam Nuclear received an order for the design, supply of materials, manufacture, testing, inspection and preparation for shipment of one 450MW Boiling Water Reactor pressure vessel. This was one of the first orders for a reactor pressure vessel, ever obtained by a European Manufacturer. The Company has since supplied 19 reactor pressure vessels for nuclear power stations, having a total weight of about 10,000,000kg. The nuclear power stations in which these are installed represent an electrical output of about 15,000MW and they are located in seven different countries (USA, Spain, Switzerland, Argentina, Sweden, Germany and the Netherlands). (Auth.)

  19. Nuclear law

    International Nuclear Information System (INIS)

    Bringuier, P.

    2009-01-01

    The object of this report is to present the evolution of the nuclear law during the period from 2006 to 2008, period that was characterized in France by a real rewriting from the implementation of a control authority. The prescriptive backing of nuclear activities has been deeply changed by numerous texts. In this first part are presented: (1) the institutional aspects, (2) openness and public information, (7) radioactive wastes and (9) liability and insurance. In a next publication will be treated: (3) safety and radiation protection; (4) nuclear matter, inspection, physical protection; (5) transports; (6) trade, non-proliferation; (8) radiological accidents. (N.C.)

  20. Nuclear fuel

    International Nuclear Information System (INIS)

    D Hondt, P.

    1998-01-01

    The research and development programme on nuclear fuel at the Belgian Nuclear Research Centre SCK/CEN is described. The objective of this programme is to enhance the quantitative prediction of the operational limits of nuclear fuel and to assess the behaviour of fuel under incidental and accidental conditions. Progress is described in different domains including the modelling of fission gas release in LWR fuel, thermal conductivity, basic physical phenomena, post-irradiation examination for fuel performance assessment, and conceptual studies of incidental and accidental fuel experiments

  1. Nuclear energy

    International Nuclear Information System (INIS)

    Wethe, Per Ivar

    2009-01-01

    Today we know two forms of nuclear energy: fission and fusion. Fission is the decomposition of heavy nuclei, while fusion is the melting together of light nuclei. Both processes create a large surplus of energy. Technologically, we can currently only use fission to produce energy in today's nuclear power plants, but there is intense research worldwide in order to realize a controlled fusion process. In a practical context, today's nuclear energy is a sustained source of energy since the resource base is virtually unlimited. When fusion technology is realized, the resource supply will be a marginal problem. (AG)

  2. Nuclear electronics

    International Nuclear Information System (INIS)

    Lucero B, E.

    1989-01-01

    The rapid technical development of Colombia over the past years, resulted among others, a considerable increase in the number of measuring instrumentation and testing laboratories, scientific research and metrology centers, in industry, agriculture, public health, education on the nuclear field, etc. IAN is a well organized institution with qualified management, trained staff and reasonably equipped laboratories to carry out tasks as: Metrology, standardization, quality control and maintenance and repair of nuclear instruments. The government of Colombia has adopted a policy to establish and operate through the country maintenance and repair facilities for nuclear instrumentation. This policy is reflected in the organization of electronic laboratories in Bogota-IAN

  3. Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant; Estabelecimento de criterios para a classificacao de medidas de remediacao de areas contaminadas apos um eventual acidente nuclear na usina de Angra dos Reis (RJ)

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2016-07-01

    When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

  4. Experimental study of para- and ortho-H3+ recombination

    Science.gov (United States)

    Plašil, R.; Varju, J.; Hejduk, M.; Dohnal, P.; Kotrík, T.; Glosík, J.

    2011-07-01

    Recombination of H3+ with electrons is a key process for many plasmatic environments. Recent experiments on storage ring devices used ion sources producing H3+ with enhanced populations of H3+ ions in the para nuclear spin configuration to shed light on the theoretically predicted faster recombination of para states. Although increased recombination rates were observed, no in situ characterization of recombining ions was performed. We present a state selective recombination study of para- and ortho-H3+ ions with electrons at 77 K in afterglow plasma in a He/Ar/H2 gas-mixture. Both spin configurations of H3+ have been observed in situ with a near infrared cavity ring down spectrometer (NIR-CRDS) using the two lowest energy levels of H3+. Using hydrogen with an enhanced population of H2 molecules in para states allowed us to influence the [para-H3+]/[ortho-H3+] ratio in the discharge and in the afterglow. We observed an increase in the measured effective recombination rate coefficients with the increase of the fraction of para-H3+. Measurements with different fractions of para-H3+ at otherwise identical conditions allowed us to determine the binary recombination rate coefficients for pure para-H3+ pαbin(77 K) = (2.0±0.4)×10-7 cm3s-1 and pure ortho-H3+ oαbin(77 K) = (4±3)×10-8 cm3s-1.

  5. Nuclear wastes

    International Nuclear Information System (INIS)

    2002-01-01

    This scientific document presents an introduction to the nuclear wastes problems, the separation process and the transmutation, the political and technical aspects of the storage, the radioprotection standards and the biological effects. (A.L.B.)

  6. Nuclear Disarmament.

    Science.gov (United States)

    Johnson, Christopher

    1982-01-01

    Material about nuclear disarmament and the arms race should be included in secondary school curricula. Teachers can present this technical, controversial, and frightening material in a balanced and comprehensible way. Resources for instructional materials are listed. (PP)

  7. Nuclear analysis

    International Nuclear Information System (INIS)

    1988-01-01

    Basic studies in nuclear analytical techniques include the examination of underlying assumptions and the development and extention of techniques involving the use of ion beams for elemental and mass analysis. 1 ref., 1 tab

  8. Nuclear reaction

    CERN Multimedia

    Penwarden, C

    2001-01-01

    At the European Research Organization for Nuclear Research, Nobel laureates delve into the mysteries of particle physics. But when they invited artists from across the continent to visit their site in Geneva, they wanted a new kind of experiment.

  9. [Nuclear theory

    International Nuclear Information System (INIS)

    1989-06-01

    This report discusses concepts in nuclear theory such as: neutrino nucleosynthesis; double beta decay; neutrino oscillations; chiral symmetry breaking; T invariance; quark propagator; cold fusion; and other related topics

  10. Nuclear constants

    International Nuclear Information System (INIS)

    Foos, J.

    1999-01-01

    This paper is written in two tables. The first one describes the different particles (bosons and fermions). The second one gives the isotopes nuclear constants of the different elements, for Z = 1 to 56. (A.L.B.)

  11. Nuclear constants

    International Nuclear Information System (INIS)

    Foos, J.

    2000-01-01

    This paper is written in two tables. The first one describes the different particles (bosons and fermions). The second one gives the isotopes nuclear constants of the different elements, for Z = 56 to 68. (A.L.B.)

  12. Nuclear constants

    International Nuclear Information System (INIS)

    Foos, J.

    1998-01-01

    This paper is made of two tables. The first table describes the different particles (bosons and fermions) while the second one gives the nuclear constants of isotopes from the different elements with Z = 1 to 25. (J.S.)

  13. Nuclear constants

    International Nuclear Information System (INIS)

    Foos, J.

    1999-01-01

    This paper is written in two tables. The first one describes the different particles (bosons and fermions). The second one gives the isotopes nuclear constants of the different elements, for Z = 56 to 68. (A.L.B.)

  14. Nuclear transmutations

    International Nuclear Information System (INIS)

    Mikulaj, V.

    1992-01-01

    Two types of nuclear transmutations are outlined, namely the radioactive transmutations and nuclear reactions. The basic characteristics are given of radioactive transmutations (gamma transmutations and isomeric transitions, beta, alpha transmutations, spontaneous fission and spontaneous emission of nucleons), their kinetics and the influence of the physical and chemical state of the radionuclide on the transmutation rate. The basic characteristics are described of nuclear reactions (reactions of neutrons including fission, reactions induced by charged particles and photons), their kinetics, effective cross sections and their mechanism. Chemical reactions caused by nuclear transmutations are discussed (recoil energy, properties of hot atoms, Szilard-Chalmers effect). A brief information is given on the behavior of radionuclides in trace concentrations. (Z.S.) 2 tabs., 19 figs., 12 refs

  15. Nuclear waste

    International Nuclear Information System (INIS)

    1992-05-01

    The Nuclear Waste Policy Act of 1982, as amended in 1987, directed the Secretary of Energy to, among other things, investigate Yucca Mountain, Nevada, as a potential site for permanently disposing of highly radioactive wastes in an underground repository. In April 1991, the authors testified on Yucca Mountain project expenditures before your Subcommittee. Because of the significance of the authors findings regrading DOE's program management and expenditures, you asked the authors to continue reviewing program expenditures in depth. As agreed with your office, the authors reviewed the expenditures of project funds made available to the Department of Energy's (DOE) Lawrence Livermore National Laboratory, which is the lead project contractor for developing a nuclear waste package that wold be used for disposing of nuclear waste at Yucca Mountain. This report discusses the laboratory's use of nuclear waste funds to support independent research projects and to manage Yucca Mountain project activities. It also discusses the laboratory's project contracting practices

  16. Nuclear shields

    International Nuclear Information System (INIS)

    Linares, R.C.; Nienart, L.F.; Toelcke, G.A.

    1976-01-01

    A process is described for preparing melt-processable nuclear shielding compositions from chloro-fluoro substituted ethylene polymers, particularly PCTFE and E-CTFE, containing 1 to 75 percent by weight of a gadolinium compound. 13 claims, no drawings

  17. Nuclear option

    International Nuclear Information System (INIS)

    Olson, P.S.

    1983-01-01

    The energy demand complexion of this country is always changing and promises to change in the future. The nuclear industry is responding to changing energy demands through standards writing activities. Since the oil embargo of 1973, there has been a change in the mix of fuels contributing to energy growth in this country; virtually all of the energy growth has come from coal and nuclear power. The predicted expansion of coal use by 1985, over 1977 level, is 37%, while the use of oil is expected to decline by 17%. Use of nuclear power is expected to increase 62% from the 1977 level. The feasibility of using nuclear energy to meet the needs of the USA for electric power is discussed

  18. Nuclear safety

    International Nuclear Information System (INIS)

    Tarride, Bruno

    2015-10-01

    The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

  19. Nuclear fission

    International Nuclear Information System (INIS)

    Kodama, T.

    1981-01-01

    The nuclear fission process is pedagogically reviewed from a macroscopic-microscopic point of view. The Droplet model is considered. The fission dynamics is discussed utilizing path integrals and semiclassical methods. (L.C.) [pt

  20. Nuclear physics

    International Nuclear Information System (INIS)

    Connell, K.A.; Warner, D.D.

    1990-01-01

    The first volume of the Annual Report for 1989/90 gives an overview of the Nuclear Structure Facility at Daresbury, its development and a selection of highlights of the year's programme. This volume is complementary, presenting brief specialist reports, submitted by the users, describing the progress and results of each individual proposal. The contents reflect the extremely successful year due in good measure to the performance of the tandem accelerator which provided a record number of hours with ''beam on target''. Reports are grouped in four sections: research into nuclear structure with contributions ordered in increasing Z numbers of the nuclei studied; investigations of nuclear reaction mechanisms; nuclear theory; accelerator operations and development plus experimental instrumentation and techniques. The appendix forms a concise summary of the work at the facility for the year. (author)

  1. Nuclear waste

    International Nuclear Information System (INIS)

    Pligt, J. van der

    1989-01-01

    This chapter present a brief overview of the current situation of siting radioactive wastes. This is followed by an overview of various psychological approaches attempting to analyse public reactions to nuclear facilities. It will be argued that public reactions to nuclear waste factilities must be seen in the context of more general attitudes toward nuclear energy. The latter are not only based upon perceptions of the health and environmental risks but are built on values, and sets of attributes which need not be similar to the representations o the experts and policy-makers. The issue of siting nuclear waste facilities is also embedded in a wider moral and political domain. This is illustrated by the importance of equity issues in siting radioactive wastes. In the last section, the implications of the present line of argument for risk communication and public participation in decisions about siting radioactive wastes will be briefly discussed. (author). 49 refs

  2. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Physician Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses ... limitations of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of ...

  3. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  4. General Nuclear Medicine

    Science.gov (United States)

    ... Resources Professions Site Index A-Z General Nuclear Medicine Nuclear medicine imaging uses small amounts of radioactive ... of General Nuclear Medicine? What is General Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  5. Children's (Pediatric) Nuclear Medicine

    Science.gov (United States)

    ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  6. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... News Physician Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging ... the limitations of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch ...

  7. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small ... of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical ...

  8. Nuclear instrumentation

    International Nuclear Information System (INIS)

    Weill, Jacky; Fabre, Rene.

    1981-01-01

    This article sums up the Research and Development effort at present being carried out in the five following fields of applications: Health physics and Radioprospection, Control of nuclear reactors, Plant control (preparation and reprocessing of the fuel, testing of nuclear substances, etc.), Research laboratory instrumentation, Detectors. It also sets the place of French industrial activities by means of an estimate of the French market, production and flow of trading with other countries [fr

  9. Nuclear hadrodynamics

    International Nuclear Information System (INIS)

    Geesaman, D.F.

    1984-01-01

    The role of hadron dynamics in the nucleus is illustrated to show the importance of nuclear medium effects in hadron interactions. The low lying hadron spectrum is considered to provide the natural collective variables for nuclear systems. Recent studies of nucleon-nucleon and delta-nucleon interactions are reviewed, with emphasis on the type of experimental phenomena which signal the importance of the many-body dynamics. 28 references

  10. Seguro Nuclear

    International Nuclear Information System (INIS)

    Oliveira, S.C.C. de.

    1978-04-01

    A description of the constitutive elements of insurance and its features in the field of law, and special legislation about the matter are given. The relationship between the liability of the nuclear power plant operator and the international conventions about civil liability on nuclear damage is discussed. Some considerations on damage reparing in the United States, Germany, France and Spain are presented. (A.L.S.L.) [pt

  11. Nuclear medicine

    International Nuclear Information System (INIS)

    Sibille, L.; Nalda, E.; Collombier, L.; Kotzki, P.O.; Boudousq, V.

    2011-01-01

    Nuclear medicine is a medical specialty using the properties of radioactivity. Radioactive markers associated with vectors are used as a tracer or radiopharmaceutical for diagnostic purposes and/or therapy. Since its birth more than half a century ago, it has become essential in the care of many patients, particularly in oncology. After some definitions, this paper presents the main nuclear techniques - imaging for diagnostic, radiopharmaceuticals as therapeutic agents, intra-operative detection, technique of radioimmunoassay - and the future of this field. (authors)

  12. Nuclear waste

    International Nuclear Information System (INIS)

    1988-01-01

    The Department of Energy has proposed a draft plan for investigating the Yucca Mountain, Nevada, site to determine if it suitable for a waste repository. This fact sheet provides information on the status of DOE's and the Nuclear Regulatory Commission's efforts to streamline what NRC expects will be the largest and most complex nuclear-licensing proceeding in history, including the development of an electronic information management system called the Licensing Support System

  13. Nuclear safety

    International Nuclear Information System (INIS)

    Arnott, D.

    1981-01-01

    Dr Arnott, scientific consultant to PANDORA, emphasises our lack of knowledge of the behaviour of highly active radioactive wastes, particularly effluents, and their characteristics. He proposes that they should be stored, preferably in a solidified state, until our knowledge allows their safe disposal. Political aspects and government policies are discussed and human fallibility is stressed. The nuclear establishment and nuclear power programme are severely criticised. (U.K.)

  14. Nuclear astrophysics

    International Nuclear Information System (INIS)

    Lehoucq, Roland; Klotz, Gregory

    2015-11-01

    Astronomy deals with the position and observation of the objects in our Universe, from planets to galaxies. It is the oldest of the sciences. Astrophysics is the study of the physical properties of these objects. It dates from the start of the 20. century. Nuclear astrophysics is the marriage of nuclear physics, a laboratory science concerned with the infinitely small, and astrophysics, the science of what is far away and infinitely large. Its aim is to explain the origin, evolution and abundance of the elements in the Universe. It was born in 1938 with the work of Hans Bethe, an American physicist who won the Nobel Prize for physics in 1967, on the nuclear reactions that can occur at the center of stars. It explains where the incredible energy of the stars and the Sun comes from and enables us to understand how they are born, live and die. The matter all around us and from which we are made, is made up of ninety-two chemical elements that can be found in every corner of the Universe. Nuclear astrophysics explains the origin of these chemical elements by nucleosynthesis, which is the synthesis of atomic nuclei in different astrophysical environments such as stars. Nuclear astrophysics provides answers to fundamental questions: - Our Sun and the stars in general shine because nuclear reactions are taking place within them. - The stars follow a sequence of nuclear reaction cycles. Nucleosynthesis in the stars enables us to explain the origin and abundance of elements essential to life, such as carbon, oxygen, nitrogen and iron. - Star explosions, in the form of supernovae, disperse the nuclei formed by nucleosynthesis into space and explain the formation of the heaviest chemical elements such as gold, platinum and lead. Nuclear astrophysics is still a growing area of science. (authors)

  15. Nuclear physics

    International Nuclear Information System (INIS)

    Spicer, B.M.

    1981-01-01

    Major centres of experimental nuclear physics are at Melbourne University, A.N.U., the A.A.E.C., James Cook University and the University of Western Australia. Groups working in theoretical nuclear physics exist at Melbourne, A.N.U., the A.A.E.C., Flinders and Adelaide Universities and the University of Western Australia. The activities of these groups are summarised

  16. Nuclear energy

    International Nuclear Information System (INIS)

    1996-01-01

    Several issues concerning nuclear energy in France during 1996 are presented: permission of a demand for installing underground laboratories in three sites (Marcoule, Bure and Chapelle-Baton); a report assessing the capacity of Superphenix plant to operate as a research tool; the project of merging between Framatome and Gec-Alsthom companies; the revision of a general report on nuclear energy in France; the issue of military plutonium management

  17. Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    White, Morgan C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-23

    PowerPoint presentation targeted for educational use. Nuclear data comes from a variety of sources and in many flavors. Understanding where the data you use comes from and what flavor it is can be essential to understand and interpret your results. This talk will discuss the nuclear data pipeline with particular emphasis on providing links to additional resources that can be used to explore the issues you will encounter.

  18. Nuclear medicine

    International Nuclear Information System (INIS)

    Blanquet, Paul; Blanc, Daniel.

    1976-01-01

    The applications of radioisotopes in medical diagnostics are briefly reviewed. Each organ system is considered and the Nuclear medicine procedures pertinent to that system are discussed. This includes, the principle of the test, the detector and the radiopharmaceutical used, the procedure followed and the clinical results obtained. The various types of radiation detectors presently employed in Nuclear Medicine are surveyed, including scanners, gamma cameras, positron cameras and procedures for obtaining tomographic presentation of radionuclide distributions [fr

  19. Nuclear medicine

    International Nuclear Information System (INIS)

    Chamberlain, M.J.

    1986-01-01

    Despite an aggressive, competitive diagnostic radiology department, the University Hospital, London, Ontario has seen a decline of 11% total (in vivo and in the laboratory) in the nuclear medicine workload between 1982 and 1985. The decline of in vivo work alone was 24%. This trend has already been noted in the U.S.. Nuclear medicine is no longer 'a large volume prosperous specialty of wide diagnostic application'

  20. Nuclear cardiac

    International Nuclear Information System (INIS)

    Slutsky, R.; Ashburn, W.L.

    1982-01-01

    The relationship between nuclear medicine and cardiology has continued to produce a surfeit of interesting, illuminating, and important reports involving the analysis of cardiac function, perfusion, and metabolism. To simplify the presentation, this review is broken down into three major subheadings: analysis of myocardial perfusion; imaging of the recent myocardial infarction; and the evaluation of myocardial function. There appears to be an increasingly important relationship between cardiology, particularly cardiac physiology, and nuclear imaging techniques

  1. Nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, S M [Bhabha Atomic Research Centre, Bombay (India). Radiation Medicine Centre

    1967-01-01

    The article deals with the growth of nuclear medicine in India. Radiopharmaceuticals both in elemental form and radiolabelled compounds became commercially available in India in 1961. Objectives and educational efforts of the Radiation Medicine Centre setup in Bombay are mentioned. In vivo tests of nuclear medicine such as imaging procedures, dynamic studies, dilution studies, thyroid function studies, renal function studies, linear function studies, blood flow, and absorption studies are reported. Techniques of radioimmunoassay are also mentioned.

  2. Nuclear technology

    International Nuclear Information System (INIS)

    1983-03-01

    This report examines nuclear technology in Canada, with emphasis on Quebec, as a means of revitilizing industry. The historical, present day, and future states of Atomic Energy of Canada Limited are examined. Future research programs are discussed in greatest detail. These range from disposal of porcine wastes to new applications for electricity to nuclear medical techniques (to cite only a few examples). The executive summary is written in English. (23 fig., 16 tab.)

  3. Nuclear risk

    International Nuclear Information System (INIS)

    Mulkers, G.

    1988-01-01

    This file includes data on risks insured by the nuclear insurance pool in Belgium and on the Chernobyl accident covering injury, economic damage and compensation for the latter. Also included are the texts of the IAEA Conventions on Early Notification and on Assistance in Case of a Nuclear Accident as well as that of a Convention on long-distance transfrontier atmospheric pollution signed in Geneva [fr

  4. Nuclear accidents

    International Nuclear Information System (INIS)

    1987-01-01

    On 27 May 1986 the Norwegian government appointed an inter-ministerial committee of senior officials to prepare a report on experiences in connection with the Chernobyl accident. The present second part of the committee's report describes proposals for measures to prevent and deal with similar accidents in the future. The committee's evaluations and proposals are grouped into four main sections: Safety and risk at nuclear power plants; the Norwegian contingency organization for dealing with nuclear accidents; compensation issues; and international cooperation

  5. Nuclear education

    International Nuclear Information System (INIS)

    Kemeny, L.G.

    1987-01-01

    All scientists and technologists are agreed that the coal based fuel cycle is somewhere between 50 to 300 times more dangerous than the uranium fuel cycle. Under these circumstances it is not difficult to show that on a more quantitative basis, the nuclear industry, in all countries, has an unblemished safety record when compared with other energy sources. Various hazards and benefits of nuclear power are analyzed in this paper comparing with other energy sources. (Liu)

  6. Nuclear astrophysics

    International Nuclear Information System (INIS)

    Arnould, M.; Takahashi, K.

    1999-01-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding of the Universe, or at least some of its many faces, through the knowledge of the microcosm of the atomic nucleus. It attempts to find as many nuclear physics imprints as possible in the macrocosm, and to decipher what those messages are telling us about the varied constituent objects in the Universe at present and in the past. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress made in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other subfields of physics and chemistry have also contributed to that advance. Notwithstanding the accomplishment, many long-standing problems remain to be solved, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endangering old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experimental and theoretical components. On top of the fact that large varieties of nuclei have to be dealt with, these nuclei are immersed in highly unusual environments which may have a significant impact on their static properties, the diversity of their transmutation modes, and on the probabilities of these modes. In order to have a chance of solving some of the problems nuclear astrophysics is facing, the astrophysicists and nuclear physicists are obviously bound to put their competence in common, and have sometimes to benefit from the help of other fields of physics, like particle physics, plasma physics or solid-state physics. Given the highly varied and complex aspects, we pick here some specific nuclear

  7. Technical study for the automation and control of processes of the chemical processing plant for liquid radioactive waste at Racso Nuclear Center; Estudio tecnico para la automatizacion y control de procesos de la planta de tratamiento quimico de los residuos liquidos radiactivos del Centro Nuclear Racso

    Energy Technology Data Exchange (ETDEWEB)

    Quevedo D, M; Ayala S, A

    1997-07-01

    The purpose of this study is to introduce the development of an automation and control system in a chemical processing plant for liquid radioactive waste of low and medium activity. The control system established for the chemical processing plant at RACSO Nuclear Center is described. It is an on-off sequential type system with feedback. This type of control has been chosen according to the volumes to be treated at the plant as processing is carried out by batches. The system will be governed by a programmable controller (PLC), modular, with a minimum of 24 digital inputs, 01 analog input, 16 digital outputs and 01 analog input. Digital inputs and outputs are specifically found at the level sensors of the tanks and at the solenoid-type electro valve control. Analog inputs and outputs have been considered at the pH control. The comprehensive system has been divided into three control bonds, The bonds considered for the operation of the plant are described, the plant has storing, fitting, processing and clarifying tanks. National Instruments' Lookout software has been used for simulation, constituting an important tool not only for a design phase but also for a practical one since this software will be used as SCADA system. Finally, the advantages and benefits of this automation system are analyzed, radiation doses received by occupationally exposed workers are reduced and reliability on the operation on the system is increased. (authors)

  8. Methodology based in the fuzzy logic for constructing the objective functions in optimization problems of nuclear fuel: application to the cells radial design; Metodologia basada en logica difusa para construir las funciones objetivo en problemas de optimizacion de combustible nuclear: aplicacion al diseno radial de celdas

    Energy Technology Data Exchange (ETDEWEB)

    Barragan M, A.M.; Martin del Campo M, C.; Palomera P, M.A. [FI-UNAM, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D.F. (Mexico)]. E-mail: ale_bar_m@yahoo.com.mx

    2005-07-01

    A methodology based on Fuzzy Logic for the construction of the objective function of the optimization problems of nuclear fuel is described. It was created an inference system that responds, in certain form, as a human expert when it has the task of qualifying different radial designs of fuel cells. Specifically it is detailed how an inference system based based on Fuzzy Logic that has five enter variables and one exit variable was built, which corresponds to the objective function for the radial design of a fuel cell for a BWR. The use of Fuzzy with Mat lab offered the visualization capacity of the exit variable in function of one or two enter variables at the same time. This allowed to build, in appropriate way, the combination of the inference rules and the membership functions of those diffuse sets used for each one of the enter variables. The obtained objective function was used in an optimization process based on Taboo search. The new methodology was proven for the design of a cell used in a fuel assemble of the Laguna Verde reactor obtaining excellent results. (Author)

  9. Operational tests and irradiation programming proposal for the industrial production of {sup 131} I in the TRIGA Mark III reactor of the Nuclear Centre (ININ); Pruebas operacionales y propuesta de programacion de irradiacion para la produccion industrial de {sup 131} I en el reactor TRIGA Mark III del Centro Nuclear (ININ)

    Energy Technology Data Exchange (ETDEWEB)

    Alanis M, J.; Reyes J, J.L.; Ruiz C, M.A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    In the National Institute of Nuclear Research it was recently finished the project for the production of I-131 at industrial level, the one which can divide basically in: (a) Preparation of the raw materials (TeO{sub 2}), (b) Sintering, (c) Neutron irradiation and (d) Separation of the I-131. With the end of starting the industrial production of this process, in this work it is presented the operational tests and an irradiation proposal of the TeO{sub 2} to obtain quantities of I-131 that cover, if not totally, partially the national market. For this, they were carried out irradiation tests of 6 samples to different flows of neutrons. The result of these tests settles down that irradiating a mass of 240 g TeO{sub 2} to a neutron flow of 6.53 x 10{sup 12} n/cm{sup 2}s in 4 cycles of 30 h per week approximately 2.54 Ci/week of I-131 distilled are obtained, which represents 35% of the demand of the Plant of Radioisotopes production of the ININ. (Author)

  10. Nuclear safety

    International Nuclear Information System (INIS)

    2014-01-01

    The Program on Nuclear Safety comprehends Radioprotection, Radioactive Waste Management and Nuclear Material Control. These activities are developed at the Nuclear Safety Directory. The Radioactive Waste Management Department (GRR) was formally created in 1983, to promote research and development, teaching and service activities in the field of radioactive waste. Its mission is to develop and employ technologies to manage safely the radioactive wastes generated at IPEN and at its customer’s facilities all over the country, in order to protect the health and the environment of today's and future generations. The Radioprotection Service (GRP) aims primarily to establish requirements for the protection of people, as workers, contractors, students, members of the general public and the environment from harmful effects of ionizing radiation. Furthermore, it also aims to establish the primary criteria for the safety of radiation sources at IPEN and planning and preparing for response to nuclear and radiological emergencies. The procedures about the management and the control of exposures to ionizing radiation are in compliance with national standards and international recommendations. Research related to the main activities is also performed. The Nuclear Material Control has been performed by the Safeguard Service team, which manages the accountability and the control of nuclear material at IPEN facilities and provides information related to these activities to ABACC and IAEA. (author)

  11. Nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Nakano, H [Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

    1976-10-01

    It is expected that nuclear power generation will reach 49 million kW in 1985 and 129 million kW in 1995, and the nuclear fuel having to be supplied and processed will increase in proportion to these values. The technical problems concerning nuclear fuel are presented on the basis of the balance between the benefit for human beings and the burden on the human beings. Recently, especially the downstream of nuclear fuel attracts public attention. Enriched uranium as the raw material for light water reactor fuel is almost monopolized by the U.S., and the technical information has not been published for fear of the diversion to nuclear weapons. In this paper, the present situations of uranium enrichment, fuel fabrication, transportation, reprocessing and waste disposal and the future problems are described according to the path of nuclear fuel cycle. The demand and supply of enriched uranium in Japan will be balanced up to about 1988, but afterwards, the supply must rely upon the early establishment of the domestic technology by centrifugal separation method. No problem remains in the fabrication of light water reactor fuel, but for the fabrication of mixed oxide fuel, the mechanization of the production facility and labor saving are necessary. The solution of the capital risk for the construction of the second reprocessing plant is the main problem. Japan must develop waste disposal techniques with all-out efforts.

  12. Nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Program on Nuclear Safety comprehends Radioprotection, Radioactive Waste Management and Nuclear Material Control. These activities are developed at the Nuclear Safety Directory. The Radioactive Waste Management Department (GRR) was formally created in 1983, to promote research and development, teaching and service activities in the field of radioactive waste. Its mission is to develop and employ technologies to manage safely the radioactive wastes generated at IPEN and at its customer’s facilities all over the country, in order to protect the health and the environment of today's and future generations. The Radioprotection Service (GRP) aims primarily to establish requirements for the protection of people, as workers, contractors, students, members of the general public and the environment from harmful effects of ionizing radiation. Furthermore, it also aims to establish the primary criteria for the safety of radiation sources at IPEN and planning and preparing for response to nuclear and radiological emergencies. The procedures about the management and the control of exposures to ionizing radiation are in compliance with national standards and international recommendations. Research related to the main activities is also performed. The Nuclear Material Control has been performed by the Safeguard Service team, which manages the accountability and the control of nuclear material at IPEN facilities and provides information related to these activities to ABACC and IAEA. (author)

  13. Nuclear energy

    International Nuclear Information System (INIS)

    Seidel, J.

    1990-01-01

    This set of questions is based on an inquiry from the years 1987 to 1989. About 250 people af all age groups - primarily, however, young people between 16 and 25 years of age - were asked to state the questions they considered particularly important on the subject of nuclear energy. The survey was carried out without handicaps according to the brain-storming principle. Although the results cannot claim to be representative, they certainly reflect the areas of interest of many citizens and also their expectations, hopes and fears in connection with nuclear energy. The greater part of the questions were aimed at three topic areas: The security of nuclear power-stations, the effects of radioactivity on people and the problem of waste disposal. The book centres around these sets of questions. The introduction gives a general survey of the significance of nuclear energy as a whole. After this follow questions to do with the function of nuclear power stations, for the problems of security and waste disposal - which are dealt with in the following chapters - are easier to explain and to understand if a few physical and technical basics are understood. In the final section of the book there are questions on the so-called rejection debate and on the possibility of replacing nuclear energy with other energy forms. (orig./HP) [de

  14. Nuclear technologies

    International Nuclear Information System (INIS)

    Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

    2010-01-01

    In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

  15. Nuclear watershed

    International Nuclear Information System (INIS)

    Makovich, L.; Parish, T.

    1984-01-01

    In 1979 the accident at Three Mile Island brought nuclear power to the forefront of national attention. Over the last five years there have been no new orders for nuclear plants, construction costs and lead times have increased drastically, and numerous plants have been cancelled. In the coming years many new plants will come on line, and the first round of nuclear plant retirements will begin. Thus, the new set of issues faced by utilities are whether to complete plants currently under construction, how to recover the cost of abandoned plants, how to handle the potential rate shock of bringing costly plants into rate base, and how to accomplish decommissioning and retirement of nuclear plants. This paper presents and analyzes these issues. First, the history of the nuclear electric generation industry is reviewed. Next a case study illustrating the cost momentum built into nuclear power plant construction is presented. The issues involved in plant cancellation are discussed. Finally, a case study involving rate phase-in strategies is analyzed. 1 reference, 7 figures

  16. Aplicações da tomografia de ressonância magnética nuclear como método não-destrutivo para avaliar os efeitos de injúrias mecânicas em goiabas 'Paluma' e 'Pedro Sato' Applications of the nuclear magnetic resonance tomography as a non-destructive method to evaluate the effects of mechanical injuries in 'Paluma' and 'Pedro Sato' guavas

    Directory of Open Access Journals (Sweden)

    Ben-Hur Mattiuz

    2002-12-01

    Full Text Available Objetivou-se determinar o potencial do uso da tomografia de ressonância magnética, como método não-destrutivo, para avaliar os efeitos das injúrias mecânicas em goiabas. Foram utilizados frutos no estádio de maturação "de vez" das cultivares Paluma e Pedro Sato. Na injúria por impacto, os frutos foram deixados cair, em queda livre, de uma altura de 1,20 m, sofrendo dois impactos, em lados opostos de sua porção equatorial. Na injúria por compressão, os frutos foram submetidos a um peso de 29,4 N, por 15 minutos. Para a injúria por corte, foram efetuados dois cortes, no sentido longitudinal dos frutos, de exatamente 30 mm de comprimento por 2 mm de profundidade. Os frutos injuriados foram armazenados sob condições de ambiente (22 ± 2 °C e 40 %UR. Foram realizadas análises com tomógrafo de ressonância magnética Varian Inova de 2 Tesla. As imagens foram obtidas a partir da detecção dos prótons de hidrogênio (¹H. Para cada fruto, foram obtidos tomogramas simétricos a partir do centro do fruto. A tomografia de ressonância magnética nuclear mostrou-se uma ferramenta eficaz na detecção de injúrias internas de frutos. O estresse físico causado pelo impacto produziu um colapso interno nos lóculos desses frutos (internal bruising, levando à perda da integridade celular e a conseqüente liquefação dos tecidos placentários. A cultivar Pedro Sato mostrou uma suscetibilidade maior à injúria por impacto que a 'Paluma'. A injúria por compressão tornou-se mais evidente no pericarpo externo do fruto, de ambas as cultivares. A injúria por corte levou a lignificação dos tecidos no local injuriado e deformações superficiais devido à perda acentuada de matéria fresca no local da lesão, evidentes no sexto dia de avaliação.The present study reports on the potential of the use of the tomography of magnetic resonance, as a non-destructive method, to evaluate the effects of the mechanical injuries in guava fruits

  17. Bases para proyectiles dirigidos

    Directory of Open Access Journals (Sweden)

    Editorial, Equipo

    1959-03-01

    Full Text Available Aunque actualmente no se ha llegado a una línea general de métodos o sistemas que gobiernen un tipo característico de rampa y servicios auxiliares necesarios para el lanzamiento al espacio de proyectiles dirigidos a grandes alturas y distancias, las experiencias obtenidas en diferentes ensayos, utilizando distintos tipos de proyectiles y trayectorias balísticas, han sentado toda una serie de procedimientos, datos y conclusiones de gran valor balístico que, aun teniendo en cuenta la continua evolución del proyectil, sus formas, combustibles y alcances, se conocen ya, con bastante aproximación, las condiciones mínimas que ha de reunir una base dedicada a este tipo de lanzamientos.

  18. Registrar para avanzar

    Directory of Open Access Journals (Sweden)

    Laia Matarranz Torres

    2017-06-01

    Full Text Available El farmacéutico comunitario es un profesional sanitario con un enorme potencial para mejorar no solo el uso de los medicamentos (detectando, por ejemplo, resultados negativos de la medicación, sino también la prevención de enfermedades y la promoción de la salud pública. Sin duda, el desarrollo y el impulso que están teniendo los servicios profesionales farmacéuticos (SPF desde hace años pueden contribuir decisivamente a que este potencial se consolide de una forma definitiva, obteniendo el reconocimiento del conjunto del sistema sanitario, incluyendo tanto a otros profesionales de la salud (médicos, enfermería, medicina especializada… como a la Administración y, por supuesto, a los propios pacientes beneficiarios de estos servicios. Es cierto que la figura del farmacéutico y su ejercicio sanitario han estado tradicionalmente bien considerados por la población, pero no es menos verdad que la integración de la actividad asistencial de la farmacia comunitaria en el Sistema Nacional de Salud (SNS es, cuanto menos mejorable, y que, incluso, algunas manifestaciones ponen en entredicho de vez en cuando la labor científico-asistencial de las farmacias o generan dudas sobre su capacidad para formar parte de pleno derecho de los equipos de salud que deben trabajar de forma coordinado en la mejora de la atención sanitaria de los pacientes.

  19. Semantic integration of scientific publications and research data: proposal of model of expanded publication for the area of nuclear sciences; Integracao semantica de publicacoes cientificas e dados de pesquisa: proposta de modelo de publicacao ampliada para a area de ciencias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sales, Luana Farias

    2014-07-01

    applied to the specificity of Nuclear Sciences. This was accomplished in two ways: through a literature review, for purposes of analysis and qualitative interpretation of the general concepts; and through the domain analysis approach that allowed empirically analyze the particular application area. As a final result was obtained a proposal of guidelines for a national policy for digital curation, and a model of scientific publication to the Nuclear Sciences area, in which the research data are linked to the academic publications by means of semantic relations systematized into taxonomy built for this purpose. Graphic models are used as a tool to represent and synthesize the resulting concepts. As a conclusion it is observed: changes in the scholarly communication cycle, the possibility of building a new scientific model as relevant standard to the practice of a more open and more collaborative science, and feasibility of incorporating the principles and theories of librarianship and Information Science for the organization of technical and scientific knowledge in the world of eScience. (author)

  20. Prospection of implementation of distance learning for the course on fundamentals of Nuclear Physics at the graduate course of IPEN using free software infrastructure; Prospeccao de implementacao de ensino a distancia para a disciplina de fundamentos de fisica nuclear na pos-graduacao do IPEN utilizanto infraestrutura de software livre

    Energy Technology Data Exchange (ETDEWEB)

    Tondim, Jose Egidio Marin

    2009-07-01

    In modern society, the utilization of technological resources and of the internet are of fundamental importance in ali areas and as such the educational activities have to follow this evolution. In this context, distance learning is a fundamental tool for educational development, being innovative and stimulating , offering a variety of resources that are complementary to the activities of the students. Also it is important to point out that distance learning can be brought to remote regions, of difficult access in many cases, so allowing a wide dissemination of knowledge and also implying in lower costs. The objective of this work is the prospection of the interest and viability of implantation of distance learning in the course on Fundamentals of Nuclear Physics at the pos-graduate course of IPEN, using free software infra-structure , by means of a pilot project on distance learning. The work was developed in three phases. In the first phase, a questionnaire was applied to the students , with the aim of finding out about their profiles and interest in distance learning, before they had contact with the pilot project. In the second phase, other students were interviewed , also with the objective of knowing their opinion about distance learning ,but after they had access to the pilot project. Finally,the professors of the graduate course of IPEN were consulted, also by means of a questionnaire, in order to know about their interest in the utilization of distance learning. The results obtained in the present work show that distance learning is a welcome pedagogical resource for students as well for teachers; these results will subsidize the future implementation of distance learning in the pos-graduate course of IPEN. (author)

  1. The para-petroleum industry

    International Nuclear Information System (INIS)

    2002-07-01

    The para-petroleum industry includes societies that realize studies and installations for the deposits exploitation. This document presents the situation of the para-petroleum industry in 2001, the world investment growth of the activity, the french societies financial results and an inventory of the main operations in the amalgamation domain. (A.L.B.)

  2. Nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The Koeberg nuclear power station, planned to come on stream in 1984, is expected to save South Africa some six million t/annum of coal, and to contribute some 10 per cent of the country's electricity requirements. The use of nuclear energy will provide for growing national energy needs, and reduce high coal transport costs for power generation at the coast. In the long term, however, it gives rise to the controversial question of nuclear waste storage. The Atomic Energy Corporation of South Africa Ltd (AEC) recently announced the purchase of a site in Namaqualand (NW Cape) for the storage of low-level radioactive waste. The Nuclear Development Corporation of South Africa (Pty) Ltd, (NUCOR) will develop and operate the site. The South African Mining and Engineering Journal interviewed Dr P.D. Toens, manager of the Geology Department and Mr P.E. Moore, project engineer, on the subject of nuclear waste, the reasons behind Nucor's choice of site and the storage method

  3. Nuclear risk

    International Nuclear Information System (INIS)

    Levenson, M.

    1989-01-01

    The title of our session, Nuclear Risk Versus Other Power Options, is provocative. It is also a title with different meanings to different people. To the utility chief executive officer, nuclear power is a high-risk financial undertaking because of political and economic barriers to cost recovery. To the utility dispatcher, it is a high-risk future power source since plant completion and start-up dates can be delayed for very long times due to uncertain legal and political issues. To the environmentalist, concerned about global effects such as greenhouse and acid rain, nuclear power is a relatively low risk energy source. To the financial people, nuclear power is a cash cow turned sour because of uncertainties as to what new plants will cost and whether they will even be allowed to operate. The statistics on risk are known and the results of probability risk assessment calculations of risks are known. The challenge is not to make nuclear power safer, it is already one of the safest, if not the safest, source of power currently available. The challenge is to find a way to communicate this to the public

  4. Nuclear recession

    International Nuclear Information System (INIS)

    Speth, G.

    1978-01-01

    The private sector's growing doubts about nuclear power plants, as reflected in the decline in new orders and the number of rescinded orders, will result in an estimated total of under 300 nuclear power plants by the year 2000 rather than the 1200 to 1500 that were projected several years ago. The decline is a result of construction and equipment costs and a lower operating efficiency than anticipated. The growth of electricity demand also declined after 1974 and, although it is increasing again, there are concerns about future growth rates. Besides its noncompetitive position relative to coal, nuclear plant construction suffers from restrictive policies based on the uncertainties of safety, security, waste disposal, and proliferation. Unless these problems can be resolved, many consider nuclear power to be an impractical option as an energy source. The Council on Environmental Quality supports policies that will permit further nuclear or coal development only after a clear demonstration of technical and institutional capacity to handle these problems. A commitment to solar technology is urged

  5. Nuclear fusion

    International Nuclear Information System (INIS)

    Al-zaelic, M.M.

    2013-01-01

    Nuclear fusion can be relied on to solve the global energy crisis if the process of limiting the heat produced by the fusion reaction (Plasma) is successful. Currently scientists are progressively working on this aspect whereas there are two methods to limit the heat produced by fusion reaction, the two methods are auto-restriction using laser beam and magnetic restriction through the use of magnetic fields and research is carried out to improve these two methods. It is expected that at the end of this century the nuclear fusion energy will play a vital role in overcoming the global energy crisis and for these reasons, acquiring energy through the use of nuclear fusion reactors is one of the most urge nt demands of all mankind at this time. The conclusion given is that the source of fuel for energy production is readily available and inexpensive ( hydrogen atoms) and whole process is free of risks and hazards, especially to general health and the environment . Nuclear fusion importance lies in the fact that energy produced by the process is estimated to be about four to five times the energy produced by nuclear fission. (author)

  6. Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2; Medidores ultrasonicos en el flujo de agua de alimentacion para recuperar potencia termica en el reactor de la Central Nuclear Laguna Verde U1 and U2

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)]. e-mail: francisco.tijerina@cfe.gob.mx

    2008-07-01

    The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

  7. Efficiency of the low energy detection system for the measurement of {sup 235} U in lung of the Nuclear Regulatory Authority; Eficiencia del sistema de deteccion de baja energia para la medicion de {sup 235} U en pulmon de la Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Spinella, M.R.; Krimer, M.; Gregori, B.N.; Rojo, A.M. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250 (C1429BNP), Buenos Aires (Argentina)]. e-mail: mspinell@cae.arn.gov.ar

    2006-07-01

    This work presents the results of the calibration process of the detection system of {sup 235} U in lung of the Nuclear Regulatory Authority. The phantom used in the calibration is the denominated Lawrence Livermore Realistic Phantom, provided of lungs and active nodules and of 4 thoracic covers that its simulate muscular tissue with thickness that vary between 1.638 and 3.871 cm. The spectra are acquired by four detecting of denominated LEGe ACTII Canberra marks, each one with an active area of 3800 mm{sup 2}, a diameter of 70 mm and a thickness of 20 mm, the sign is processed by a SYSTEM100 multichannel and the spectra are analyzed with the GENIE2K program. The detectors are suspended by mobile structures that allow to vary the position with regard to a horizontal stretcher that defines the measurement geometry. The whole system is located in the interior of an armored enclosure of 200 x 150 x 200 cm{sup 3} of steel of 15 cm thickness, inside recovered with layers of 0.5 cm lead and 0.05 cm cadmium. The total weight of the enclosure is 40 ton. For the described system the efficiency curves versus muscular thoracic tissue thickness (ETM) corresponding to the energy of 143.76, 163.358 and 185.72 keV of the {sup 235} U radioisotope were obtained. Its were also practiced displacements of those detectors of approximately 1 cm with respect to the reference position and its were analyzed the corresponding changes of magnitude in the efficiencies. The obtained variations oscillate, for vertical displacements, between 5% and 7.8% for the smallest value in ETM (1.638 cm) and between 4.2% to 6.7% for the ETM 3.871 cm. While for the practiced lateral displacements, the variations go from 4% to 15%. The detection limits corresponding to each energy and thickness were determined. The results showed for the photopeak of 185.72 keV, the more outstanding in the evaluations that saying limit it oscillates between 3.7 and 6.4 Bq {sup 235} U inside the considered thickness range

  8. Nuclear scales

    International Nuclear Information System (INIS)

    Friar, J.L.

    1998-01-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the π-γ force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted

  9. Nuclear forces

    International Nuclear Information System (INIS)

    Holinde, K.

    1990-01-01

    In this paper the present status of the meson theory of nuclear forces is reviewed. After some introductory remarks about the relevance of the meson exchange concept in the era of QCD and the empirical features of the NN interaction, the exciting history of nuclear forces is briefly outlined. In the main part, the author gives the basic physical ideas and sketch the derivation of the one-boson-exchange model of the nuclear force, in the Feynman approach. Secondly we describe, in a qualitative way, various necessary extensions, leading to the Bonn model of the N interaction. Finally, points to some interesting pen questions connected with the extended quark structure of the hadrons, which are topics of current research activity

  10. Nuclear astrophysics

    International Nuclear Information System (INIS)

    Penionzhkevich, Yu. E.

    2010-01-01

    The International Year of Astronomy 2009 (IYA2009) was declared by the 62nd General Assembly of the United Nations and was also endorsed by UNESCO. Investigations in the realms of particle and nuclear physicsmake a large contribution in the development of our ideas of the properties of the Universe. The present article discusses some problems of the evolution of the Universe, nucleosyntheses, and cosmochronology from the point of view of nuclear and particle physics. Processes occurring in the Universe are compared with the mechanisms of the production and decay of nuclei, as well as with the mechanisms of their interaction at high energies. Examples that demonstrate the potential of nuclearphysics methods for studying cosmic objects and the properties of the Universe are given. The results that come from investigations into nuclear reactions induced by beams of radioactive nuclei and which make it possible to take a fresh look at the nucleosynthesis scenario in the range at light nuclei are presented.

  11. Nuclear scales

    Energy Technology Data Exchange (ETDEWEB)

    Friar, J.L.

    1998-12-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

  12. Nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    The NEA Nuclear Waste Bulletin has been prepared by the Radiation Protection and Waste Management Division of the OECD Nuclear Energy Agency to provide a means of communication amongst the various technical and policy groups within the waste management community. In particular, it is intended to provide timely and concise information on radioactive waste management activities, policies and programmes in Member countries and at the NEA. It is also intended that the Bulletin assists in the communication of recent developments in a variety of areas contributing to the development of acceptable technology for the management and disposal of nuclear waste (e.g., performance assessment, in-situ investigations, repository engineering, scientific data bases, regulatory developments, etc)

  13. Nuclear policy

    International Nuclear Information System (INIS)

    Ford, G.R.

    1976-01-01

    Then-President Gerald Ford outlines the potential benefits of nuclear power as opposed to the danger of proliferation. He points out that not all nations have the same interest or views toward nuclear energy; but also he says that if a choice must be made, nonproliferation objectives must take precedence over economic and energy benefits. It is pointed out that the management of nuclear energy can be only partial and temporary by technical measures, and that full management can result only if nations realistically face the task prepared to forego preconceived short-term advantages in favor of long-term gains. Coordination of the policies of all nations toward the common goal of nonproliferation is predicted to lead to success

  14. Para-bosons and Para-fermions in Quantum Mechanics

    International Nuclear Information System (INIS)

    Cattani, M.S.D.; Fernandes, N.C.

    1982-01-01

    Within the framework of the ordinary quantum mechanics, a detailed study of the energy eigenfunctions of N identical particles using the irreducible representations of the permutation group in the Hilbert space is performed. It is shown that the para-states, as occurs with the boson and fermion states, are compatible with the postulates of quantum mechanics and with the principle of indistinguishability. A mathematical support for the existence of para-bosons and para-fermions is given. Gentile's quantum statistics is, in a certain sense, justified. (Author) [pt

  15. Generating para-water from para-hydrogen: A Gedankenexperiment.

    Science.gov (United States)

    Ivanov, Konstantin L; Bodenhausen, Geoffrey

    2018-07-01

    A novel conceptual approach is described that is based on the transfer of hyperpolarization from para-hydrogen in view of generating a population imbalance between the two spin isomers of H 2 O. The approach is analogous to SABRE (Signal Amplification By Reversible Exchange) and makes use of the transfer of spin order from para-hydrogen to H 2 O in a hypothetical organometallic complex. The spin order transfer is expected to be most efficient at avoided level crossings. The highest achievable enrichment levels of para- and ortho-water are discussed. Copyright © 2018 Elsevier Inc. All rights reserved.

  16. Nuclear proliferation and terrorism

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This section of the book, Part III, has two chapters (9 and 10). Chapter 9, Nuclear Power and Proliferation of Nuclear Weapons, is disucssed under these subjects: nuclear nonproliferation: origins and status; requirements for nuclear weapons manufacture; current nuclear programs and proliferation capabilities; encouraging decisions to forego weapons; arms control; safeguards; attitudes and expectations. Chapter 10, Nuclear Terrorism, discusses these areas: theft of nuclear materials; attacks on nuclear reactors; responding to nuclear terrorism; security and civil liberties

  17. Nuclear politics

    International Nuclear Information System (INIS)

    Hall, Tony.

    1986-01-01

    Written by an arts graduate journalist this is intended for a non-technical general readership. It chronicles the history of the nuclear power industry in Britain from its beginnings, which were inextricably tied to the development of the atomic bomb, to the Sellafield investigation and Sizewell public inquiry. In particular the government decisions which have influenced the present structure and state of the industry are criticised. With important decisions about to be made the author questions the accountability of the nuclear industry and the government's ability to understand the complex technical aspects of the industry. (U.K.)

  18. Nuclear dilemma

    Energy Technology Data Exchange (ETDEWEB)

    Penn, J.

    Declaring nuclear preparedness 'immoral' helps to recreate the pacifism of 50 years ago. War itself is a dilemma, not the weapons with which it is waged. We must ask of the anti-war proposals: whom do they benefit. On the whole people concerned are ordinary citizens who are fearful of nuclear incineration. But marching with them is a spectrum of forces with other motivations and purposes. In a real life situation of international tension or crises, numbers of weapons in combination with their particular charateristics could mean the difference between peace and outbreak of war.

  19. Nuclear energy

    International Nuclear Information System (INIS)

    Lotter, A.C.

    1979-01-01

    The recent, terrifying threat of a major calamity at Pennsylvania's Three Mile Island power plant near Harrisburg reverberated across practically the whole of the civilised world. An almost incredible sequence of human and mechanical failures at this installation had stopped just short of disaster and had brought the unthinkable perilously close to happening. The accident had sprayed radioactive waste into the air and had led to the large scale evacuation of people from the endangered area, disrupted hundreds of thousands of lives and caused a crippling setback to the nuclear industry. In this article the author discusses the impact the Harrisburg incident has had on the nuclear industry

  20. Nuclear cardiology

    International Nuclear Information System (INIS)

    Bashore, T.M.; Shaffer, P.B.

    1985-01-01

    The birth of nuclear cardiology has generally been attributed to a 1927 experiment during which a radium salt was injected in one arm vein and the circulation time calculated by recording the arrival of the radioactivity in the opposite arm. This simple experiment lead to the radiocardiogram in the late 1940s that was used to measure left ventricular function and, later, cardiac output. This chapter provides a brief overview of nuclear cardiology. Methodology is presented when it is important for the understanding of test results. The use of these studies in the diagnosis and evaluation of patients with suspected cardiovascular disease is emphasized

  1. Nuclear fuel

    International Nuclear Information System (INIS)

    Azevedo, J.B.L. de.

    1980-01-01

    All stages of nuclear fuel cycle are analysed with respect to the present situation and future perspectives of supply and demand of services; the prices and the unitary cost estimation of these stages for the international fuel market are also mentioned. From the world resources and projections of uranium consumption, medium-and long term analyses are made of fuel availability for several strategies of use of different reactor types. Finally, the cost of nuclear fuel in the generation of electric energy is calculated to be used in the energetic planning of the electric sector. (M.A.) [pt

  2. Nuclear reactions

    International Nuclear Information System (INIS)

    Lane, A.M.

    1980-01-01

    In reviewing work at Harwell over the past 25 years on nuclear reactions it is stated that a balance has to be struck in both experiment and theory between work on cross-sections of direct practical relevance to reactors and on those relevant to an overall understanding of reaction processes. The compound nucleus and direct process reactions are described. Having listed the contributions from AERE, Harwell to developments in nuclear reaction research in the period, work on the optical model, neutron capture theory, reactions at doorway states with fine structure, and sum-rules for spectroscopic factors are considered in more detail. (UK)

  3. The nuclear

    International Nuclear Information System (INIS)

    2011-01-01

    This report proposes an overview of knowledge and technical aspects regarding nuclear energy. It presents the phenomenon of radioactivity and its measurement and thresholds, describes the fuel cycle, presents the different principles and types of nuclear reactors, and more precisely the pressurized water reactors and their various models (900, 1300, 1400 and 1600 MW). It presents other reactors: boiling water reactors, heavy water reactors, high temperature reactors, fourth generation reactors. It addresses the issues of wastes and releases, presents the OSPAR convention, the issues of management and safety. It presents the national safety bodies (ASN, IRSN, HCTISM) and international bodies

  4. Nuclear medicine

    International Nuclear Information System (INIS)

    Reichelt, H.G.

    1980-01-01

    Nuclear medicine as a complex diagnostical method is used mainly to detect functional organic disorders, to locate disorders and for radioimmunologic assays (RIA) in vitro. In surgery, its indication range comprises the thyroid (in vivo and in vitro), liver and bile ducts, skeletal and joint diseases, disorders of the cerebro-spinal liquor system and the urologic disorders. In the early detection of tumors, the search for metastases and tumor after-care, scintiscanning and the tumor marcher method (CEA) can be of great practical advantage, but the value of myocardial sciritiscanning in cardiac respectively coronary disorders is restricted. The paper is also concerned with the radiation doses in nuclear medicine. (orig.) [de

  5. Para compreender a ciberliteratura

    Directory of Open Access Journals (Sweden)

    Lucia Santaella

    2012-12-01

    Full Text Available http://dx.doi.org/10.5007/1807-9288.2012v8n2p229   Mediante as mídias digitais, a configuração da literatura sofreu um salto qualitativo em todos os seus aspectos. O espaço virtual gerado pelas redes de computadores funciona como um novo meio. Abre-se com ele uma miríade de oportunidades que expandem o conceito de literatura em função da emergência de novas formas de criação literária. Disso decorre que a criação, a teoria e a crítica literárias exigem a redefinição de seus paradigmas herdados da era de Gutenberg. Tendo isso em vista, este artigo está voltado para a construção textual e hipertextual no espaço digital, o que implica uma exploração do que é ciberliteratura, em que ela se cruza e em que diverge da literatura impressa, que estratégias significantes a caracterizam e como essas estratégias são interpretadas pelos usuários na sua busca de significado.

  6. para promover la salud

    Directory of Open Access Journals (Sweden)

    Ma. del Consuelo Chapela

    2002-01-01

    Full Text Available Hablar de educación a distancia sustentada en el desarrollo de la cibernética obliga a reflexionar sobre sus definiciones, objetivos y medios, especialmente si pensamos en las necesidades de la fracción de población que no tiene acceso a las posibilidades que ofrece el desarrollo tecnológico. En este trabajo se presenta e ilustra con un ejemplo práctico, una perspectiva sobre las posibilidades de la educación a distancia desde las necesidades de la promoción de la salud entre grupos de población marginada en el mundo virtual. Se propone la creación de bibliotecas itinerantes regionales que pongan a disposición de la población con acceso limitado a la información, la tecnología comunicativa necesaria para apoyar los trabajos de promoción de la salud.

  7. Nuclear energy and nuclear technology

    International Nuclear Information System (INIS)

    Luescher, E.

    1982-01-01

    This book originated in the training courses for teachers of grammar- and secondary schools in Dillingen (Bavaria). The aim of these courses is to become informed about the latest state in one field of physics. The lectures are well-known experts in the respective fields. In the latest study (1980) of the National Academy of Sciences the experts came to the conclusion that without further development nuclear power plants the utilization of too much coal would become necessary and involve irreversible environmental damage (see chapter 6). There are two important obstacles impeding the further extension of nuclear energy. The first problem to be solved is the processing and storage of radioactive waste. This is a more technical task and can be treated in a satisfactory way. The second obstacle is less easy to take as the population has to be convinced that a nuclear power plant can be operated with almost unbelievable safety (see chapter 5) and be shut down safely in the case of incidents. The most promising possibility of controlled nuclear fusion as energy source is still many decades- if feasible at all- away from being performed (see chapter. 7). In the Soviet Union 25% of the electric energy production shall be proceed from nuclear power plants by the year 1990. (orig./GL) [de

  8. Nuclear winter or nuclear fall?

    Science.gov (United States)

    Berger, André

    Climate is universal. If a major modern nuclear war (i.e., with a large number of small-yield weapons) were to happen, it is not even necessary to have a specific part of the world directly involved for there to be cause to worry about the consequences for its inhabitants and their future. Indeed, smoke from fires ignited by the nuclear explosions would be transported by winds all over the world, causing dark and cold. According to the first study, by Turco et al. [1983], air surface temperature over continental areas of the northern mid-latitudes (assumed to be the nuclear war theatre) would fall to winter levels even in summer (hence the term “nuclear winter”) and induce drastic climatic conditions for several months at least. The devastating effects of a nuclear war would thus last much longer than was assumed initially. Discussing to what extent these estimations of long-term impacts on climate are reliable is the purpose of this article.

  9. Para-equilibrium phase diagrams

    International Nuclear Information System (INIS)

    Pelton, Arthur D.; Koukkari, Pertti; Pajarre, Risto; Eriksson, Gunnar

    2014-01-01

    Highlights: • A rapidly cooled system may attain a state of para-equilibrium. • In this state rapidly diffusing elements reach equilibrium but others are immobile. • Application of the Phase Rule to para-equilibrium phase diagrams is discussed. • A general algorithm to calculate para-equilibrium phase diagrams is described. - Abstract: If an initially homogeneous system at high temperature is rapidly cooled, a temporary para-equilibrium state may result in which rapidly diffusing elements have reached equilibrium but more slowly diffusing elements have remained essentially immobile. The best known example occurs when homogeneous austenite is quenched. A para-equilibrium phase assemblage may be calculated thermodynamically by Gibbs free energy minimization under the constraint that the ratios of the slowly diffusing elements are the same in all phases. Several examples of calculated para-equilibrium phase diagram sections are presented and the application of the Phase Rule is discussed. Although the rules governing the geometry of these diagrams may appear at first to be somewhat different from those for full equilibrium phase diagrams, it is shown that in fact they obey exactly the same rules with the following provision. Since the molar ratios of non-diffusing elements are the same in all phases at para-equilibrium, these ratios act, as far as the geometry of the diagram is concerned, like “potential” variables (such as T, pressure or chemical potentials) rather than like “normal” composition variables which need not be the same in all phases. A general algorithm to calculate para-equilibrium phase diagrams is presented. In the limit, if a para-equilibrium calculation is performed under the constraint that no elements diffuse, then the resultant phase diagram shows the single phase with the minimum Gibbs free energy at any point on the diagram; such calculations are of interest in physical vapor deposition when deposition is so rapid that phase

  10. Marcadores para la Realidad Aumentada para fines educativos

    Directory of Open Access Journals (Sweden)

    María Reina Zarate Nava

    2013-12-01

    Full Text Available La Realidad Aumentada (AR es considerada por algunos expertos como la tecnología en crecimiento para el 2014, en diferentes sectores: ingeniería, educación, juegos y negocios, siendo este último el más usado en él 2013. Sin embargo en el sector educativo la AR se presenta en algunos proyectos que se han desarrollado para diferentes áreas de las ciencias, como Química, Física y Matemáticas, lo anterior con el objetivo de facilitar el proceso de Enseñanza-Aprendizaje. En el presente artículo se presenta el modelo de patrones utilizado para un Proyecto AR enfocado en Química, el cual presenta un conjunto de patrones que fueron valorados para facilitar el rastreo de los objetos y a su vez el entendimiento de algunos materiales de los laboratorios de Química I.

  11. Nuclear crime

    International Nuclear Information System (INIS)

    Braun, P.; Ferchland, B.

    1993-01-01

    The article discusses the legal provisions (Criminal Code (StGB), weapons Control Act) applicable in Germany to combat illegal trading of nuclear fuels and other readioactive materials. The authors conclude that part of the provisions are not in live with the rights and duties of the police, and they evolve near-practice proposals for remedy and legal improvement. (hP) [de

  12. 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)

  13. Nuclear energy

    International Nuclear Information System (INIS)

    Reuss, Paul

    2012-01-01

    With simple and accessible explanations, this book presents the physical principles, the history and industrial developments of nuclear energy. More than 25 years after the Chernobyl accidents and few months only after the Fukushima one, it discusses the pros and cons of this energy source with its assets and its risks. (J.S.)

  14. Nuclear imaging

    International Nuclear Information System (INIS)

    Miller, J.H.; Reid, B.S.

    1985-01-01

    Nuclear imaging, utilizing relatively low photon energy emitting isotopes, allows an assessment of anatomic configuration and organ function. This method of imaging is predicted on the utilization of physiologically active radioisotope-labeled compounds or biologically active radioisotopes. Localization of such isotopes in normal or abnormal concentrations may be due to varying physiological or pathological mechanisms

  15. Nuclear Energy

    International Nuclear Information System (INIS)

    1982-11-01

    A brief indication is given of the United Kingdom nuclear power programme including descriptions of the fission process, the Magnox, AGR and PWR type reactors, the recycling process, waste management and decommissioning, safety precautions, the prototype fast reactor at Dounreay, and the JET fusion experiment. (U.K.)

  16. Nuclear physics

    International Nuclear Information System (INIS)

    Guzman B, O.; Vallejo M, J.I.; Cardenas C, H.F.

    1989-01-01

    A historical review of the evolution of the Nuclear Physics Section at the IAN is presented along the 30 years of existence of the Institute. Objectives, structure, programs and goal are historically examined. Present status of the section and its projection on national development is also analyzed

  17. Nuclear films

    International Nuclear Information System (INIS)

    Malone, Peter.

    1985-01-01

    This booklet is a resource for the study of feature films that highlight the theme of nuclear war. It provides basic credits and brief indication of the theme, treatment, quality and particular notable aspects; and a series of questions raised by the film. Seventy feature films and thirty documentaries are examined

  18. Nuclear reactions

    International Nuclear Information System (INIS)

    Corner, J.; Richardson, K.; Fenton, N.

    1990-01-01

    Nuclear reactions' marks a new development in the study of television as an agency of public policy debate. During the Eighties, nuclear energy became a major international issue. The disasters at Three-mile Island and Chernobyl created a global anxiety about its risks and a new sensitivity to it among politicians and journalists. This book is a case-study into documentary depictions of nuclear energy in television and video programmes and into the interpretations and responses of viewers drawn from many different occupational groupings. How are the complex and specialist arguments about benefit, risk and proof conveyed through the different conventions of commentary, interview and film sequence? What symbolic associations does the visual language of television bring to portrayals of the issue? And how do viewers make sense of various and conflicting accounts, connecting what they see and hear on the screen with their pre-existing knowledge, experience and 'civic' expectations. The authors examine some of the contrasting forms and themes which have been used by programme makers to explain and persuade, and then give a sustained analysis of the nature and sources of viewers' own accounts. 'Nuclear Reactions' inquires into the public meanings surrounding energy and the environment, spelling out in its conclusion some of the implications for future media treatments of this issue. It is also a key contribution to the international literature on 'television knowledge' and the processes of active viewing. (author)

  19. Nuclear fragmentation

    International Nuclear Information System (INIS)

    Chung, K.C.

    1989-01-01

    An introduction to nuclear fragmentation, with emphasis in percolation ideas, is presented. The main theoretical models are discussed and as an application, the uniform expansion approximation is presented and the statistical multifragmentation model is used to calculate the fragment energy spectra. (L.C.)

  20. Nuclear physics

    International Nuclear Information System (INIS)

    1990-01-01

    This work describes the actual situation of nuclear physics in Brazil as well as its perspectives of developments and real needs in the next decade. It discusses the main projects and the financing of brazilian research groups and Universities. (A.C.A.S.)