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Sample records for brazil reator nuclear

  1. 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)

  2. Technical and institutional safety features of nuclear power plants in Brazil. Aspectos tecnicos e institucionais da seguranca dos reatores nucleares no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, L P [Sociedade Brasileira de Fisica, Rio de Janeiro, RJ (Brazil)

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.).

  3. 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)

  4. LDC nuclear power: Brazil

    International Nuclear Information System (INIS)

    Johnson, V.

    1982-01-01

    Brazil has been expanding its nuclear power since 1975, following the Bonn-Brasilia sales agreement and the 1974 denial of US enriched uranium, in an effort to develop an energy mix that will reduce dependence and vulnerability to a single energy source or supplier. An overview of the nuclear program goes on to describe domestic non-nuclear alternatives, none of which has an adequate base. The country's need for transfers of capital, technology, and raw materials raises questions about the advisability of an aggressive nuclear program in pursuit of great power status. 33 references

  5. Nuclear material control in Brazil

    International Nuclear Information System (INIS)

    Marzo, M.A.S.; Iskin, M.C.L.; Palhares, L.C.; Almeida, S.G. de.

    1988-01-01

    A general view about the safeguards activities in Brazil is presented. The national system of accounting for and control of nuclear materials is described. The safeguards agreements signed by Brazil are presented, the facilities and nuclear material under these agreements are listed, and the dificulties on the pratical implementation are discussed. (E.G.) [pt

  6. Application of photoelasticity to study stress in component of the fuel element of nuclear reator

    International Nuclear Information System (INIS)

    Diniz, S.M.C.

    1987-11-01

    The fuel assembly, in the core of the nuclear reactor, is submitted to a system of forces (weight, buoyancy and hydraulic lift-up) with a resultant oriented in the direction of the coolant flow. To assure the assembly stability, under all operation conditions of the nuclear reactor, a holding-down device composed of four leaf springs is used. The safe/operation of the reactor depends on the capacity of such springs to support the maximum loads applied on them. The strictly mathematical methods for stress analysis of these springs are very complex, due to several factors such as: tri-dimensional geometry, changing loading, plastic strains and stress concentration. The stress analysis of these springs was performed using the photoelastic method. This technique has been proved to be adequate to the leaf spring analysis. In order to permit the evaluation of the potentialities of the employed method the Photoelasticity is decribed in its multiples purposes; that is, two-dimensional problems, stress frozen technique and reflection photoelasticity. The results obtained certify the role of the Photoelasticity, as a powerfull tool to the stress analyst and to the nuclear industry as well. (author) [pt

  7. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  8. Nuclear research reactors in Brazil

    International Nuclear Information System (INIS)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias

    2011-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Bianchi, Paulo Henrique

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Vianna Filho, Alfredo Marques

    2016-07-01

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

  11. The situation of nuclear research in Brazil

    International Nuclear Information System (INIS)

    Alves, R.N.

    1989-04-01

    In order to understand the nuclear research situation in Brazil, one must examine the historical facts and their political, economical and social dimensions. In the first part of this work, the international aspects of the nuclear area and the corresponding measures adopted in Brazil are examined. The reasons that caused the country to adopt the current development model are presented. A proposal that will permit Brazil to develop and use nuclear energy in the way it wants and not as it might be imposed is presented. 4 tabs

  12. Distribution of nuclear medicine service in Brazil

    International Nuclear Information System (INIS)

    Silva, Ana Carolina Costa da; Duarte, Alessandro; Santos, Bianca Maciel dos

    2011-01-01

    The Brazil does not posses a good distribution of nuclear medicine service por all his territory. This paper shows the difference among country regions as far the number of clinics of nuclear medicine as is concerning, and also doctors licensed in the area and radioprotection supervisors, both licensed by the Brazilian Nuclear Energy Commission (CNEN)

  13. Argentina and Brazil: an evolving nuclear relationship

    International Nuclear Information System (INIS)

    Redick, J.R.

    1990-01-01

    Argentina and Brazil have Latin America's most advanced nuclear research and power programs. Both nations reject the Non-Proliferation Treaty (NPT), and have not formally embraced the Tlatelolco Treaty creating a regional nuclear-weapon-free zone. Disturbing ambiguities persist regarding certain indigenous nuclear facilities and growing nuclear submarine and missile capabilities. For these, and other reasons, the two nations are widely considered potential nuclear weapon states. However both nations have been active supporters of the International Atomic Energy Agency (IAEA) and have, in recent years, assumed a generally responsible position in regard to their own nuclear export activities (requiring IAEA safeguards). Most important, however, has been the advent of bilateral nuclear cooperation. This paper considers the evolving nuclear relationship in the context of recent and dramatic political change in Argentina and Brazil. It discusses current political and nuclear developments and the prospects for maintaining and expanding present bilateral cooperation into an effective non-proliferation arrangement. (author)

  14. 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)

  15. A nuclear power reactor concept for Brazil

    International Nuclear Information System (INIS)

    Sefidvash, F.

    1980-01-01

    For the purpose of developing an independent national nuclear technology and effective manner of transferring such a technology, as well as developing a modern reactor, a new nuclear power reactor concept is proposed which is considered as a suitable and viable project for Brazil to support its development and finally construct its prototype as an indigeneous venture. (Author) [pt

  16. Nuclear power plant safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The Code of Practice for the Safe Operation of Nuclear Power Plants states that: 'In discharging its responsibility for public health and safety, the government should ensure that the operational safety of a nuclear reactor is subject to surveillance by a regulatory body independent of the operating organization'. In Brazil this task is being carried out by the Comissao Nacional de Energia Nuclear in accordance with the best international practice. (orig./RW)

  17. Ergonomics in the licensing and evaluation of nuclear reactors control room; A ergonomia no licenciamento e na avaliacao de salas de controle de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Isaac Jose Antonio Luquetti dos [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Vidal, Mario Cesar Rodriguez [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia de Producao

    2002-07-01

    A nuclear control room is a complex system that controls a thermodynamic process used to produce electrical energy. The operators interact with the control room through interfaces that have significant implications to nuclear plant safety and influence the operator activity. The TMI (Three Mile Island) accident demonstrated that only the anthropometric aspects were not enough for an adequate nuclear control room design. The studies showed that the accident was aggravated because the designers had not considered adequately human factor aspects. After TMI accident, the designers introduce in the nuclear control room development only human factors standards and human factors guidelines. The ergonomics approaches was not considered. Our objective is introduce in nuclear control room design and nuclear control room evaluation, a methodology that. includes human factors standards, human factors guidelines and ergonomic approaches, the operator activity analysis. (author)

  18. Proceedings of the 3. Workshop on Nuclear Physics in Brazil

    International Nuclear Information System (INIS)

    1980-01-01

    This publication is the final report of the III Workshop on Nuclear Physics in Brazil. Many works were presented on the fields related to Nuclear Physics. It was organized some work groups which discussed the following topics: Perspectivas of Nuclear Physics in Brazil, Personnel Formation and Related Instrumentation. (A.C.A.S.) [pt

  19. A nuclear reactor core fuel reload optimization using Artificial-Ant-Colony Connective Networks; Recarga de reatores nucleares utilizando redes conectivas de colonias de formigas artificiais

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Alan M.M. de; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear]. E-mail: alan@lmp.ufrj.br; schirru@lmp.ufrj.br

    2005-07-01

    A Pressurized Water Reactor core must be reloaded every time the fuel burnup reaches a level when it is not possible to sustain nominal power operation. The nuclear core fuel reload optimization consists in finding a burned-up and fresh-fuel-assembly pattern that maximizes the number of full operational days. This problem is NP-hard, meaning that complexity grows exponentially with the number of fuel assemblies in the core. Besides that, the problem is non-linear and its search space is highly discontinual and multimodal. In this work a parallel computational system based on Ant Colony System (ACS) called Artificial-Ant-Colony Networks is introduced to solve the nuclear reactor core fuel reload optimization problem. ACS is a system based on artificial agents that uses the reinforcement learning technique and was originally developed to solve the Traveling Salesman Problem, which is conceptually similar to the nuclear fuel reload problem. (author)

  20. 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)

  1. 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)

  2. Nuclear reactors project optimization based on neural network and genetic algorithm; Otimizacao em projetos de reatores nucleares baseada em rede neural e algoritmo genetico

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Claudio M.N.A. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Schirru, Roberto; Martinez, Aquilino S. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia

    1997-12-01

    This work presents a prototype of a system for nuclear reactor core design optimization based on genetic algorithms and artificial neural networks. A neural network is modeled and trained in order to predict the flux and the neutron multiplication factor values based in the enrichment, network pitch and cladding thickness, with average error less than 2%. The values predicted by the neural network are used by a genetic algorithm in this heuristic search, guided by an objective function that rewards the high flux values and penalizes multiplication factors far from the required value. Associating the quick prediction - that may substitute the reactor physics calculation code - with the global optimization capacity of the genetic algorithm, it was obtained a quick and effective system for nuclear reactor core design optimization. (author). 11 refs., 8 figs., 3 tabs.

  3. Models of signal validation using artificial intelligence techniques applied to a nuclear reactor; Modelos de validacao de sinal utilizando tecnicas de inteligencia artificial aplicados a um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Mauro V. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia

    2000-07-01

    This work presents two models of signal validation in which the analytical redundancy of the monitored signals from a nuclear plant is made by neural networks. In one model the analytical redundancy is made by only one neural network while in the other it is done by several neural networks, each one working in a specific part of the entire operation region of the plant. Four cluster techniques were tested to separate the entire operation region in several specific regions. An additional information of systems' reliability is supplied by a fuzzy inference system. The models were implemented in C language and tested with signals acquired from Angra I nuclear power plant, from its start to 100% of power. (author)

  4. Modelling of critical functions of nuclear reactors using Fild Programmable Gate Array; Modelagem de funcoes criticas de reatores nucleares utilizando Fild Programmable Gate Array

    Energy Technology Data Exchange (ETDEWEB)

    Teixeira, Pamela Iara Nolasco

    2016-07-01

    This paper proposes the development of a method using FPGA for critical security functions of a nuclear reactor. It was implemented two critical safety functions in VHDL, which is a way to describe, through a program, the behavior of a circuit or digital component. Two critical security functions, FCS Core Cooling, responsible for cooling the reactor core in the charts of the plant and also in the event of accidents involving loss of coolant and FCS Heat Transfer, responsible for cooling the reactor core in the event an accident with loss of coolant were implemented. In this Dissertation it was chosen the use of FPGA, because - due to the effects of aging, obsolescence issues, environmental degradation and mechanical failures - nuclear power plants need to replace their older systems by new ones based on digital technology. The technologies obtained using a system described in hardware language can be implemented in a programmable device, having the advantage of changing the code at any time. (author)

  5. Nuclear cooperation between Brazil and Federal Republic of Germany

    International Nuclear Information System (INIS)

    Syllus, C.

    1989-01-01

    The Brazil-Federal Republic of Germany Cooperation Agreement for constructing nuclear power plants, and the process of nuclear tecnology transfer in the different areas of design, are discussed. (M.C.K.) [pt

  6. Thermohydraulic simulation of HTR-10 nuclear reactor core using realistic CFD approach; Simulacao termohidraulica do nucleo do reator nuclear HTR-10 com o uso da abordagem realistica CFD

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Alexandro S.; Dominguez, Dany S., E-mail: alexandrossilva@gmail.com, E-mail: dsdominguez@gmail.com [Universidade Estadual de Santa Cruz (UESC), Ilheus, BA (Brazil); Mazaira, Leorlen Y. Rojas; Hernandez, Carlos R.G., E-mail: leored1984@gmail.com, E-mail: cgh@instec.cu [Instituto Superior de Tecnologias y Ciencias Aplicadas, La Habana (Cuba); Lira, Carlos Alberto Brayner de Oliveira, E-mail: cabol@ufpe.br [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil)

    2015-07-01

    High-temperature gas-cooled reactors (HTGRs) have the potential to be used as possible energy generation sources in the near future, owing to their inherently safe performance by using a large amount of graphite, low power density design, and high conversion efficiency. However, safety is the most important issue for its commercialization in nuclear energy industry. It is very important for safety design and operation of an HTGR to investigate its thermal–hydraulic characteristics. In this article, it was performed the thermal–hydraulic simulation of compressible flow inside the core of the pebble bed reactor HTR (High Temperature Reactor)-10 using Computational Fluid Dynamics (CFD). The realistic approach was used, where every closely packed pebble is realistically modelled considering a graphite layer and sphere of fuel. Due to the high computational cost is impossible simulate the full core; therefore, the geometry used is a column of FCC (Face Centered Cubic) cells, with 41 layers and 82 pebbles. The input data used were taken from the thermohydraulic IAEA Benchmark (TECDOC-1694). The results show the profiles of velocity and temperature of the coolant in the core, and the temperature distribution inside the pebbles. The maximum temperatures in the pebbles do not exceed the allowable limit for this type of nuclear fuel. (author)

  7. Reflexions on the expansion of nuclear generation in Brazil

    International Nuclear Information System (INIS)

    Freitas, Juliana de Moraes Marreco de

    2006-01-01

    This article analyses the pros and cons of the nuclear generation in Brazil, involving in a large discussion the technological perspectives both economic, social and environmental. The objective is to rise the main questions about the polemical nuclear expansion in Brazil

  8. Avaliação da suscetibilidade à corrosão sob tensão da ZAC do aço inoxidável AISI 316L em ambiente de reator nuclear PWR Stress corrosion cracking of stainless steel AISI 316L HAZ in PWR Nuclear reactor environment

    Directory of Open Access Journals (Sweden)

    Mônica Maria de Abreu Mendonça Schvartzman

    2009-09-01

    Full Text Available Aços carbono de baixa liga e aços inoxidáveis são amplamente utilizados nos circuitos primários de reatores nucleares do tipo PWR (Pressurized Water Reactor. Ligas de níquel são empregadas na soldagem destes materiais devido a características como elevadas resistências mecânica e à corrosão, coeficiente de expansão térmica adequado, etc. Nos últimos 30 anos, a corrosão sob tensão (CST tem sido observada principalmente nas regiões das soldas entre materiais dissimilares existentes nestes reatores. Este trabalho teve como objetivo avaliar, por comparação, a suscetibilidade à corrosão sob tensão da zona afetada pelo calor (ZAC do aço inoxidável austenítico AISI 316L quando submetida a um ambiente similar ao do circuito primário de um reator nuclear PWR nas temperaturas de 303ºC e 325ºC. Para esta avaliação empregou-se o ensaio de taxa de deformação lenta - SSRT (Slow Strain Rate Test. Os resultados indicaram que a CST é ativada termicamente e que a 325ºC pode-se observar a presença mais significativa de fratura frágil decorrente do processo de corrosão sob tensão.In pressurized water reactors (PWRs, low alloy carbon steels and stainless steel are widely used in the primary water circuits. In most cases, Ni alloys are used to joint these materials and form dissimilar welds. These alloys are known to accommodate the differences in composition and thermal expansion of the two materials. Stress corrosion cracking of metals and alloys is caused by synergistic effects of environment, material condition and stress. Over the last thirty years, CST has been observed in dissimilar metal welds. This study presents a comparative work between the CST in the HAZ (Heat Affected Zone of the AISI 316L in two different temperatures (303ºC and 325ºC. The susceptibility to stress corrosion cracking was assessed using the slow strain rate tensile (SSRT test. The results of the SSRT tests indicated that CST is a thermally

  9. Nuclear safeguards in Brazil and Argentina: 25 years of ABACC

    Science.gov (United States)

    Kassenova, Togzhan

    2017-11-01

    As possessors of advanced nuclear technology, Brazil and Argentina bear special responsibility for helping the international community and neighbors in their region feel confident that their nuclear programs are peaceful, secure, and safe. Over the past 25 years, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) has played an indispensable role in strengthening such confidence by implementing nuclear safeguards in the two countries. Today, ABACC carries out safeguards inspections at a total of 76 nuclear facilities in Brazil and Argentina. This article describes how Brazil and Argentina view trends in the global nonproliferation regime and international nuclear safeguards, and explains how these trends relate to unique challenges and opportunities facing Brazil, Argentina, and ABACC.

  10. National report of Brazil: nuclear safety convention - September 1998

    International Nuclear Information System (INIS)

    1998-09-01

    This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil

  11. Technology transfer assessment in the nuclear agreement Brazil-Germany

    International Nuclear Information System (INIS)

    Cecchi, J.C.

    1985-04-01

    The three main arguments utilized in the Nuclear Brazil-Germany Agreement celebrated in 1975 were the following: a) the low Brazilian hydroelectric potential insufficient to attend the increasing of electrical energy demand; b) the low cost of nuclear energy related to hydroelectric energy: c) and finally, the nuclear technology transfer, involving inclusive the fuel cycle and that could permit to Brazil self-sufficiency in the nuclear energy field. Thus, this work intends to describe and discussing the 'technology transfer strategy' trying to understand and showing which are its main characteristics, and also which are the real actuals results. (author) [pt

  12. National report of Brazil: nuclear safety convention - September 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

  13. Nuclear proliferation. I. Atoms for Brazil, dangers for all

    International Nuclear Information System (INIS)

    Gall, N.

    1976-01-01

    West Germany and Brazil, by seeking to establish their independence in the transfer of nuclear technology to a developing country, have raised international anxieties over how to finance and manage nuclear trade in a way that will secure peace. The deal, which commits the two countries to a program of uranium exploration and mining, enrichment, fuel fabrication and reprocessing, and power plant construction, means food supplies, jobs, and contracts for Germany and economic development for Brazil. Of concern to the rest of the world are the opportunities for diverting nuclear materials to weapons. Both countries have agreed to comply with the International Atomic Energy Agency's safeguards agreement, but Brazil is not bound by it. Brazil's development is making her the dominant power in South America and altering her relationship with the United States. A review of the West German-Brazilian agreement focuses on the historical competition for export markets and the lessening of U.S. control over the enriched uranium market

  14. The global nuclear safety regime and its impact in Brazil

    International Nuclear Information System (INIS)

    Almeida, C.

    2004-01-01

    This work describes the Global Nuclear Safety Regime that was established worldwide after the accident at the Tchernobyl nuclear power plant. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. The impact of this Global Regime in Brazil is also discussed. (Author)

  15. Patterns identification in supervisory systems of nuclear reactors installations and gas pipelines systems using self-organizing maps; Identificacao de padroes em sistemas supervisorios de instalacoes de reatores nucleares e em sistemas de gasodutos utilizando mapas auto-organizaveis

    Energy Technology Data Exchange (ETDEWEB)

    Doraskevicius Junior, Waldemar

    2005-07-01

    Self-Organizing Maps, SOM, of Kohonen were studied, implemented and tested with the aim of developing, for the energy branch, an effective tool especially for transient identification in nuclear reactors and for gas pipelines networks logistic supervision, by classifying operations and identifying transients or abnormalities. The digital system for the test was developed in Java platform, for the portability and scalability, and for belonging to free development platforms. The system, executed in personal computers, showed satisfactory results to aid in decision taking, by classifying IRIS (International Reactor Innovative and Secure) reactor operation conditions (data from simulator) and by classifying Southeast (owner: TRANSPETRO - Brazil) gas pipeline network. Various adaptations were needed for such business, as new topologies for the output layer of artificial neural network and particular preparation for the input data. (author)

  16. Thermal fluid dynamics study of nuclear advanced reactors of high temperature using RELAP5-3D; Estudo termofluidodinâmico de reatores nucleares avançados de alta temperatura utilizando o RELAP5-3D

    Energy Technology Data Exchange (ETDEWEB)

    Scari, Maria Elizabeth

    2017-07-01

    Fourth Generation nuclear reactors (GEN-IV) are being designed with special features such as intrinsic safety, reduction of isotopic inventory and use of fuel in proliferation-resistant cycles. Therefore, the investigation and evaluation of operational and safety aspects of the GEN-IV reactors have been the subject of numerous studies by the international community and also in Brazil. In 2008, in Brazil, was created the National Institute of Science and Technology of Innovative Nuclear Reactors, focusing on studies of projects and systems of new generation reactors, which included GEN-IV reactors as well as advanced PWR (Pressurized Water Reactor) concepts. The Department of Nuclear Engineering of the Federal University of Minas Gerais (DEN-UFMG) is a partner of this Institute, having started studies on the GEN-IV reactors in the year 2007. Therefore, in order to add knowledge to these studies, in this work, three projects of advanced reactors were considered to verify the simulation capability of the thermo-hydraulic RELAP5-3D code for these systems, either in stationary operation or in transient situations. The addition of new working fluids such as ammonia, carbon dioxide, helium, hydrogen, various types of liquid salts, among them Flibe, lead, lithium-bismuth, lithium-lead, was a major breakthrough in this version of the code, allowing also the simulation of GEN-IV reactors. The modeling of the respective core of an HTTR (High Temperature Engineering Test Reactor), HTR-10 (High Temperature Test Module Reactor) and LS-VHTR (Liquid-Salt-Cooled Very-High-Temperature Reactor) were developed and verified in steady state comparing the values found through the calculations with reference data from other simulations, when it is possible. The first two reactors use helium gas as coolant and the LS-VHTR uses a mixture of 66% LiF and 34% of BeF{sub 2}, the LiF-BeF{sub 2}, also know as Flibe. All the studied reactors use enriched uranium as fuel, in form of TRISO

  17. Nuclear material measurement system in Brazil

    International Nuclear Information System (INIS)

    Almeida, S.G. de.

    1988-01-01

    The description of the activities developed at the Safeguards Laboratory of Brazilian Nuclear Energy Commission is done. The methods and techniques used for measuring and evaluating nuclear materials and facilities are presented. (E.G.) [pt

  18. Communication challenges in the perspective of nuclear organizations in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Tariana Brocardo, E-mail: tariana@usp.br [Universidade de São Paulo (USP), SP (Brazil). Escola de Comunicações e Artes

    2017-07-01

    The aim of this paper is to discuss the results of a study which reveals the communication challenges faced by organizations of the nuclear segment in Brazil towards its public acceptance. This is a descriptive study with qualitative approach based on primary data collection made through interview with non-probabilistic sample and categorical content analysis as method. The study was carried out with managers, technicians and communicators of three representative organizations of the segment in the country – CNEN, Eletronuclear and IPEN – in the period ranging from October, 2015, to March, 2016, as part of a greater study composing the author’s Master’s dissertation presented at Universidade de São Paulo in October, 2016. As results, the main communication challenges spotted by nuclear professionals in Brazil are lack of public acceptance of the nuclear energy in the country, followed by low levels of communication of the benefits of the nuclear field, lack of budget for investing in communication strategy and activities and institutional bureaucracy, as well as political motives and professionals being politically appointed for holding communication positions. Other communication-related challenges faced by the nuclear field in Brazil mentioned by interviewees include employees without adequate amount of time to dedicate to communication or unfit for this specific work, excessive use of technical language, discredit of the nuclear area within local society, lack of interest by the media and difficulty for hiring new communication professionals. This research was financially supported by CAPES. 1. (author)

  19. Communication challenges in the perspective of nuclear organizations in Brazil

    International Nuclear Information System (INIS)

    Machado, Tariana Brocardo

    2017-01-01

    The aim of this paper is to discuss the results of a study which reveals the communication challenges faced by organizations of the nuclear segment in Brazil towards its public acceptance. This is a descriptive study with qualitative approach based on primary data collection made through interview with non-probabilistic sample and categorical content analysis as method. The study was carried out with managers, technicians and communicators of three representative organizations of the segment in the country – CNEN, Eletronuclear and IPEN – in the period ranging from October, 2015, to March, 2016, as part of a greater study composing the author’s Master’s dissertation presented at Universidade de São Paulo in October, 2016. As results, the main communication challenges spotted by nuclear professionals in Brazil are lack of public acceptance of the nuclear energy in the country, followed by low levels of communication of the benefits of the nuclear field, lack of budget for investing in communication strategy and activities and institutional bureaucracy, as well as political motives and professionals being politically appointed for holding communication positions. Other communication-related challenges faced by the nuclear field in Brazil mentioned by interviewees include employees without adequate amount of time to dedicate to communication or unfit for this specific work, excessive use of technical language, discredit of the nuclear area within local society, lack of interest by the media and difficulty for hiring new communication professionals. This research was financially supported by CAPES. 1. (author)

  20. Annual report 1999 - Brazil Nuclear Industry (INB)

    International Nuclear Information System (INIS)

    2000-01-01

    This document presents the 1999 annual report covering the following activities: nuclear fuel, resources and application, ISO 9001, environment social activities, personnel, financial indicators, and countability

  1. Future of nuclear energy for electricity generation in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Maiorino, Jose R.; Moreira, Joao M.L.; Carajlescov, Pedro, E-mail: joserubens.maiorino@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: pedro.carajlescov@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

    2015-07-01

    We discuss in this paper the medium- and long- terms evolution of nuclear power in Brazil considering official governmental studies and reports prepared by research groups. The documents reviewed include the national energy balance (BEN, 2014), the short-term planning (PDEE, 2023) and long-term planning (PNE-2030) documents emitted by EPE, and studies conducted by independent institutions and researchers. The studies consider different scenarios regarding gross national product growth and institutional development for the country and conclude that nuclear power should increase its role in Brazil. The generation matrix should diversity by 2030 and 2040 with hydropower decreasing its share from today's 70 % to values between 47 and 57 %. Nuclear power is considered a viable alternative for base load electricity generation in Brazil; to reduce generation risks during dry seasons, and to facilitate the operation of the whole power generation system. The share of nuclear power may reach values between 8 % and 15 % by 2040 according to different scenarios. To meet such growth and facilitate new investments, it is necessary to change the legal framework of the sector, and allow private ownership of enterprises to build and operate nuclear power plants in the country. (author)

  2. Future of nuclear energy for electricity generation in Brazil

    International Nuclear Information System (INIS)

    Maiorino, Jose R.; Moreira, Joao M.L.; Carajlescov, Pedro

    2015-01-01

    We discuss in this paper the medium- and long- terms evolution of nuclear power in Brazil considering official governmental studies and reports prepared by research groups. The documents reviewed include the national energy balance (BEN, 2014), the short-term planning (PDEE, 2023) and long-term planning (PNE-2030) documents emitted by EPE, and studies conducted by independent institutions and researchers. The studies consider different scenarios regarding gross national product growth and institutional development for the country and conclude that nuclear power should increase its role in Brazil. The generation matrix should diversity by 2030 and 2040 with hydropower decreasing its share from today's 70 % to values between 47 and 57 %. Nuclear power is considered a viable alternative for base load electricity generation in Brazil; to reduce generation risks during dry seasons, and to facilitate the operation of the whole power generation system. The share of nuclear power may reach values between 8 % and 15 % by 2040 according to different scenarios. To meet such growth and facilitate new investments, it is necessary to change the legal framework of the sector, and allow private ownership of enterprises to build and operate nuclear power plants in the country. (author)

  3. Multipurpose nuclear process heat for energy supply in Brazil

    International Nuclear Information System (INIS)

    Hansen, U.; Inden, P.; Oesterwind, D.; Hukai, R.Y.; Pessine, R.T.; Pieroni, R.R.; Visoni, E.

    1978-11-01

    The industrialized nations require 75% of the energy as heat and it is likely that developing countries in the course of industrialization will show a comparable energy consumption structure. The High Temperature Reactor (HTR) allows the utilization of nuclear energy at high temperatures as process heat. In the Federal Republic of Germany (FRG) the development in the relevant technical areas is well advanced and warrants investigation as a matter for transfer to Brazil. In Brazil nuclear process heat finds possible applications in steel making, shale oil extraction, petroleum refining, and in the more distant future coal gasification with distribution networks. Based on growth forecasts for these industries a theoretical potential market of 38-53 GW (th) can be identified. At present nuclear process heat is marginally more expensive than conventional fossil technologies but the anticipated development is expected to add an economic incentive to the emerging necessity of providing a sound energy base in the developing countries. (author)

  4. The monopoly of the nuclear activities in Brazil

    International Nuclear Information System (INIS)

    Santanna, Luciano Portal

    2009-01-01

    The difficulty in dealing with some technical and legal concepts related to use of radioactivity and nuclear energy, combined with a confusing law silent and many respects outdated, doubts arise and often, misconceptions about scope of the monopoly of the Federal Government on activities with nuclear ores and minerals and derivatives. With an interdisciplinary approach, the aim of this work address key aspects of the legal regime of nuclear activities and facilities in Brazil, distinguishing it from that applicable to the activities and radiative facilities

  5. National report of Brazil. Nuclear Safety Convention

    International Nuclear Information System (INIS)

    1998-09-01

    This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  6. Brazilian nuclear programme - energy in Brazil

    International Nuclear Information System (INIS)

    Lima, J.O.V.

    1988-01-01

    The brazilian energetic model, highly dependent of petroleum, have been changed in the sense to adopt diversified and regionalized solutions. This paper describes the role and the perspective of the nuclear energy in this context. (M.I.)

  7. Nuclear Power Plant (NPP) safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The multidisciplinary aspects of the activities involved in the nuclear power plant (NPP) licensing, are presented. The activities of CNEN's technical staff in the licensing of Angra-1 and Angra-2 power plants are shown. (E.G.) [pt

  8. 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)

  9. Sustainability indicators to nuclear research centers in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Simone F.; Feliciano, Vanusa Maria D.; Barreto, Alberto A., E-mail: symonfonseca@yahoo.com.br, E-mail: vmfj@cdtn.br, E-mail: aab@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The relevance and applicability of sustainability indicators have been discussed in various international and national debates through forums, conferences, seminars and lectures. The information obtained from the use of these indicators is essential to the decision-making process, contributing to the creation of discussion channels and interaction with society; also it is useful for the design and implementation of environmental education programs, perception and risk communication. So far, at least in Brazil, existing indicators for the nuclear area are related only to power generation, as performance and safety in radioactive waste management. According to this reality we see the need to build indicators that contribute to the assessment of environmental, social, cultural, economic and institutional performance of a nuclear innovation and research institute in Brazil. This work aims to highlight, through literature review, the importance of developing sustainability indicators appropriate to nuclear research centers in Brazil, revealing how much they are strategic to measuring the sustainability of these endeavours. The main finding, after the literature review, is that this type of indicator is important not only to identify positive or negative impacts of a project focused on the research and innovation of nuclear area, but also for assessment of his commitment to the sustainable development. (author)

  10. Sustainability indicators to nuclear research centers in Brazil

    International Nuclear Information System (INIS)

    Alves, Simone F.; Feliciano, Vanusa Maria D.; Barreto, Alberto A.

    2015-01-01

    The relevance and applicability of sustainability indicators have been discussed in various international and national debates through forums, conferences, seminars and lectures. The information obtained from the use of these indicators is essential to the decision-making process, contributing to the creation of discussion channels and interaction with society; also it is useful for the design and implementation of environmental education programs, perception and risk communication. So far, at least in Brazil, existing indicators for the nuclear area are related only to power generation, as performance and safety in radioactive waste management. According to this reality we see the need to build indicators that contribute to the assessment of environmental, social, cultural, economic and institutional performance of a nuclear innovation and research institute in Brazil. This work aims to highlight, through literature review, the importance of developing sustainability indicators appropriate to nuclear research centers in Brazil, revealing how much they are strategic to measuring the sustainability of these endeavours. The main finding, after the literature review, is that this type of indicator is important not only to identify positive or negative impacts of a project focused on the research and innovation of nuclear area, but also for assessment of his commitment to the sustainable development. (author)

  11. Obstacles to the nuclear technology development in Brazil: from the beginning of atomic age to the Brazil-Germany Nuclear Agreement

    International Nuclear Information System (INIS)

    Medeiros, Tharsila Reis de

    2005-01-01

    This paper intends to comprehend the Brazilian social actors' efforts applied to the nuclear energy control, from the beginning of Atomic Age to Brazil-Germany Nuclear Agreement. It tries to demonstrate that the limits of The Brazilian nuclear development in this period derive from the capitalist development dynamics in Brazil and from the absence of continuity on the motivations of its nuclear policy. (author)

  12. Nuclear futures for sale: to Brazil from West Germany, 1975

    International Nuclear Information System (INIS)

    Lowrance, W.W.

    1977-01-01

    On June 27, 1975, Brazil and West Germany signed a fifteen-year Agreement of Cooperation in the Peaceful Use of Nuclear Energy. The United States termed the deal ''nuclear madness'' with Brazil in its ''backyard'', and it also observed that it was heavily engaged in Germany's backyard to guard it against such peril. The author reviews these events that marked the crossing of major thresholds both in technology transfer and in international politics. He draws a general description of the political territory in which they are bound to remain prominent landmarks. The agreement provided for the largest industrial nuclear sale ever transacted, its total value exceeding $US 5 billion. More importantly, it was the first time a complete, self-sufficient nuclear fuel cycle ''package sale'' had ever been made between nations. Its most controversial feature was the inclusion of the two ''sensitive technologies'' for enriching uranium and reprocessing spent fuel, both of which, if sufficient effort is expended, can be applied to the making of nuclear-weapons-grade fissile material. The supplier nation is a signatory of the Nuclear Nonproliferation Treaty and has long been a supporting strand in the web of nations committed to retarding the spread of nuclear weapons; the recipient nation, a nuclear newcomer, has refused to sign that treaty and in the past has made few such commitments. Pervading the international debate over these events are issues of the developing nations' rights of access to the political, military, technical, and economic wealth that nuclear technology holds, on the one hand, and on the other, management of the export competition in such a way that the technology can be shared without compromising international stability. Proliferation is inevitable, Mr. Lowrance says, so these issues ''should be accorded much higher political attention.''

  13. Nuclear fuel cycle facilities and RP: the case of Brazil

    International Nuclear Information System (INIS)

    Tranjan Filho, Alfredo; Costa, Cesar Gustavo S.

    2008-01-01

    Full text: The renewed nuclear energy scenario, national and worldwide, calls for the strengthening of all activities involving the nuclear fuel production, from uranium extraction at the mines to fuel assemblies delivery at the nuclear power plants, which in Brazil is the mission of the Industrias Nucleares do Brasil (INB). With only a third of its territory prospected, Brazil currently has the sixth largest uranium reserve in the world. Brazil's three main deposits are: the Caldas mine (in the state of Minas Gerais) the first mineral-industrial complex that processed uranium, developed in 1982, and presently being decommissioned; Caetite mine and processing facility (located in the state of Bahia), nowadays operational and with a current production capacity of 400 tonnes per year of uranium concentrates, being in trend of doubling its annual capacity; and the Itataia/Santa Quiteria deposit (in Ceara State), the largest geological uranium reserve in Brazil, although its feasible future production depends on the exploration of the phosphate associated to it. Concerning the nuclear fuel fabrication, INB plant at Resende (in the state of Rio de Janeiro) is responsible for the conversion of Uf 6 to UO 2 the production of fuel pellets and the assembly of the fuel elements, in order to supply the demands of Brazil's two operating PWR (Angra 1 and Angra 2). In addition, in May 2006, INB-Resende inaugurated the uranium enrichment facility, employing the ultra-centrifugation technology. Today still in its first phase of operation, when completed the enrichment facility is intended to provide 100 percent of the domestic requirements, eventually by the year 2015. Detailing present status and future perspectives of INB, in face of the global and national renaissance of nuclear energy, this paper addresses the Radiation Protection (RP) aspects related to INB's achievements and performance, as well as the pressing future challenges to be dealt with, in order to guarantee

  14. Opportunities and obstacles for new nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Henning, Fernando

    2003-01-01

    The presentation displays the main characteristics of the Brazilian Electric Sector, emphasizing its potential market growth, the role of all relevant alternative sources for generation of electricity, the major constraints, and the possibilities for nuclear to compete in this scenario. Within this framework, it will highlight the features of national industry to cope with this challenge, as seen by the Brazilian Utility. The key issues to overcome are dealt with, in order to establish the boundary conditions for the feasibility of new nuclear plants in Brazil, as well as what is expected from improvements in technology and economics for a new reactor generation (author)

  15. Nuclear Power in South-Central Brazil

    International Nuclear Information System (INIS)

    Cintra do Prado, L.

    1966-01-01

    The region of South-Central Brazil includes the states of Sao Paulo, Rio de Janeiro, Guanabara and Minas Gerais. The most recent power study was made by Canambra Engineering Consultants Limited. This group reported that the public-grid electricity output for the area in 1962 was 2.16 GW (average generation), with an installed capacity of 3.41 GW and annual mean load factor of 63.4; an increase in power requirements for 1970 was forecast, corresponding to an average output of 5.37 GW and an installed capacity of 8.3 GW. This forecast was based on an annual growth rate of 11.9% in generation. ''The energy requirements have grown at an average annual rate of 10.9% since 1955; however, the present forecast is based on the assumption of power being available as required, and hence includes the suppressed demand resulting from existing restrictions in generating and distribution capacity''

  16. Public perception of the nuclear area in Brazil

    International Nuclear Information System (INIS)

    Almeida, Renata Araujo de; Moreira, Maria de Lourdes

    2013-01-01

    Nowadays human dependence on electricity is increasing and as a result access to energy resources and / or energy, is becoming a priority in most countries, both developed and developing. With this comes the need for government involvement in the planning and expansion of energy activities, especially when dealing with nuclear energy. This study makes a detailed assessment of the availability of energy and its capacity, the geographical location of current and future nuclear plants, economic criteria, the deployment period and public opinion concerning the construction of new nuclear plants. The aim of the study is not only to show the advantages of the expansion of nuclear energy in Brazil but also to evaluate public opinion on this issue. (author)

  17. Obstacles to the nuclear technology development in Brazil: from the beginning of atomic age to the Brazil-Germany Nuclear Agreement; Entraves ao desenvolvimento da tecnologia nuclear no Brasil: dos primordios da era atomica ao Acordo Nuclear Brasil-Alemanha

    Energy Technology Data Exchange (ETDEWEB)

    Medeiros, Tharsila Reis de

    2005-07-01

    This paper intends to comprehend the Brazilian social actors' efforts applied to the nuclear energy control, from the beginning of Atomic Age to Brazil-Germany Nuclear Agreement. It tries to demonstrate that the limits of The Brazilian nuclear development in this period derive from the capitalist development dynamics in Brazil and from the absence of continuity on the motivations of its nuclear policy. (author)

  18. Obstacles to the nuclear technology development in Brazil: from the beginning of atomic age to the Brazil-Germany Nuclear Agreement; Entraves ao desenvolvimento da tecnologia nuclear no Brasil: dos primordios da era atomica ao Acordo Nuclear Brasil-Alemanha

    Energy Technology Data Exchange (ETDEWEB)

    Medeiros, Tharsila Reis de

    2005-07-01

    This paper intends to comprehend the Brazilian social actors' efforts applied to the nuclear energy control, from the beginning of Atomic Age to Brazil-Germany Nuclear Agreement. It tries to demonstrate that the limits of The Brazilian nuclear development in this period derive from the capitalist development dynamics in Brazil and from the absence of continuity on the motivations of its nuclear policy. (author)

  19. Public perception of the nuclear area in Brazil

    International Nuclear Information System (INIS)

    Imeida, R.A. de; Lourdes Moreira, M. de

    2013-01-01

    In Brazil electricity production is proving increasingly important, the Brazilian government has recently launched the National Energy Plan, PNE-2030 which aims, among other objectives, to conclude construction of the Angra 3 plant and to deploy new nuclear power plants in the Northeast region. The Brazilian government wants to assess how the public has perceived its energy policy and what the public thinks about the nuclear issue. A public opinion survey was performed and sampling resulted in 127 respondents who were stratified by gender, age and educational level. The survey results show that although most respondents have post-graduate degrees, 64.6% are not aware of, or had never heard of PNE-2030. While 72 respondents consider nuclear energy as an alternative source of clean energy, 84 respondents did not know where the next Brazilian nuclear power plant will be built. The nuclear regulator, CNEN, is seen by 45.7% of respondents as the body that has most credibility to talk about the safety of nuclear power plants and the media most used to obtain information about the nuclear area were newspapers and discussion forums, with 52 and 50 votes respectively. These results prove the need to implement communication plans with clear and concise goals for different segments of society, since the degree of understanding differs within each segment

  20. THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL

    International Nuclear Information System (INIS)

    Almeida, C.

    2004-01-01

    A turning point of the world nuclear industry with respect to safety occurred due to the accident at Chernobyl, in 1986. A side from the tragic personal losses and the enormous financial damage, the Chernobyl accident has literally demonstrated that ''a nuclear accident anywhere is an accident everywhere''. The impact was felt immediately by the nuclear industry, with plant cancellations (e.g. Austria), elimination of national programs (e.g. Italy) and general construction delays. However, the reaction of the nuclear industry was equally immediate, which led to the proposal and establishment of a Global Nuclear Safety Regime. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. In a previous work, the author has presented in detail the components of this Regime, and briefly discussed its impact in the Brazilian nuclear power organizations, including the Regulatory Body. This work, on the opposite, briefly reviews the Global Nuclear Safety Regime, and concentrates in detail in the discussion of its impact in Brazil, showing how it has produced some changes, and where the peer pressure regime has failed to produce real results

  1. Establishment of a Nuclear Cooperation Network between Korea and Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyoung Pyo; Sohn, Dong Seong; Song, Kee Chan (and others)

    2008-03-15

    The objective of this study is to establish a personnel network and to identify potential complementary areas for technical cooperation in the future to advance Korean-Brazilian nuclear cooperation activities. To this end, current status of the cooperation in the areas of economy, energy resources and S and T between the two countries was surveyed, and the history of the nuclear development program and the current nuclear R and D status in Brazil, as well as the bilateral nuclear cooperation activities of both countries were analyzed. In addition, areas of mutual interest were identified by both countries' focal points and a personnel network was established. Based on the aforementioned preliminary activities, bilateral joint seminars were held in Brazil. At the joint seminars, possible areas of cooperation were discussed and joint research collaboration areas were surveyed and identified while both sides made efforts to expand the information and experts exchanges in specific areas. Through this study, possible specific areas of cooperation in which both sides have a common interest were identified in such areas as radiation technology application, post irradiation examination, radioactive waste management, I and C, and advanced nuclear fuel, and also concrete implementation methods were proposed. These results will be effectively utilized in establishing a basic direction for expanding bilateral nuclear cooperation activities in the future. Consistent establishment of a foundation for promoting cooperation could be established and maintained through the operation of a focal point in charge of coordinating bilateral technical cooperation, and then a long-term and stable human network could be established.

  2. Establishment of a Nuclear Cooperation Network between Korea and Brazil

    International Nuclear Information System (INIS)

    Kim, Kyoung Pyo; Sohn, Dong Seong; Song, Kee Chan

    2008-03-01

    The objective of this study is to establish a personnel network and to identify potential complementary areas for technical cooperation in the future to advance Korean-Brazilian nuclear cooperation activities. To this end, current status of the cooperation in the areas of economy, energy resources and S and T between the two countries was surveyed, and the history of the nuclear development program and the current nuclear R and D status in Brazil, as well as the bilateral nuclear cooperation activities of both countries were analyzed. In addition, areas of mutual interest were identified by both countries' focal points and a personnel network was established. Based on the aforementioned preliminary activities, bilateral joint seminars were held in Brazil. At the joint seminars, possible areas of cooperation were discussed and joint research collaboration areas were surveyed and identified while both sides made efforts to expand the information and experts exchanges in specific areas. Through this study, possible specific areas of cooperation in which both sides have a common interest were identified in such areas as radiation technology application, post irradiation examination, radioactive waste management, I and C, and advanced nuclear fuel, and also concrete implementation methods were proposed. These results will be effectively utilized in establishing a basic direction for expanding bilateral nuclear cooperation activities in the future. Consistent establishment of a foundation for promoting cooperation could be established and maintained through the operation of a focal point in charge of coordinating bilateral technical cooperation, and then a long-term and stable human network could be established

  3. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z., E-mail: jonatasfmata@yahoo.com.br, E-mail: vasconv@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  4. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    International Nuclear Information System (INIS)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z.

    2015-01-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  5. On the future of nuclear power in Brazil

    International Nuclear Information System (INIS)

    Lameiras, Fernando Soares

    2002-01-01

    The recent optimism related to the resumption of nuclear energy for the generation of electricity in Brazil has been based on investments by the actual government to finish Angra II, the expansion of INB's facilities, the electricity supply crisis, and, on the external plan, the announcement of the Energy Plan of the George W. Bush government. However, for this resumption to take hold, it is necessary that the nuclear enterprises decrease their dependence on State resources and enter the nuclear power international market. With these measures, it was sought to demonstrate that the interest of the private capital could appear, making feasible the construction of new nuclear power plants. In fact, the major hurdle to the increase of the use of nuclear power is in the economic area. The State does not have resources available to afford the investments necessary to build new nuclear power plants. In contrast, the private sector prefers other alternatives which require less investment and afford faster capital return rates. (author)

  6. Sixth national report of Brazil for the nuclear safety convention

    International Nuclear Information System (INIS)

    2013-01-01

    Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  7. Sixth national report of Brazil for the nuclear safety convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations.

  8. Nuclear power plants: recent developments in Brazil relating to the legal aspect of installation - erection - operation

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1981-10-01

    A Federal statutory system governs the setting up and operation of nuclear power plants in Brazil. This paper describes the general regulatory framework for electric utilities and in particular analyses the licensing procedure for nuclear installations. (NEA) [fr

  9. Replacing nuclear staff: The proactive work at IPEN/CNEN-SP-Brazil

    International Nuclear Information System (INIS)

    Pupak, M.O.; Rogero, J.R.

    2005-01-01

    The purpose of this paper was to bring out the actual situation of Nuclear Education and Training in Brazil. Accordingly, this paper overviews the situation of educational matters in Latin America, especially in Brazil, in terms of efficiency and effectiveness of its superior education system. Mainly, this paper points out the replacing of nuclear staff and the proactive work of the Energy and Nuclear Research Institute (IPEN) of the Brazilian Nuclear Energy Commission (CNEN). (author)

  10. The monopoly of the nuclear activities in Brazil; O monopolio das atividades nucleares no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Santanna, Luciano Portal

    2009-07-01

    The difficulty in dealing with some technical and legal concepts related to use of radioactivity and nuclear energy, combined with a confusing law silent and many respects outdated, doubts arise and often, misconceptions about scope of the monopoly of the Federal Government on activities with nuclear ores and minerals and derivatives. With an interdisciplinary approach, the aim of this work address key aspects of the legal regime of nuclear activities and facilities in Brazil, distinguishing it from that applicable to the activities and radiative facilities.

  11. Brazil-Argentina bilateral cooperation - Protocol 11. Nuclear safety and radiation protection. Visit of CNEA engineers to Brazil

    International Nuclear Information System (INIS)

    Gasparian, A.E.

    1991-01-01

    The activities carried out by Techniques of Argentine Organization (CNEA) during visitation to Angra dos Reis (Brazil) are related. Licensing procedures for nuclear installations (reactors), and transport, licensing of personnels for nuclear installations, quality assurance and regulatory inspections were discussed. (M.C.K.)

  12. Fast pyrolysis of biomass in fluidized bed reactor UNICAMP, Brazil: problems, causes and solutions; Pirolise rapida de biomassa em reator de leito fluidizado UNICAMP-Brasil: problemas, causas e solucoes

    Energy Technology Data Exchange (ETDEWEB)

    Mesa Perez, Juan Miguel; Marin Mesa, Henry Ramon [Bioware Tecnologia, Campinas, SP (Brazil); Rocha, Jose Dilcio; Olivares Gomez, Edgardo [Universidade Estadual de Campinas (NIPE/UNICAMP), SP (Brazil). Nucleo Interdisciplinar de Planejamento Energetico; Cortez, Luis Augusto Barbosa; Shimabukuro, Fabio Rodrigo; Vallin, Marco Jim Gui [Universidade Estadual de Campinas (FEAGRI/UNICAMP), SP (Brazil). Fac. de Engenharia Agricola

    2006-07-01

    The fluidized bed reactor developed by the researchers of the UNICAMP in the installations of the Sugar Cane Technology Center (CTC), in Piracicaba-SP, is the first reactor of biomass fast pyrolysis in Brazil to produce bio-oil. In this work the problems of operation with the reactor in functioning are presented as the emptying of gases produced in the pyrolysis by means of the biomass feeding system, the block of the thread of biomass feeding, the inert material sintering in the bed, etc. The possible causes are described. Thus it, the first ones could be solved, either by the reduction of the height of the inert bed, or by the increase of the wadding percentage of the thread, among others. These results of the exploratory tests make possible the steady work of the plant, greater knowledge of the phenomena that occur during the fast pyrolysis in flutizide bed, as well as the establishment of adjusted levels for the identified independent factors during the remaining experimental works. (author)

  13. The use of genetic algorithms with niching methods in nuclear reactor related problems; A utilizacao dos metodos de nichos dos algoritmos geneticos na otimizacao de problemas de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sacco, Wagner Figueiredo

    2000-03-01

    Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to test existing niching techniques and two methods introduced herein, bearing in mind their eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. Tests are performed using widely known test functions and their results show that the new methods are quite promising, specially in real world problems like the nuclear reactor core reload. (author)

  14. Cuckoo Search with flight of Levy applied to the problem of reload of fuels in nuclear reactors; Busca Cuco com voo de Levy aplicado ao problema de recarga de combustiveis em reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Patrick V.; Nast, Fernando N.; Schirru, Roberto; Meneses, Anderson A.M., E-mail: patrickvs@hotmail.com, E-mail: fernandonnast@gmail.com, E-mail: anderson.meneses@pq.cnpq.br, E-mail: schirru@lmp.ufrj.br [Universidade Federal do Oeste do Para (UFOPA), Santarem, PA (Brazil). Instituto de Engenharia e Geociencias. Programa de Ciencia e Tecnologia; Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ) RJ (Brazil). Programa de Engenharia Nuclear

    2017-11-01

    Intra-Nuclear Fuel Management Optimization is a complex combinatorial problem of the NP-difficult type, associated with the refueling process of a nuclear reactor, which aims to extend the cycle of operation by determining loading patterns, obeying safety margins. In addition to the combinatorial problem, we have the aspect of calculations of reactor physics, which increases the difficult of OGCIN. Methods that are proving effective when applied to OGCIN are the algorithms belonging to the swarm intelligence paradigm. A new member of this paradigm is Cuckoo Search (CS), which has shown results promising when applied to optimization issues. The CS is based on the litter parasitism of some cuckoo species combined with the Levy flight behavior of some birds. In the present work we present the results of the application of CS to OGCIN, and compare them to the results obtained by the application of ABC.

  15. Validation of main nuclear libraries used in thorium reactors using the Serpent code; Validação das principais bibliotecas nucleares utilizadas em reatores de tório com o código Serpent

    Energy Technology Data Exchange (ETDEWEB)

    Faga, Lucas J., E-mail: lucas.faga@usp.br [Universidade de São Paulo (USP), SP (Brazil). Instituto de Física; Stefani, Giovanni L. de, E-mail: giovanni.stefani@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil). Centro de Engenharia Nuclear; Santos, Thiago A. dos, E-mail: thiago.santos@ufabc.edu.br [Universidade Federal do ABC (UFABC), São Paulo, SP (Brazil)

    2017-07-01

    The purpose of this work is to validate the library of the Serpent standard database for systems containing U-233, U-235, Th-232, Pu-239 and Pu-240. The project will support the other projects of the newly created study group of Nuclear Engineering Center (CEN) of Instituto de Pesquisas Energéticas e Nucleares (IPEN), linked to the study of several types of reactors and their application in thorium cycles, a subject that gains more and more visibility, due to strong and potential promises of energy revolution. The results obtained at the end of the simulations were satisfactory, with the multiplication factors being effective close to 100 PCM of the values provided by the benchmarks, as expected for a validated library. The minimum distance between these values was 2 PCM and the maximum of 280 PCM. The final analysis demonstrates that the ENDF / B-VII library has validated nuclear data for the isotopes of interest and may be used in future thorium study group projects.

  16. Nuclear policy retrospection in Brazil and forecasting for using of small nuclear power plants - SNPs - in the Brazilian electric system

    International Nuclear Information System (INIS)

    Santos, E.M. dos.

    1992-02-01

    This thesis highlights the nuclear energy perspectives to regain a prominent place in the world energy mix, as a competitive and safe energy source. Just considering the current international changes in the nuclear power features in the developed countries, it is assessed the suitability and feasibility of defining a new nuclear policy in Brazil, based on the development of small and medium nuclear power reactors - SMNPR. The SMNPR's may be a good nuclear strategy for Brazil to develop a national and evolutionary reactor design with several improvements in safety, by means of passive safety systems. This reactor may play a significant role in the brazilian electrical system in the long term. (author)

  17. Particle Swarm Optimization applied to combinatorial problem aiming the fuel recharge problem solution in a nuclear reactor; Particle swarm optimization aplicado ao problema combinatorio com vistas a solucao do problema de recarga em um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Meneses, Anderson Alvarenga de Moura; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear]. E-mail: ameneses@con.ufrj.br; schirru@lmp.ufrj.br

    2005-07-01

    This work focuses on the usage the Artificial Intelligence technique Particle Swarm Optimization (PSO) to optimize the fuel recharge at a nuclear reactor. This is a combinatorial problem, in which the search of the best feasible solution is done by minimizing a specific objective function. However, in this first moment it is possible to compare the fuel recharge problem with the Traveling Salesman Problem (TSP), since both of them are combinatorial, with one advantage: the evaluation of the TSP objective function is much more simple. Thus, the proposed methods have been applied to two TSPs: Oliver 30 and Rykel 48. In 1995, KENNEDY and EBERHART presented the PSO technique to optimize non-linear continued functions. Recently some PSO models for discrete search spaces have been developed for combinatorial optimization. Although all of them having different formulation from the ones presented here. In this paper, we use the PSO theory associated with to the Random Keys (RK)model, used in some optimizations with Genetic Algorithms. The Particle Swarm Optimization with Random Keys (PSORK) results from this association, which combines PSO and RK. The adaptations and changings in the PSO aim to allow the usage of the PSO at the nuclear fuel recharge. This work shows the PSORK being applied to the proposed combinatorial problem and the obtained results. (author)

  18. The licensing of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    In Brazil the governmental organization responsible for the licensing of NPPs is the Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body. A description of CNEN's organization, responsabilities and working methods, as well as the present situation of the Brazilian NPPs undergoing licensing, has recently been presented. In this paper the experience gained by CNEN in the course of licensing Brazilian NPPs Units I and II is discussed. CNEN's present day technical competence and its future trends are analysed with regard to in-house capacity, foreign consultants and research contracts with Brazilian Universities. Finally, the immediate need for a Safety research programm in support of licensing is discussed. Manpower needs and major areas for such a programm are also indicated. (orig./RW)

  19. Procedures, activities and doses in nuclear medicine cycle in Brazil

    International Nuclear Information System (INIS)

    Oliveira, Silvia Maria Velasques de

    2005-01-01

    With the aim of characterizing nuclear medicine procedures performed in Brazil, activities of radiopharmaceuticals used and effective doses to patients, data was collected from nuclear medicine institutions in three regions of the country, namely the Southeast, the Northeast and the South regions, representing public hospitals, university hospitals, private and philanthropic institutions with low, medium and high levels of consumption of radiopharmaceuticals. The three chosen regions are responsible for 92% of radiopharmaceutical consumption and imaging equipment in the country. Accordingly, it was requested of some participating institutions to fulfill manually from individual patients data, to record gender, age, weight, height and activities used, for each type of exam as well as the equipment used. In others, the researcher collected data personally. Per institution, nuclear medicine diagnostic procedures ranged from 700 to 13,000 per year, most of which are myocardial and bone imaging procedures, and imaging equipment ranged, from 1 to 8 machines, one or two head SPECT's (hybrid or not). 26.782 patients protocols were analysed, 24.371 adults and 2.411 children and teenagers. For adult patients, differences were observed in the amount of activities used in diagnostic procedures between public and private institutions, with lower average activities used in public institutions. Activities administered to children and their effective doses were difficult to evaluate due to the incompleteness of individual records. Appropriate individual patient records could be adopted without affecting hospitals routine and contributing for a comprehensive evaluation of the radiation protection of nuclear medicine patients. Data from 8.881 workers were analysed, 346 working at nuclear medicine institutions. For monitored workers and measurably exposed workers in nuclear medicine, the values 2.3 mSv and 5.4 mSv, respectively, for effective annual doses are greater than data

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

    Energy Technology Data Exchange (ETDEWEB)

    Bonfietti, Gerson

    2003-07-01

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

  1. Applied to neuro-fuzzy models for signal validation in Angra 1 nuclear power plant; Modelos de validacao de sinal utilizando tecnicas de inteligencia artificial aplicados a um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Mauro Vitor de

    1999-06-15

    This work develops two models of signal validation in which the analytical redundancy of the monitored signals from an industrial plant is made by neural networks. In one model the analytical redundancy is made by only one neural network while in the other it is done by several neural networks, each one working in a specific part of the entire operation region of the plant. Four cluster techniques were tested to separate the entire region of operation in several specific regions. An additional information of systems' reliability is supplied by a fuzzy inference system. The models were implemented in C language and tested with signals acquired from Angra I nuclear power plant, from its start to 100% of power. (author)

  2. 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)

  3. 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

  4. Qualification and application of nuclear reactor accident analysis code with the capability of internal assessment of uncertainty; Qualificacao e aplicacao de codigo de acidentes de reatores nucleares com capacidade interna de avaliacao de incerteza

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Ronaldo Celem

    2001-10-15

    This thesis presents an independent qualification of the CIAU code ('Code with the capability of - Internal Assessment of Uncertainty') which is part of the internal uncertainty evaluation process with a thermal hydraulic system code on a realistic basis. This is done by combining the uncertainty methodology UMAE ('Uncertainty Methodology based on Accuracy Extrapolation') with the RELAP5/Mod3.2 code. This allows associating uncertainty band estimates with the results obtained by the realistic calculation of the code, meeting licensing requirements of safety analysis. The independent qualification is supported by simulations with RELAP5/Mod3.2 related to accident condition tests of LOBI experimental facility and to an event which has occurred in Angra 1 nuclear power plant, by comparison with measured results and by establishing uncertainty bands on safety parameter calculated time trends. These bands have indeed enveloped the measured trends. Results from this independent qualification of CIAU have allowed to ascertain the adequate application of a systematic realistic code procedure to analyse accidents with uncertainties incorporated in the results, although there is an evident need of extending the uncertainty data base. It has been verified that use of the code with this internal assessment of uncertainty is feasible in the design and license stages of a NPP. (author)

  5. Incidents in nuclear research reactor examined by deterministic probability and probabilistic safety analysis; Incidentes em reatores nucleares de pesquisa examinados por analise de probabilidade deterministica e analise probabilistica de seguranca

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Valdir Maciel

    2010-07-01

    This study aims to evaluate the potential risks submitted by the incidents in nuclear research reactors. For its development, two databases of the International Atomic Energy Agency, IAEA, were used, the Incident Report System for Research Reactor and Research Reactor Data Base. For this type of assessment was used the Probabilistic Safety Analysis (PSA), within a confidence level of 90% and the Deterministic Probability Analysis (DPA). To obtain the results of calculations of probabilities for PSA, were used the theory and equations in the paper IAEA TECDOC - 636. The development of the calculations of probabilities for PSA was used the program Scilab version 5.1.1, free access, executable on Windows and Linux platforms. A specific program to get the results of probability was developed within the main program Scilab 5.1.1., for two distributions Fischer and Chi-square, both with the confidence level of 90%. Using the Sordi equations and Origin 6.0 program, were obtained the maximum admissible doses related to satisfy the risk limits established by the International Commission on Radiological Protection, ICRP, and were also obtained these maximum doses graphically (figure 1) resulting from the calculations of probabilities x maximum admissible doses. It was found that the reliability of the results of probability is related to the operational experience (reactor x year and fractions) and that the larger it is, greater the confidence in the outcome. Finally, a suggested list of future work to complement this paper was gathered. (author)

  6. 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.

  7. 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.

  8. The importance of nuclear energy for the expansion of Brazil's electricity grid

    International Nuclear Information System (INIS)

    Santos, Ricardo Luis Pereira dos; Rosa, Luiz Pinguelli; Arouca, Maurício Cardoso; Ribeiro, Alan Emanuel Duailibe

    2013-01-01

    This article analyzes the thermal energy options available in the country to support the expansion of Brazil's electricity grid capacity. The country's electricity mix consists primarily of renewable sources of energy and this configuration will be maintained throughout the 21st century. However, grid expansion can no longer benefit from hydroelectric power plants with large reservoirs leading to a greater participation of thermal power plants. Among the thermal sources available in the country, nuclear power has important comparative advantages. Recognizing these benefits, the Brazilian government has established that expanding electricity grid capacity will amount to up to 8000 MW through nuclear energy by 2030. The use of nuclear technology for electricity generation has historically been a controversial issue worldwide and some countries have decided to review their nuclear programs in the aftermath of the 2011 Fukushima nuclear accident. This article shows that increasing the participation of nuclear energy in Brazil's electricity grid will provide important benefits for the country by ensuring energy security, keeping Brazil's electricity mix as one of the cleanest in the world, securing electricity grid reliability and safety and reducing operating costs. - Highlights: • The expansion of the power capacity is essential to support the economic growth. • The increase through hydropower cannot benefit from storage reservoirs. • It will be necessary to increase the capacity thermal power. • Nuclear power has significant comparative advantages in Brazil. • Brazil has institutional base, uranium reserves and nuclear technology

  9. Second national report of Brazil for the nuclear safety convention - September 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-01

    This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

  10. Second national report of Brazil for the nuclear safety convention - September 2001

    International Nuclear Information System (INIS)

    2001-09-01

    This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil

  11. Proceedings of the 13. Workshop on Nuclear Physics in Brazil

    International Nuclear Information System (INIS)

    1990-01-01

    Theoretical and experimental studies on nuclear structure, nuclear matter, scattering, nuclear reactions, radioactive decay, nuclear properties and nuclear models are presented. Studies on radiation protection, radiation detectors, spectroscopy and elementary particles area also presented. (M.C.K.)

  12. Sea pollution by nuclear reactors. Poluicao marinha pelos reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Tommasi, L A [Companhia de Tecnologia de Saneamento Ambiental, Sao Paulo, SP (Brazil)

    1981-01-01

    The capacity of radionuclides accumulation by organisms of a estuary is described he gives examples about what happen with the St. Jacques shell, in Ems estuary, in Columbia river and others. The talks about the biological effects, the radionuclides behaviour in environment of estuary, the thermal effects and finishes with some considerable notices. (C.M.).

  13. Nuclear proliferation and Latin American security : is the "Bomb" program dead in Brazil?

    OpenAIRE

    DeJesus, Eduardo De Jesus

    1994-01-01

    This thesis addresses the possibility of a Brazilian "hidden agenda" in order to support one of the most advanced nuclear research and nuclear power programs in Latin America. From the early 1970s to the late 1980s Brazilian military leaders pursued the development of nuclear weapons. With the emergence of democratic regimes during the 1980s, these covert projects were halted or terminated. The civilian administration in Brazil is now supporting an ambiguous and uncompromising position by ...

  14. The nuclear inspections in Brazil and a french public urinal

    International Nuclear Information System (INIS)

    Silva, Othon L.P. da

    2004-01-01

    The article approaches the political aspects concerning to the nuclear energy, specifically the commercial contracts with Germany for acquisition of nuclear power plants and the entire nuclear fuel cycle, and the considerations of the IAEA

  15. The possibility of clean development mechanism in a nuclear power expansion in Brazil

    International Nuclear Information System (INIS)

    Paris, Alexandre G.; Oliveira, Wagner S.

    2009-01-01

    The nuclear power expansion is a very controversial topic in Brazil, which needs to be carefully addressed, especially because the national energy supply system is becoming more carbon-intensive. Although most of the electricity generated in Brazil is by hydropower plants, the country's electricity matrix expansion is moving towards a larger participation of fossil fuel thermo power generation which is contrarily the global objects of climate change mitigation. Climate change is a reality and the choice facing this problem is between action and delay. There will be needed a huge international mobilization, associated with a great amount of financial, political and engineering resources interested for preventing the aggravation of the greenhouse effect. This article analyses, in the possibility of including nuclear power in the Clean Development Mechanism (CDM) criteria, the revenue that could be generated from the trading of Certified Emission Reduction (CER) in different scenarios of nuclear power expansion in Brazil. (author)

  16. 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)

  17. The potential of nuclear energy to generate clean electric power in Brazil

    International Nuclear Information System (INIS)

    Stecher, Luiza C.; Sabundjian, Gaiane; Menzel, Francine; Giarola, Rodrigo S.; Coelho, Talita S.

    2013-01-01

    The generation of electricity in Brazil is concentrated in hydroelectric generation, renewable and clean source, but that does not satisfy all the demand and leads to necessity of a supplementary thermal sources portion. Considering the predictions of increase in demand for electricity in the next years, it becomes necessary to insert new sources to complement the production taking into account both the volume being produced and the needs of environmental preservation. Thus, nuclear power can be considered a potential supplementary source for electricity generation in Brazil as well as the country has large reserves of fissile material, the generation emits no greenhouse gases, the country has technological mastery of the fuel cycle and it enables the production of large volumes of clean energy. The objective of this study is to demonstrate the potential of nuclear energy in electricity production in Brazil cleanly and safely, ensuring the supplies necessary to maintain the country's economic growth and the increased demand sustainable. For this, will be made an analysis of economic and social indicators of the characteristics of our energy matrix and the availability of our sources, as well as a description of the nuclear source and arguments that justify a higher share of nuclear energy in the matrix of the country. Then, after these analysis, will notice that the generation of electricity from nuclear source has all the conditions to supplement safely and clean supply of electricity in Brazil. (author)

  18. State regulation of nuclear sector: comparative study of Argentina and Brazil models

    International Nuclear Information System (INIS)

    Monteiro Filho, Joselio Silveira

    2004-08-01

    This research presents a comparative assessment of the regulation models of the nuclear sector in Argentina - under the responsibility of the Autoridad Regulatoria Nuclear (ARN), and Brazil - under the responsibility of Comissao Nacional de Energia Nuclear (CNEN), trying to identify which model is more adequate aiming the safe use of nuclear energy. Due to the methodology adopted, the theoretical framework resulted in criteria of analysis that corresponds to the characteristics of the Brazilian regulatory agencies created for other economic sector during the State reform staring in the middle of the nineties. Later, these criteria of analysis were used as comparison patterns between the regulation models of the nuclear sectors of Argentina and Brazil. The comparative assessment showed that the regulatory structure of the nuclear sector in Argentina seems to be more adequate, concerning the safe use of nuclear energy, than the model adopted in Brazil by CNEN, because its incorporates the criteria of functional, institutional and financial independence, competence definitions, technical excellence and transparency, indispensable to the development of its functions with autonomy, ethics, exemption and agility. (author)

  19. 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)

  20. Basic information to improve public acceptance to nuclear energy in Brazil

    International Nuclear Information System (INIS)

    Gibelli, Sonia M.O.; Lima e Silva, Pedro Paulo de; Xavier, Ana Maria

    1997-01-01

    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)

  1. Proceedings of the 10. Workshop on Nuclear Physics in Brazil

    International Nuclear Information System (INIS)

    1987-01-01

    Theoretical and experimental studies on Nuclear Physics are presented. Nuclei structures, nuclear reaction cross sections, collision phenomena between particles at several energy ranges and radiation effects on solids and liquids are analysed. (M.C.K.) [pt

  2. National report of Brazil on nuclear safety convention - introduction

    International Nuclear Information System (INIS)

    1998-01-01

    This document was prepared for fulfilling the Brazilian obligations under the Convention on Nuclear Safety. Chapter 1 presents some historical aspects of the Brazilian nuclear policy, targets to be attained for increasing the nuclear energy contribution for the national production of electric energy

  3. Evolution of the physical protection and control of nuclear materials in Brazil

    International Nuclear Information System (INIS)

    Paschoa, A.S.; Renha, G.; Mafra, O.Y.

    2005-01-01

    Full text: Brazil started protecting its nuclear materials soon after the end of the World War II, when the Combined Development Trust intended to control the world supply of uranium and thorium. This happened in 1944, but on December 27, 1946, an amendment to the report of Committee II of the United Nations established that the international ownership of the unexplored uranium and thorium would not be mandatory. Brazil nationalized its thorium and uranium reserves in 1951. The Brazil-Germany agreement signed in 1975 enhanced the need for Brazilian nuclear safeguards and security. The physical protection (PP) and control of nuclear materials (CNM) became activities under the supervision of the Brazilian military forces. The System for Protection of the Brazilian Nuclear Program (SIPRON), established on 7 October 1980, took over the responsibilities for PP and other aspects of the Brazilian nuclear program. The central organ of SIPRON was the Brazilian National Security Council (CSN). The Brazilian Nuclear Energy Commission (CNEN) was in charge of coordinating, among others, the PP sector. Earlier that year - on 3 March 1980 - the Convention on the Physical Protection of Nuclear Material (CPPNM) was signed simultaneously in New York and Vienna. The Brazilian congress approved the CPPNM on 27 November 1984, and the Brazilian government deposited the ratification letter on 17 October 1985. On 16 April 1991 the Brazilian government issued a decree to enforce the CPPNM in the Brazilian territory. CNEN published the regulatory documents NE - 2.01 on 19 April 1996, and NN - 2.02 on 21 September 1999 for PP, and CNM, respectively. CNEN has the ultimate responsibility to enforce these regulations. The operational aspects of PP and CNM in Brazil are still improving. Potential nuclear terrorism for example needs to be examined. Activities concerning training personnel and implementing PP and CNM will be described in the paper. (author)

  4. Energy-development correlation and the nuclear strategy in Brazil. Part 2

    International Nuclear Information System (INIS)

    Amarante, J.A.A. do

    1981-01-01

    Special attention is called for the extremely high nuclear energy potencial available in Brazil, which is equivalent to the energy that could be generated by all our huge hidroeletric potencial under continuous operation for more then 9 thousands years. (Author) [pt

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

    International Nuclear Information System (INIS)

    Anon.

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

  6. Technical and institutional safety features of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.)

  7. Scientific and technical production of IPEN - Nuclear and Energetic Research Institute, SP, Brazil. 1997-1999

    International Nuclear Information System (INIS)

    2001-01-01

    This document reports the general activities results of technical and scientific research production of the Institute for Energetic and Nuclear Researches, IPEN, Brazil, during the year of 1997-1999, listing journal articles, scientific events (complete texts, communications, abstracts and panels), thesis and dissertations, books, technical and scientific reports

  8. Annual report - ABACC (accounting and nuclear materials control Brazil-Argentina agency) - 1998

    International Nuclear Information System (INIS)

    1999-01-01

    The annual activities report of 1998 of accounting and nuclear materials control Brazil-Argentina agency introduces the next main topics: institutional activities - safeguards agreements implementation and administration; technical activities - planning and evaluation, operation, technical support, information accounting and treatment, technical cooperation, technical capacity invigoration; administrative and financial activities

  9. Modelling and simulation the radioactive source-term of fission products in PWR type reactors; Modelagem e simulacao do termo-fonte radioativo de produtos de fissao em reatores nucleares do tipo PWR

    Energy Technology Data Exchange (ETDEWEB)

    Porfirio, Rogilson Nazare da Silva

    1996-07-01

    The source-term was defined with the purpose the quantify all radioactive nuclides released the nuclear reactor in the case of accidents. Nowadays the source-term is limited to the coolant of the primary circuit of reactors and may be measured or modelled with computer coders such as the TFP developed in this work. The calculational process is based on the linear chain techniques used in the CINDER-2 code. The TFP code considers forms of fission products release from the fuel pellet: Recoil, Knockout and Migration. The release from the gap to the coolant fluid is determined from the ratio between activity measured in the coolant and calculated activity in the gap. Considered the operational data of SURRY-1 reactor, the TFP code was run to obtain the source=term of this reactor. From the measured activities it was verified the reliability level of the model and the employed computational logic. The accuracy of the calculated quantities were compared to the measured data was considered satisfactory. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Mesquita, Amir Zacarias

    2005-07-01

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

  11. General view about reactor safety nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Gasparian, A.E.; Silva, D.E.; Salvatore, J.E.L.; Lima, J.M. de

    1991-01-01

    In this paper the authors describe the principles and goals that have guided, as well as the methods that have been used by the National Commission of Nuclear Energy (CNEN) to set forth measures aiming at providing safety to the Brazilian nuclear power plants. The status of the licensing process of these power plants is shown. The performance and the results obtained so far in relation to the nuclear safety are also described. (author)

  12. Evolution of nuclear security regulatory activities 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 changing of the world scenario in the last 15 years has increased worldwide the concerns about overall security and, as a consequence, about the nuclear and radioactive material as well as their associated facilities. Considering the new situation, in February 2004, the Brazilian National Nuclear Energy Commission (CNEN), decided to create the Nuclear Security Office. This Office is under the Coordination of Nuclear Safeguards and Security, in the Directorate for Safety, Security and Safeguards (Regulatory Directorate). Before that, security regulation issues were dealt in a decentralized manner, within that Directorate, by different licensing groups in specific areas (power reactors, fuel cycle facilities, radioactive facilities, transport of nuclear material, etc.). This decision was made in order to allow a coordinated approach on the subject, to strengthen the regulation in nuclear/radioactive security, and to provide support to management in the definition of institutional security policies. The CNEN Security Office develops its work based in the CNEN Physical Protection Regulation for Nuclear Operational Units - NE-2.01, 1996, the Convention on the Physical Protection of Nuclear Material and the IAEA Nuclear Security Series . This paper aims at presenting the activities developed and the achievements obtained by this new CNEN office, as well as identifying the issues and directions for future efforts. (author)

  13. Evolutionary computing in Nuclear Engineering Institute/CNEN-Brazil

    International Nuclear Information System (INIS)

    Pereira, Claudio M.N.A.; Lapa, Celso M.F.; Lapa, Nelbia da Silva; Mol, Antonio C.

    2000-01-01

    This paper aims to discuss the importance of evolutionary computation (CE) for nuclear engineering and the development of this area in the Instituto de Engenharia Nuclear (IEN) at the last years. Are describe, briefly, the applications realized in this institute by the technical group of CE. For example: nuclear reactor core design optimization, preventive maintenance scheduling optimizing and nuclear reactor transient identifications. It is also shown a novel computational tool to implementation of genetic algorithm that was development in this institute and applied in those works. Some results were presents and the gains obtained with the evolutionary computation were discussing. (author)

  14. On Brazil's participation in the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO)

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho

    2007-01-01

    In response to a resolution of its 44th General Conference (GC(44)/RES/21) held in September 2000, the International Atomic Energy Agency launched in May 2001 the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO) with the objective of supporting the safe, sustainable, economic and proliferation-resistant use of nuclear technology to meet the global energy needs of the 21st century. Brazil joined the project from its beginnings and in 2005 submitted a proposal for the screening assessment using INPRO methodology of two small-size light-water reactors as potential components of an innovative nuclear reactor system (INS) completed with a conventional open nuclear fuel cycle. The INS reactor components currently being assessed are the International Reactor Innovative and Secure (IRIS) that is being developed by an international consortium made of 21 organizations from 10 countries (Brazil included) led by the Westinghouse Company, and the Fixed Bed Nuclear Reactor (FBNR) that is being developed at the Federal University of Rio Grande do Sul. This paper gives an overview of Brazil's participation in INPRO, highlighting the objective, scope and intermediate results of the assessment study being performed, and the possibilities for participation in one or two collaborative research projects under INPRO Phase 2 Action Plan for 2008-2009. (author)

  15. On the implementation of activities for the life management of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Di Lorenzo, R.F.; Mansur, T.R.; Moreira, R.M.; Quinan, M.A.; Rocha, Z.; Soares, W.A.; Tofani, P.C.

    1998-01-01

    Brazil joined the IAEA IWG-LMNPP in 1993, in view of a potential interest in the LMNPP subject. In this report, aspects of nuclear activities, as well as activities related to LMNPP, are reviewed. The nuclear energy scenario is presented with emphasis on the nuclear share of the total electrical energy supply and on the nuclear sector organization. Angra Nuclear Power Plant units are presented and some construction and/or operational features are discussed. Concerning the activities on LMNPP, the contribution of different nuclear sector organizations is briefly considered. Some aspects are stressed with regard to an integrated approach of LMNPP and the country's available manpower and technical infrastructure capabilities in the nuclear field. The technical assistance of the IAEA in the area of plant life management if focused. From the experience of this first phase (1993-97) representing Brazil in the IWG-LMNPP, special aspects are emphasized aiming, on the basis of their consideration, at improving the efficiency of this process. The implementation of a Brazilian network, the BRWG-LMNPP, is underway, formulating plans for the future. (author)

  16. Improvements in the nuclear accident response system in Brazil

    International Nuclear Information System (INIS)

    Estrada, J.J.S.; Azevedo, E.M.; Knofel, T.M.J.; Recio, J.C.A.; Alves, R.N.

    1998-01-01

    The National Commission on Nuclear Energy has been making outstanding effort to improve its nuclear and radiological accident response systems since the tragic accident in Goiania. Most of this effort is related to nuclear area although the radiological accident has been also considered. This paper describes the improvements in the CNEN response system structure, discusses several topics involving those related to emergency planning and preparedness, and points out some deficiencies that need to be corrected also. The situation during the Goiania accident was more disadvantageous than nowadays, so it is believed that none of the actual deficiencies are sufficient to guess that the population and the environment will not be protected in case of a nuclear or radiological accident

  17. Agreement between the Republic of Argentina and the Federative Republic of Brazil for the exclusively peaceful use of nuclear energy

    International Nuclear Information System (INIS)

    1991-01-01

    The document reproduces the text of the Agreement between the Republic of Argentina and the Federative Republic of Brazil for the Exclusively Peaceful Use of Nuclear Energy, signed by the Ministers for Foreign Affairs of Argentina and Brazil in Guadalajara, Mexico, on 18 July 1991

  18. Reactors licensing: proposal of an integrated quality and environment regulatory structure for nuclear research reactors in Brazil

    International Nuclear Information System (INIS)

    Serra, Reynaldo Cavalcanti

    2014-01-01

    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)

  19. INPRO economic assessment of the IRIS nuclear reactor for deployment in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves Filho, Orlando Joao Agostinho, E-mail: orlando@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN - RJ), Rua Helio de Almeida, 75, Cidade Universitaria, Ilha do Fundao, 21941-906 Rio de Janeiro, RJ (Brazil)

    2011-06-15

    Highlights: > First INPRO evaluation of IRIS economic competitiveness for deployment in Brazil. > Plant arrangement of three independent IRIS single units constructed in series. > Angra 3 reactor used as reference design for judgment of IRIS economic potential. > IRIS economically competes with 2nd generation nuclear power plants in Brazil - Abstract: This paper presents the results of the economic assessment of the International Reactor Innovative and Secure (IRIS) for deployment in Brazil using the assessment methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO initiated in 2001 and has the main objective of helping to ensure that nuclear energy will be available to contribute in a sustainable manner to the energy needs of the 21st century. Among its missions is the development of a methodology to assess innovative nuclear energy systems (INSs) on a global, regional and national basis. In 2005, Brazil submitted a proposal for the assessment of two small-size reactors as components of an INS, completed with a conventional open nuclear fuel cycle based on enriched uranium. One of the reactors assessed was IRIS, a small-size, modular, integral-type PWR reactor. IRIS was evaluated with regard to the areas of reactor safety and economics only. This paper outlines the rationale for the study and summarizes the results of the economic assessment. The study concluded that the reference design of IRIS complies with most of INPRO economics criteria and has potential to comply with the remaining ones.

  20. Education in nuclear science at IPEN - CNEN, Sao Paulo, Brazil. Advanced School of Nuclear Energy-EAEN

    International Nuclear Information System (INIS)

    Semmler, R.; Catharino, M.G.M.; Vasconcellos, M.B.A.

    2012-01-01

    EAEN (Advanced School of Nuclear Energy, 2010) is an annual school that consists of a week of activities in the area of Nuclear Physics, Radiochemistry and uses of Nuclear Energy for a public made of high school students. The EAEN project represents a pioneering program on science education and dissemination of knowledge, conducted by researchers and focused mainly on high school and scientific education for the population in general. The school's priority is to explore the failures and the lack of education in the dissemination of nuclear energy for high school students as well as to attract prospective students with great potential for graduate courses of IPEN and other institutions in Sao Paulo and in Brazil. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Matuoka, Paula Fernanda Toledo

    2016-07-01

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

  2. A new scenery for nuclear energy at Brazil

    International Nuclear Information System (INIS)

    Vieira, Wilson J.; Menezes, Artur; Claro, Luiz H.; Urbina, Ligia M. Soto

    1999-01-01

    In a not so distant future, nuclear energy will substitute other forms of electric energy generation. In this work it is shown that recent factors around the world, that is, globalization, the need for technological innovation, quality programs, and the need to stop devastation of the planet by human activity is promoting a change in attitude of the population in respect to nuclear energy. A new public opinion is rising in a world which comes to the end of the millennium in the middle of a scientific and technological revolution, as important as the 1500 s discoveries or the French revolution. These facts reveal a historical moment to boost nuclear energy development. The reasons for this assumption are: the rise in scientific and technological activities promoted by the competition between countries to gain positions in production an exportation of goods and services with aggregate technology; the public acceptation of nuclear energy which is now considered as the most proper option to stop the environment damage caused by fossil fuels; the generalization of nuclear applications. These reasons prove the need of the human being to know and utilize the most complex phenomena of Nature to proceed in the road of its own evolution. (author)

  3. Discussions and projections about the future demand for nuclear power in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Fabio Branco Vaz de, E-mail: fabio@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Nuclear and Engineering Center; Imakuma, Kengo, E-mail: kimakuma@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Information Technology Development Dept.

    2011-07-01

    This paper aims mainly to discuss the current scenarios of power consumption, nuclear power and conventional and uranium resources and, based on that, present projections about the future demand for power generated through atomic fissions in Brazil, showing that there may be differences in estimates of future projections, depending on the indexes considered: global or domestic. The time horizon for the analysis was studied up to the maximum for the national population, for some of the world and Brazil's governmental data in terms of population growth, energy consumption and energy consumption per capita. To introduce the importance of the methodology adopted, data and some problems presented about the current world energy and Brazilian scenarios are discussed. Calculations show that the power consumption projections for Brazil, when using global indexes, are very high. According to our methodology, power consumption in Brazil is nearly 4.5 times below the estimates presented by the global indexes. The conclusion is that applying global indexes and their extension to domestic scenarios lead to errors of orders of magnitudes, due to the specific particularities of each country, and must be avoided if accurate projections about energy and nuclear scenarios must be considered. (author)

  4. Discussions and projections about the future demand for nuclear power in Brazil

    International Nuclear Information System (INIS)

    Oliveira, Fabio Branco Vaz de; Imakuma, Kengo

    2011-01-01

    This paper aims mainly to discuss the current scenarios of power consumption, nuclear power and conventional and uranium resources and, based on that, present projections about the future demand for power generated through atomic fissions in Brazil, showing that there may be differences in estimates of future projections, depending on the indexes considered: global or domestic. The time horizon for the analysis was studied up to the maximum for the national population, for some of the world and Brazil's governmental data in terms of population growth, energy consumption and energy consumption per capita. To introduce the importance of the methodology adopted, data and some problems presented about the current world energy and Brazilian scenarios are discussed. Calculations show that the power consumption projections for Brazil, when using global indexes, are very high. According to our methodology, power consumption in Brazil is nearly 4.5 times below the estimates presented by the global indexes. The conclusion is that applying global indexes and their extension to domestic scenarios lead to errors of orders of magnitudes, due to the specific particularities of each country, and must be avoided if accurate projections about energy and nuclear scenarios must be considered. (author)

  5. Nuclear power renaissance in Brazil - the need for a positive agenda

    International Nuclear Information System (INIS)

    Villar, Heldio P.

    2007-01-01

    After having promised electricity 'too cheap to meter' and being hailed as a viable alternative to the oil shocks of the 1970s, nuclear power is having one more chance - and most probably the last. Prices are competitive, environmentalists now favour it and concerns over global warming are fast overcoming nuclear power's risks, though the vast majority of the population has no clear idea of which they are. Yet, most countries are reluctant to embrace this technology, even those rich in uranium. Brazil, a uranium-rich, energy-hungry country, is still debating if it is not more appropriate to build power plants that use imported gas or - which is probably worse - Brazilian coal. This paper deals with the current situation, taking Brazil as a model. lt is then suggested that the nuclear sector changes its attitude, thus establishing for itself a positive agenda. Instead of stressing safety as its most important feature, the sector must sell nuclear technology as clean, innovative and affordable. Proposals include a good use of the media and, most of all, the introduction of nuclear topics in schools. This will ensure that nuclear power can have a prominent role in bridging the gap between present and future energy sources. (author)

  6. Fifth national report of Brazil for the nuclear safety convention

    International Nuclear Information System (INIS)

    2010-01-01

    This Fifth National Report is a new update to include relevant information for the period of 2007/2009. This document represents the national report prepared as a fulfillment of the Brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  7. Keeping ports accessible: Brazil is saving “millions” in dredging costs thanks to nuclear techniques

    International Nuclear Information System (INIS)

    Quevenco, Rodolfo

    2015-01-01

    With a coastline of over 8500 kilometres, 90 per cent of Brazil’s total exports and imports pass through its ports. Many of the country’s major ports and harbours were built over 100 years ago. Keeping shipping lanes open and enabling these ports to accommodate larger vessels with ever bigger loads requires constant dredging, often at high cost. Over the years, the use of nuclear techniques to study sediment build-up and transport across major ports and harbours (see box) has saved Brazil millions of dollars in dredging costs, said Jefferson Vianna Bandeira, a senior researcher in the Environment Department of the National Nuclear Energy Commission of Brazil. With IAEA assistance, Bandeira and a team of scientists have been using radiotracers to map sediment movements that affect Brazil’s major ports since the 1960s.

  8. The role of nuclear emulsions in the institutionalization of research in experimental physics in Brazil

    International Nuclear Information System (INIS)

    Vieira, Cassio Leite; Videira, Antonio A.P.

    2011-01-01

    In this paper, we describe and analyze the introduction and the use of the nuclear emulsions technique in Brazil. Even though consistent researches in cosmic ray physics had been done since the forties of the last century in this country, physicists here only began using this technique after Cesar Lattes' works in Bristol (England) and Berkeley (US). Despite being the implantation of the technique in this country posterior to the origin of the method itself dated from late 1900s, Brazilian scientists were quickly familiarized with it and adopted it not only in cosmic rays, but also in particle physics and nuclear physics, employing it until recently. In our work, we will be concerned with the reasons of this longevity. In other words, why were the nuclear emulsions technique employed for so many years in Brazil, even after its vanishing in physics researches centers in the world? We advance here that the answer to this question involves the institutionalization of science in Brazil mainly physics and economical, social, and geographic reasons. (author)

  9. The Significance of 2010 Iran-Turkey-Brazil Nuclear Deal for Turkey and Brazil

    Science.gov (United States)

    2014-12-01

    Bosnia and Serbia- Montenegro issues. It opened 12 new embassies in Turkic states and other countries and granted many scholarships to the students from...U.S. Atoms for Peace, according to which the United States committed to establish a nuclear research reactor and power plants in Iran.236 Iran

  10. Nuclear development in Chile: A comparative analysis with Argentina and Brazil 1964-2008

    International Nuclear Information System (INIS)

    Cubillos Meza, Adela

    2009-01-01

    The nuclear era in international relations began with the explosion of the atomic bombs over Hiroshima and Nagasaki on August 6th and 9th in 1945, signaling the end of World War II. At that time the United States was the only country with nuclear power and that exclusivity meant, at least for a few years, that it would become the superpower of the Cold War. This situation continued until the Soviet Union detonated its first nuclear device in 1949. The nuclear race between the two Cold War super powers began, and was later joined by Great Britain, France and China. These five big nuclear powers are the same ones with veto rights in the United Nations Security Council. With the creation of the International Atomic Energy Agency (IAEA) in 1957, under United Nations auspices, the use of nuclear energy for peaceful purposes was institutionalized. Many countries received technological support from the powers, beginning nuclear programs for peaceful aims, among them Spain, Finland, Germany, Japan, Argentina and Brazil. The developing countries also started nuclear programs with the incentive that the development of this energy meant progress in science and technology, as well as giving them prestige and power in the international system. While at first, the countries that initiated nuclear energy development programs did so in order to apply it to medicine, industry, and nutrition and to generate electricity, they also built reactors for research and for power. Later, several countries produced nuclear weapons initiating a race for power and containment, keys to the architecture of the Cold War. Meanwhile, some developing countries also started nuclear programs, receiving technical assistance from the super powers, and obeying a nuclear non- proliferation regime but their development was limited, and they were unable to develop nuclear programs that would allow them enough scientific- technological progress to head down the road to development. One of these countries was

  11. Implantation of tomography qualities in Centro Regional de Ciencias Nucleares do Nordeste, Brazil

    International Nuclear Information System (INIS)

    Diniz, Osana F.; Silveira, Renata R.; Melo, Roberto T.; Oliveira, Marcia L.

    2016-01-01

    The quality guarantee of the service offered by a ionizing radiation metrology laboratory is deeply connected to the conformity to the radiation beams implanted to the determination and definition present in the international standards and adopted by the Brazilian National Commission of Nuclear Energy – CNEN. The objective of this work was the implementation of computerized tomography qualities, RQT 8, 9 e 10, in accordance with the IEC-61267 standard in the Metrology Laboratory of the Northeast Regional Center of Nuclear Sciences (CRCN-NE), PE, Brazil. (author)

  12. The Choice of Sites for the First Nuclear Power Plants in Brazil

    International Nuclear Information System (INIS)

    Cintra do Prado, L.

    1966-01-01

    In selecting the sites for nuclear power plants a decision has to be taken as to (1) which area of the country is best suited for the purpose - e.g. the area of Recife, Rio or Sao Paulo, etc. - given the trend in energy requirements and the availability of resources, and (2) where to site the plant or plants within that area. In this paper I shall concentrate on the first of these problems and shall be concerned with assessing the merits and demerits of installing nuclear power plants in certain regions of Brazil which seem particularly well suited for the purpose

  13. The role of nuclear energy in the generation of electricity in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1981-01-01

    A comparative calculation of the potential of conventional electricity-generating energy sources-hydroelectric, coal, nuclear - according to different cost levels of generated energy is presented. Assuming a plausible estimate of the demand increase for electricity in the country, calculations show that nuclear energy will have an important role in Brazil only in the second decade of the next century. The potential of some other alternative electricity generating sources is calculated - shale and biomass (bagasse and biogas of vinhoto are discussed) - indicating that by that time nuclear energy will indeed be an option, but not necessarily the only one or the best. Finally a chronological table has been worked out indicating a construction schedule for the reactors in case the option is for nuclear energy - keeping in mind that this option does not depend exclusively on technical and economic but also political criteria and therefore requires a democratic decision-making process. (Author) [pt

  14. Conflict between constitutional norms: monopoly of nuclear ore and the social function of property in Brazil

    International Nuclear Information System (INIS)

    Costa-de-Moura, Jorge

    2014-01-01

    This monograph broaches about the conflict existing between the social Constitution of 1988, in relation to what is disposed in the Article 5, XXIII and XXIV, entrenchment clause of immediate application that determines the social function of property in Brazil, and articles 21, XXIII, and 177, V, that stipulate the monopoly of ores containing nuclear elements, i.e., those containing the chemical elements uranium, thorium, and plutonium in economically exploitable amounts. Initially, the work deals with legal definitions for nuclear ore, nuclear policy of some countries, the economical concepts of the social function of property and the negative aspects related to the maintenance of the nuclear ore in the state monopole regime in confrontation with the economic and social interest also expressed in the Constitutional Valance of 1988. Finally, it is presented an actualized compilation of nuclear laws related to the Brazilian nuclear policy and a glossary of terms used in the nuclear policy conducted by the Brazilian Nuclear Regulatory Agency (CNEN). (author)

  15. The social and economic impact of nuclear energy in Brazil

    International Nuclear Information System (INIS)

    Marques, E.

    1976-01-01

    A model for structural analysis is introduced and discussed. An application is made to the 'Brazilian Nuclear System' defined by a structural matrix lying upon 42 factors (of which 11 are political 7 economic, 9 technological, 6 sociological, 7 ecological and 2 psychdogical, whose interactions are evalueted. The hierarchical ordering of these 42 factors shows the preponderance of the political ones, the technological factors being the least important. The study is completed by calculating the impact of a PWR pant construction in Brazilian territory, using an enlarged input-output method the sectorial impacts are determined for industrial production, value added, inderect imports and capital goods industries [pt

  16. The law governing the nuclear licensing procedure in Brazil and in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Andrade Da Costa Lima, W.

    1984-01-01

    The two first parts of this thesis separately describe the framework of the legal system of the two countries in the field of nuclear energy, whereas the third part goes into details which are explained in order to prepare the subsequent comparative analysis. The comparison covers the structural set-up of the bodies of the national atomic energy provisions, the structure of the various nuclear licensing procedures, the role and competences of experts and their opinions, and the role and competence of jurisdiction. The most profound difference is found in the fact that Brazilian administrative law does not include jurisdiction of an administrative court, and this for constitutional reasons. The civil courts only have competence to examine acts of administration with regard to their legality. The procedure for licensing nuclear installations or equipment is determined by the central licensing authority within the framework of its competency. So far, there have been no attempts in Brazil to seek judicial remedy or to start an action to set aside decisions taken in the nuclear licensing procedure. Furthermore, there are no means in Brazilian law to stop licensing whenever the requirements of Art. 7, section 1, no. I-IV of Lei 6189 are met. The licensing authority has no scope of discretion. Applicants for a licence in Brazil will have no problems in finding out which regulations are applicable to their particular case. The concrete definition of details, however, always is a time-consuming and expensive process. (orig./HSCH) [de

  17. ABACC - Brazil-Argentina Agency for Accounting and Control of Nuclear Materials, a model of integration and transparence

    International Nuclear Information System (INIS)

    Oliveira, Antonio A.; Do Canto, Odilon Marcusso

    2013-01-01

    Argentina and Brazil began its activities in the nuclear area about the same time, in the 50 century past. The existence of an international nuclear nonproliferation treaty-TNP-seen by Brazil and Argentina as discriminatory and prejudicial to the interests of the countries without nuclear weapons, led to the need for a common system of control of nuclear material between the two countries to somehow provide assurances to the international community of the exclusively peaceful purpose of its nuclear programs. The creation of a common system, assured the establishment of uniform procedures to implement safeguards in Argentina and Brazil, so the same requirements and safeguards procedures took effect in both countries, and the operators of nuclear facilities began to follow the same rules of control of nuclear materials and subjected to the same type of verification and control. On July 18, 1991, the Bilateral Agreement for the Exclusively Peaceful Use of Nuclear Energy created a binational body, the Argentina-Brazil Agency for Accounting and Control of Nuclear Materials-ABACC-to implement the so-called Common System of Accounting and Control of Nuclear materials - SCCC. The deal provided, permanently, a clear commitment to use exclusively for peaceful purposes all material and nuclear facilities under the jurisdiction or control of the two countries. The Quadripartite Agreement, signed in December of that year, between the two countries, ABACC and IAEA completed the legal framework for the implementation of comprehensive safeguards system. The 'model ABACC' now represents a paradigmatic framework in the long process of economic, political, technological and cultural integration of the two countries. Argentina and Brazil were able to establish a guarantee system that is unique in the world today and that consolidated and matured over more than twenty years, has earned the respect of the international community

  18. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-09-15

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  19. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    International Nuclear Information System (INIS)

    2007-09-01

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  20. From rivals to partners; nuclear cooperation process between Argentina and Brazil

    International Nuclear Information System (INIS)

    Carasales, J.C.

    1997-01-01

    The process of rapprochement and integration with Brazil is probably the most important event of the Argentine foreign policy in the last quarter of the 20th. century. In the framework of this broad undertaking, the gradual development of a new relationship in the nuclear field has showed special and unprecedented characteristic which have aroused the international interest. This publication relates the origin and the evolution of the growing nuclear cooperation process between the two countries which until then had been rivals. The sensitive matter involved makes unexpected the speed and the success of the transition from an attempt to generate confidence and transparency in the nuclear programs of both countries to a whole complex of mandatory legal instruments and to the creation of an agency of mutual safeguard that has no precedent [es

  1. Evaluation of the nuclear and radiological emergency response system in Brazil; Visao critica do sistema de atendimento a emergencia radiologica e nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Estrada, Julio J.S.; Azevedo, Eduardo M.; Knoefel, Tom M.J. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Brazilian Nuclear Energy Commission (CNEN) has made outstanding efforts to improve its nuclear and radiological accident response system since the tragic accident in Goiania, Brazil. Most of these efforts are related to nuclear emergency although radiological accidents are also considered. Several topics are discussed involving those related to planning and preparedness. Some deficiencies that need to be corrected or improved are pointed out 8 refs.

  2. The experience of CDTN/CNEN, Centro de Desenvolvimento da Tecnologia Nuclear: A medium size nuclear research centre in Brazil

    International Nuclear Information System (INIS)

    Sobrinho, P.

    2001-01-01

    At first a university research centre, then a captive research centre of the state owned company in charge of establishing a nuclear industry in Brazil, then a research centre of CNEN (the Brazilian Nuclear Energy Authority), nearing its 50 th anniversary, CDTN has a rich experience. even keeping the project portfolio around a number of traditional nuclear energy areas such as nuclear reactors, materials, environment, process engineering, waste management, radiological protection, the institution experienced an evolution in the substance of the proposed projects. This evolution represents the different institutional insertions, but the major changes occurred at a time when, due to a lesser demand from the nuclear sector and other factors, the explicit idea of producing outputs for the benefit of society received a large acceptance from the employees. The challenges to the institution at this time are commented upon. Retirements, coupled to the lack of job openings, work together for the decrease in the staff number, one major challenge. Up to a certain point, private companies have been hired to fill some of the organisational needs, but it is felt that a limit to this policy is being reached. It is argued that, even in the absence of a strong demand from the energy generation sector, a number of opportunities are still available to a NRC in a developing country. Maturity of nuclear energy and applications of radiation tend to transfer the focus of the activities from the fundamentals of nuclear science and technology to quality related issues, a requirement of the modern times. quality systems cannot substitute for the in depth knowledge of the fundamentals. (author)

  3. Release of alpha emitters into the environment by Nuclear Industries of Brazil in Resende, RJ

    International Nuclear Information System (INIS)

    Pereira, Wagner S.; Kelecom, Alphonse; Santos, Rodney; Santos, Maisa F.M.; Torres, Vinicius R.M.; Rodrigues, Jéssica J.S.; Universidade Veiga de Almeida; Universidade Federal Fluminense

    2017-01-01

    The Nuclear Industries of Brazil operates in the field of nuclear energy and has a monopoly on mining and manufacturing the nuclear fuel element in Brazil. The Nuclear Fuel Factory is also responsible for the reconversion process, the manufacture of the pellets and the assembly of the fuel element. Once there is a possibility of particulate material generation during the reconversion processes and the manufacture of pellets, a method of collective protection of the worker was established, which includes a system of air exhaustion of the factory area, with the capacity to renew the indoor air six times per hour. As a control measure, there is a system of automatic detection of the release of radionuclides in the chimney that monitors and calculates the released values. Through the dose calculation model established by the National Commission for Nuclear Energy the release limit is fixed at 1.2∙ 10"7Bq.y"-"1 of alpha emitters by FCN. The present work aims to evaluate the alpha radionuclides released by FCN, in terms of total release (Bq) and Activity Concentration (AC, mBq∙m"-"3). In 2016 it was released 4.14∙10"6Bq.y"-"1, which means an average of 3.45∙10"5Bq.month"-"1. The largest mean for AC was 4.03 mBq∙m"-"3. The release data was almost an order of magnitude lower than the annual release limit, proving the suitability of the atmospheric effluents to the licensing requirements. The largest magnitudes of the two variables (AC and release) were observed in August while the smallest ones, in January. (author)

  4. Release of alpha emitters into the environment by Nuclear Industries of Brazil in Resende, RJ

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Wagner S.; Kelecom, Alphonse; Santos, Rodney; Santos, Maisa F.M.; Torres, Vinicius R.M.; Rodrigues, Jéssica J.S., E-mail: comap@inb.gov.br, E-mail: pereiraws@gmail.com, E-mail: lararapls@hotmail.com [Indústrias Nucleares do Brasil (COMAP.N/FCN/INB), Resende RJ (Brazil). Fábrica de Combustível Nuclear. Coordenação de Meio Ambiente e Proteção Radiológica Ambiental; Universidade Veiga de Almeida (UVA), Rio de Janeiro, RJ (Brazil); Universidade Federal Fluminense (LARARA-PLS/UFF), Niterói, RJ (Brazil). Laboratório de Radiobiologia e Radiometria

    2017-07-01

    The Nuclear Industries of Brazil operates in the field of nuclear energy and has a monopoly on mining and manufacturing the nuclear fuel element in Brazil. The Nuclear Fuel Factory is also responsible for the reconversion process, the manufacture of the pellets and the assembly of the fuel element. Once there is a possibility of particulate material generation during the reconversion processes and the manufacture of pellets, a method of collective protection of the worker was established, which includes a system of air exhaustion of the factory area, with the capacity to renew the indoor air six times per hour. As a control measure, there is a system of automatic detection of the release of radionuclides in the chimney that monitors and calculates the released values. Through the dose calculation model established by the National Commission for Nuclear Energy the release limit is fixed at 1.2∙ 10{sup 7}Bq.y{sup -1} of alpha emitters by FCN. The present work aims to evaluate the alpha radionuclides released by FCN, in terms of total release (Bq) and Activity Concentration (AC, mBq∙m{sup -3}). In 2016 it was released 4.14∙10{sup 6}Bq.y{sup -1}, which means an average of 3.45∙10{sup 5}Bq.month{sup -1}. The largest mean for AC was 4.03 mBq∙m{sup -3}. The release data was almost an order of magnitude lower than the annual release limit, proving the suitability of the atmospheric effluents to the licensing requirements. The largest magnitudes of the two variables (AC and release) were observed in August while the smallest ones, in January. (author)

  5. Assessment of 222Rn occupational exposure at IPEN nuclear materials storage site, SP, Brazil

    International Nuclear Information System (INIS)

    Caccuri, Lilian Saueia

    2007-01-01

    In this study it was assessed the occupational exposure to 222 Rn at IPEN, SP, Brazil, nuclear materials storage site through the committed effective dose received by workers exposed to this radionuclide. The radiation dose was calculated through the radon concentrations at nuclear materials storage site. Radon concentrations were determined by passive detection method with solid state nuclear detectors (SSNTD). The SSNTD used in this study was the polycarbonate Makrofol E; each detector is a small square plastic of 1 cm 2 , placed into a diffusion chamber type KFK. It was monitored 14 points at nuclear materials storage site and one external point, over a period of 21 months, changing the detectors every three months, from December 2004 to September 2006. The 222 Rn concentrations varied from 196 ± 9 and 2048 ± 81 Bq·m -3 . The committed effective dose due to radon inhalation at IPEN nuclear materials storage site was obtained from radon activity incorporated and dose conversion factor, according to International Commission on Radiological Protection procedures. The effective committed dose received by workers is below 20 mSv·y -1 . This value is suggested as an annual effective dose limit for occupational exposure by ICRP 60. (author)

  6. Sustainability indicators for innovation and research institutes of nuclear area in Brazil

    International Nuclear Information System (INIS)

    Alves, S.F.; Barreto, A.A.; Rodrigues, P.C.H.; Feliciano, V.M.D.

    2016-01-01

    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)

  7. TLD environmental monitoring at the Institute of Nuclear Engineering in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Taam, I.H. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Caixa Postal 68550, 21945-970 Rio de Janeiro, RJ (Brazil); Rosa, L.A.R. da [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Av. Salvador Allende s/n, Caixa Postal 37760, 22780-160 Rio de Janeiro, RJ (Brazil)], E-mail: lrosa@ird.gov.br; Crispim, V.R. [PEN/COPPE-DNC/POLI/CT/UFRJ, Caixa Postal 68509, 21941-972 Rio de Janeiro, RJ (Brazil)

    2008-09-15

    Since 2003 the Institute of Nuclear Engineering in Rio de Janeiro city, Brazil, operates a new cyclotron, RDS-111, to produce {sup 18}F-Fluorodeoxyglucose to be used in nuclear medicine. Additionally, the IEN radioactive waste repository has been enlarged during the past last years, receiving a considerable amount of radioactive materials. Therefore, it became necessary to evaluate a possible increase of the environmental gamma exposure rates at the institute site due to the operation of the new accelerator and the enlargement of the institute waste repository as well. LiF:Mg,Cu,P, TLD-100H, and TL detectors were employed for environmental kerma rate evaluation and the results were compared with previous results obtained before the RDS-111 operation initialisation and the enlargement of IEN waste repository. No significant contribution for the enhancement of environmental gamma kerma rates was detected.

  8. Comparison of three energy types : nuclear, hydroelectric and thermoelectric, in Brazil, up to 2050

    International Nuclear Information System (INIS)

    Mohallem, N.D.S.

    1982-12-01

    To pursue a semi-quantitative analysis of Brazil's electric energy production-consumption problem from now on until the 2050 year, is done. The main energy sources under consideration will be hidroelectric, thermoelectric (coal) and nuclear. It is assumed that the energy consumption will be within a specified minimum and maximum level of growth rate and for the limiting cases, the supply by hidroelectricity will be considered, and further supply from other sources will also be considered in the case which hidroelectric potential becomes exausted. It is intended that the best energy alternatives will be devised from today's reality, such as the almost exausted hidroelectric potential in the southwest region and the building of a growing nuclear program. The analysis will be oriented in the viewpoint of the cost-benefit in the economic, social and ecological areas. (Author) [pt

  9. The PRONUCLEAR role (1976-1986 in the human resource training for the nuclear area in Brazil: science history

    International Nuclear Information System (INIS)

    Schmiedecke, Winston Gomes

    2006-01-01

    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)

  10. Construction of sustainability indicators for Nuclear Area Innovation and Research Institutes in Brazil

    International Nuclear Information System (INIS)

    Alves, Simone Fonseca

    2017-01-01

    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)

  11. e-Gamma: Nuclear Material Accountancy and Control System in Brazil

    International Nuclear Information System (INIS)

    Negri Ferreira, S.; Souza Dunley, L.

    2015-01-01

    The Brazilian Nuclear Energy Commission (CNEN) is the government organization responsible for regulating all nuclear activities in Brazil and for ensuring that international safeguards are implemented according to the international agreements. In 2006 CNEN initiated a project aiming at the development and implementation of a web based system (e-Gamma) for on line nuclear material accountancy and control. In January-2014, after three years of beta testing, e-Gamma finally became the official nuclear material accountancy system in Brazil. e-Gamma is a web system hosted in a dedicated server under a secure environment maintained at CNEN headquarters. Secure access is provided by the use of Digital Client Certificate and internal user pre-authorization for login as well as multiple access profiles each one with specific function menus. The System operation is based on source documents for each inventory change prepared and updated by the MBA operators with the help of specific forms with strong validations. After the document conclusion the System records the inventory change in a general ledger. Monthly the officers of CNEN analyzes the general ledgers of each MBA and generates the applicable reports through the System [Inventory Change Reports (ICR), Physical Inventory List (PIL), and Material Balance Report (MBR)]. The System allows the running of managerial queries and has brought to CNEN much more control and traceability of the inventory changes and significant reduction in typing errors, costs and inspection efforts. Therefore, more efficient accountancy verification procedures at national and international levels are expected, as well as remote accountancy verification previous to an inspection. The proposed paper will describe the e-Gamma System, its main features and the oral presentation will contain a brief demonstration of some functionalities through the use of a local version installed on a notebook. (author)

  12. A study on the public perception in nuclear area in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Renata Araujo de [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear; Moreira, Maria de Lourdes; Guimaraes, Antonio Cesar Ferreira, E-mail: malu@ien.gov.b, E-mail: tony@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Wieland, Patricia, E-mail: pwieland@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioprotecao e Seguranca Nuclear. Div. de Normas

    2011-07-01

    During the course of the last years the need for the increase in the electric energy production in Brazil as well as in the rest of the world, has raised the tone of the debate about the environment impact of such production. As a result of these debates, both the several levels of government and some of the Non-Governmental Organizations (NGO's) have commissioned innumerous opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation of the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil., however due to that year's drought, the competent authorities were faced with the necessity of developing a plan, the Plano Nacional de Energia (PNE2030) aiming, among others objectives, at finalizing the construction of the Angra 3 plant and implementing new nuclear plants in places still to be determined. Allowing for the complexity of the subject, this paper presents a field research conducted from 28th September 2010 to 28th October 2010 assessing the current level of perception of the Brazilian population about the nuclear area, in particular of the residents of three cities of Rio de Janeiro. As a result of this work, we suggest how the competent authorities should proceed to reach in an efficient manner a greater understanding of the population about the proposed subject, through communication campaigns being both informative and educational. (author)

  13. A study on the public perception in nuclear area in Brazil

    International Nuclear Information System (INIS)

    Almeida, Renata Araujo de; Wieland, Patricia

    2011-01-01

    During the course of the last years the need for the increase in the electric energy production in Brazil as well as in the rest of the world, has raised the tone of the debate about the environment impact of such production. As a result of these debates, both the several levels of government and some of the Non-Governmental Organizations (NGO's) have commissioned innumerous opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation of the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil., however due to that year's drought, the competent authorities were faced with the necessity of developing a plan, the Plano Nacional de Energia (PNE2030) aiming, among others objectives, at finalizing the construction of the Angra 3 plant and implementing new nuclear plants in places still to be determined. Allowing for the complexity of the subject, this paper presents a field research conducted from 28th September 2010 to 28th October 2010 assessing the current level of perception of the Brazilian population about the nuclear area, in particular of the residents of three cities of Rio de Janeiro. As a result of this work, we suggest how the competent authorities should proceed to reach in an efficient manner a greater understanding of the population about the proposed subject, through communication campaigns being both informative and educational. (author)

  14. State regulation of nuclear sector: comparative study of Argentina and Brazil models; Regulacao estatal do setor nuclear: estudo comparativo dos modelos da Argentina e do Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro Filho, Joselio Silveira

    2004-08-01

    This research presents a comparative assessment of the regulation models of the nuclear sector in Argentina - under the responsibility of the Autoridad Regulatoria Nuclear (ARN), and Brazil - under the responsibility of Comissao Nacional de Energia Nuclear (CNEN), trying to identify which model is more adequate aiming the safe use of nuclear energy. Due to the methodology adopted, the theoretical framework resulted in criteria of analysis that corresponds to the characteristics of the Brazilian regulatory agencies created for other economic sector during the State reform staring in the middle of the nineties. Later, these criteria of analysis were used as comparison patterns between the regulation models of the nuclear sectors of Argentina and Brazil. The comparative assessment showed that the regulatory structure of the nuclear sector in Argentina seems to be more adequate, concerning the safe use of nuclear energy, than the model adopted in Brazil by CNEN, because its incorporates the criteria of functional, institutional and financial independence, competence definitions, technical excellence and transparency, indispensable to the development of its functions with autonomy, ethics, exemption and agility. (author)

  15. Production of /sup 77/Br for nuclear medicine using the CV-28 cyclotron of Instituto de Engenharia Nuclear (RJ, Brazil)

    Energy Technology Data Exchange (ETDEWEB)

    Bastos, M A.V.; Silva, A.G. da [Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil); Newton, W A [Manchester Univ. (UK)

    1984-06-01

    The reaction /sup 75/As (..cap alpha..,2n)/sup 77/Br with 28 MeV alpha particles is used to obtain /sup 77/Br with the CV-28 cyclotron of Instituto de Engenharia Nuclear (Rio de Janeiro, Brazil). A production method has been developed, using 200 mg of arsenium metal, electroplated on platinum. These targets can withstand 25 ..mu..A beams for several hours, yielding 0.29 mCi/..mu..A h. The /sup 77/Br which is separated by coprecipitation with AgCl, is recovered as NaBr with yields better than 98%. Measures have been taken to obtain a product which is pure, sterile and carrier-free.

  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. SISTEMA COMBINADO DE FLOTAÇÃO POR AR DISSOLVIDO E FILTRAÇÃO ADSORTIVA EM ZEÓLITA PARA TRATAMENTO DE EFLUENTE DE REATOR UASB

    Directory of Open Access Journals (Sweden)

    Bruno Oliveira Freitas

    2016-06-01

    Full Text Available RESUMO: Dentre as soluções existentes para efetuar o tratamento de esgoto, o reator anaeróbio do tipo UASB é largamente utilizado no Brasil, porém esta tecnologia apresenta problemas em atender aos limites estabelecidos pela legislação brasileira para lançamento de efluente em termos de nitrogênio amoniacal, fósforo e matéria orgânica, necessitando de pós-tratamento. Diante do potencial para remoção de matéria orgânica e sólidos suspensos pela flotação e da eficiência que a zeólita apresenta na remoção de amônia, a floto-filtração-adsortiva em zeólita pode ser uma promissora alternativa para tratamento deste efluente. Sendo assim, o presente trabalho visou avaliar a eficiência de um sistema de flotação associado à filtração-adsortiva, utilizando zeólita como meio filtrante, para pós-tratamento de efluente de reator UASB. Para tal, foram realizados ensaios de coagulação/floculação, flotação e filtração-adsortiva com um floteste adaptado com filtros adsorventes, utilizando efluente de reator anaeróbio do tipo UASB. Os resultados obtidos neste estudo atenderam aos padrões estabelecidos pela legislação brasileira para lançamento de efluentes em corpos d’água, alcançando 100 % de remoção de nitrogênio amoniacal, permitindo que esse efluente possa ser aproveitado para reuso. Desse modo, o sistema de flotação com a filtração-adsortiva utilizando zeólita como meio filtrante mostrou-se eficiente na remoção de todos os poluentes avaliados. Esta pesquisa teve como principal contribuição a avaliação de alternativa promissora para pós-tratamento de efluente de reator UASB buscando atender as exigências da legislação brasileira e melhorar da qualidade dos efluentes sanitários. ABSTRACT: Among the existing solutions to sewage treatment, the UASB reactor is widely used in Brazil, but this technology has problem to attend the limits established by Brazilian law for discharging of effluent

  18. New recommendations from the IAEA for medical exposures: impact on nuclear medicine in Brazil

    International Nuclear Information System (INIS)

    Sa, Lidia Vasconcellos de; Kodlulovich, Simone

    2013-01-01

    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)

  19. An evaluation of light water breeder reactor system (LWBR) as an alternative for nuclear power generation in Brazil

    International Nuclear Information System (INIS)

    Sauer, I.L.

    1981-01-01

    The LWBR system as an alternative for nuclear power generation in Brazil, was technically and economically evaluated. The LWBR system has been characterized comparatively with the Pressurized Water Reactors through technological and investment cost analysis and through the analysis of the processes and unit costs of the fuel cycle stages. The characteristics of the LWBR system in comparison to the PWR system, with respect to utilization and cumulative consumption of uranium and thorium resources, fuel cycle processes and associated costs have been determined for possible alternatives of nuclear power participation in the Brazilian hidro-thermal electricity generating system. The analysis concluded that the LWBR system does not represent an attractive alternative for nuclear power generation in Brazil and even has no potential to compete with conventional Pressurized Water Reactors. (Author) [pt

  20. Notes on third party liability for nuclear damage in connection with the construction of the first nuclear power plant in Brazil

    International Nuclear Information System (INIS)

    Simoes, A.C.

    1975-01-01

    Responsibilities for the construction and operation of the first nuclear power plant have been transferred from the National Nuclear Energy Commission to Electrobras, a public undertaking set up for this purpose. In view of such transfer of responsibilities and the implementation of further nuclear power projects, liability for nuclear damage has to be regulated in a way consistent with international conventions. A working group associating representatives of national authorities and public utilities was entrusted with the task of drafting rules for co-ordinating their respective activities in relation to the execution of the first nuclear power project; these rules were issued by Ministerial order in 1970. The working group also prepared a draft law on civil liability for nuclear damage, based on the Vienna Convention. This draft law has reached its final stage and, after promulgation, will enable Brazil to ratify the Vienna Convention. (author)

  1. Measurement of nuclear reaction rates and spectral indices along the radius of fuel pellets from IPEN/MB-01 reactor; Medidas de taxas de reacao nuclear e de indices espectrais ao longo do raio das pastilhas combustiveis do reator IPEN/MB-01

    Energy Technology Data Exchange (ETDEWEB)

    Mura, Luis Felipe Liambos

    2010-07-01

    This work presents the measurements of the nuclear reaction rates along the radial direction of the fuel pellet by irradiation and posterior gamma spectrometry of a thin slice of fuel pellet of UO{sub 2} with 4,3% enrichment. From its irradiation the rate of radioactive capture and fission have been measured as a function of the radius of the pellet disk using a HPGe detector. Lead collimators has been used for this purpose. Simulating the fuel pellet in the pin fuel of the IPEN/MB-01 reactor, a thin UO{sub 2} disk is used. This disk is inserted in the interior of a dismountable fuel rod. This fuel rod is then placed in the central position of the IPEN/MB-01 reactor core and irradiated during 1 hour under a neutron flux of around 9 x 10{sup 8} n/cm{sup 2}s. For gamma spectrometry 10 collimators with different diameters have been used, consequently, the nuclear reactions of radioactive capture that occurs in atoms of {sup 238}U and fissions that occur on both {sup 235}U and {sup 238}U are measured in function of 10 different region (diameter of collimator) of the fuel pellet disk. Corrections in the geometric efficiency due to introduction of collimators on HPGe detection system were estimated using photon transport of MCNP-4C code. Some calculated values of nuclear reaction rate of radioactive capture and fission along of the radial direction of the fuel pellet obtained by Monte Carlo methodology, using the MCNP-4C code, are presented and compared to the experimental data showing very good agreement. Besides nuclear reaction rates, the spectral indices {sup 28{rho}} and {sup 25{delta}} have been obtained at each different radius of the fuel pellet disk. (author)

  2. 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)

  3. 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.

  4. Evaluation of residual activity of solid waste generated in nuclear medicine services of Porto Alegre - Brazil

    International Nuclear Information System (INIS)

    Xavier, Ana M.; Alabarse, Frederico Gil; Magalhaes, Maisa Haiidamus; Guerrero, Jesus Salvador Perez

    2008-01-01

    An experimental programme to estimate, with a better degree of accuracy, the activity that remains adsorbed in flasks and syringes used in Nuclear Medicine Services for the administration of radionuclides to patients submitted to diagnostic or therapy was conducted under the coordination of the Radioactive Waste Division of the Brazilian Nuclear Energy Commission. The adopted recommendation in Brazil to allow an expedite solid waste management in nuclear medicine facilities, up to the present, is to consider that 2% of the initial activity remains adsorbed in the solid waste, which easily allows the calculation of the storage time to achieve regulatory clearance levels by decay. This research evaluates 17 different kinds of radio pharmaceuticals and three radioisotopes: 99m Tc, 67 Ga and 201 Tl. Results obtained by means of a weighting method to estimate the residual mass in flasks show that the ratio of the mass of the liquid that remains in the solid waste to the mass of the empty flask is constant. This suggests that the residual activity depends on the initial activity concentration of radiopharmaceutical contained in each flask, as assumed by the regulatory body. Additionally, results obtained by determining the remaining activity in flasks, shortly after the injection of its radionuclides contents in patients, indicate that an average value for the residual activity of the order of 10% of the initial activity contained in the flasks or syringes can be adopted instead of the previously assumed 2%. It is suggested that the more conservative average value obtained in the present work for the activity that remains in flasks and syringes, that is, 10% of the initial activity, could be adopted to determine the decay storage time before the release of solid waste in the urban conventional land fill disposal system. (author)

  5. Implantation of tomography qualities in Centro Regional de Ciencias Nucleares do Nordeste, Brazil; Implantacao das qualidades de tomografia no Centro Regional de Ciencias Nucleares do Nordeste, CNEN-PE, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Diniz, Osana F.; Silveira, Renata R.; Melo, Roberto T.; Oliveira, Marcia L., E-mail: osana.diniz@hotmail.com [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PB (Brazil)

    2016-07-01

    The quality guarantee of the service offered by a ionizing radiation metrology laboratory is deeply connected to the conformity to the radiation beams implanted to the determination and definition present in the international standards and adopted by the Brazilian National Commission of Nuclear Energy – CNEN. The objective of this work was the implementation of computerized tomography qualities, RQT 8, 9 e 10, in accordance with the IEC-61267 standard in the Metrology Laboratory of the Northeast Regional Center of Nuclear Sciences (CRCN-NE), PE, Brazil. (author)

  6. Assessment of two small-sized innovative nuclear reactors for electricity generation in Brazil using INPRO methodology

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho; Sefidvash, Farhang

    2009-01-01

    This paper presents the main results of the assessment study of two small-sized innovative reactors for electricity generation in Brazil using the methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO was initiated in 2001 and has the main objective of helping to ensure that nuclear energy is available to contribute in a sustainable manner to the energy needs of the 21st century. Brazil joined the INPRO project since its beginning and in 2005 submitted a proposal for the assessment using INPRO methodology of two small-sized reactors (IRIS - International Reactor Innovative and Secure, and FBNR - Fixed Bed Nuclear Reactor) as potential components of an innovative nuclear energy system (INS) completed by a conventional open nuclear fuel cycle based on enriched uranium. The scope of this assessment study was restricted to the reactor component of the INS and to the methodology areas of economics and safety for IRIS, and proliferation resistance and safety for FBNR. The results indicate that both IRIS and FBNR innovative designs comply mostly with the basic principles of the areas assessed and have potential to comply with the remaining ones. (author)

  7. Evaluation of diagnostic procedures in nuclear medicine services of Pernambuco and Alagoas states - Brazil

    International Nuclear Information System (INIS)

    Silva, Ricardo Braz F. da; Hazin, Clovis A.

    2011-01-01

    The medical use of ionizing radiation contributes significantly to population exposure to radiation. This study aimed to evaluate the diagnostic procedures carried out in nuclear medicine (SMN) in Pernambuco and Alagoas in order to gather data to subsidize the proposal of reference levels for nuclear medicine in Brazil. Data were collected of the SMN in Pernambuco and Alagoas in the period of 2005 to 2009, according by UNSCEAR. The study used data from IBGE. The results showed that the total number of examinations in the period 2005 to 2009 was 34.828 in Pernambuco and 27.700 in Alagoas, corresponding to 6.966 and 5.540 average annual examinations in Pernambuco and Alagoas, respectively. The total number of examinations performed in both states in 2009 was twice the number carried out in 2005. Scintigraphy is the cardiovascular examination most performed in both states, followed by bone scintigraphy. Tc-99m is the radionuclide used most often, followed by I-131. The number of tests using Tc-99m in 2009 doubled when compared with the examinations performed in 2005. The results indicate that there has been a significant increase in the number of examinations in MN, and that females outnumber males, as far as the use of this diagnostic resource is concerned. The study of the activities of the radionuclides administered to patients in the states of Pernambuco and Alagoas showed that they are high when compared to the values recommended by the IAEA in its Safety Report Series Document No. 40. (author)

  8. Estimation of metal pollutant loads from Nuclear and Energy Research Institute (Brazil)

    Energy Technology Data Exchange (ETDEWEB)

    Marques, Joyce R.; Monteiro, Lucilena R.; Soares, Sabrina M.V.; Stellato, Thamiris B.; Silva, Tatiane B.S.C.; Silva, Douglas B. da; Faustino, Mainara G.; Pires, Maria A.F.; Cotrim, Marycel E.B., E-mail: joyce.marques@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    According to National Environmental Council's (CONAMA) Resolution 357/05, pollutant load can be defined as the amount of a particular pollutant released in receiving water body; it is commonly expressed in a mass-time ratio. As specified in CONAMA's Resolution 430/11, the responsible for the pollutant source must present the Pollutant Load Declaration to environmental authorities. However, pollutant load knowledge is also important to the water quality maintenance and its environmental rating that must be kept to meet the requirements of the most restrictive use. In the control of metals releases is also important due public health matters, since they can cause harmful environmental contamination and major public health issues. Therefore this work aims to present the estimated metal pollutant load released by Nuclear and Energy Research Institute (IPEN/CNEN - Brazil), between 2013 and 2014. Results of cadmium, lead, copper, chromium, zinc, nickel, manganese, iron, barium, silver, boron and tin in composite samples (weekly) via Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES) and bromide (Br-) released as a tracer, to measure the wastewater flow were used to estimate IPEN's Metal Pollutant load. This study is part of the environmental assessment Program at IPEN, instituted since 2006 to the attendance of the current environmental legislation (CONAMA's Resolution 430/11, Article 19-A of State Decree 8.468/76 and State Decree 15.425/80). (author)

  9. Continuing education in radiation protection in the nuclear fuel cycle: The case of Nuclear Industries of Brazil

    International Nuclear Information System (INIS)

    Souza Pereira, W. de; Kelecom, A.

    2014-01-01

    This paper describes the pedagogical and technical concept that guided training in radiation protection implemented by the Indústrias Nucleares do Brasil (INB; Nuclear Industries of Brazil) to maintain the competence of its technical staff to perform activities with exposure to radiation, the staff responsible for the supervision of this work and as a form of dissemination of knowledge to the staff not involved in the use of ionizing radiation. The groups of workers to be trained are here described, as well as the level of training, the frequency and types of training, the profile of trainers, the training programs, the forms of assessment and recording of training. It also describes the first general training performed in 2004. After this initial training no other general training was realized, and the option was to train small groups of workers, to avoid stopping the production as it occurred when general training was executed. The overall training was conducted in three units: the Uranium Concentration Unit (URA) under production in the city of Caetité, state of Bahia, the Ore Treatment Unit (UTM) undergoing decommissioning at Poços de Caldas, state of Minas Gerais and the Unit of Heavy Minerals (UMP), at Buena, state of Rio de Janeiro. In the initial training at URA 79 workers were trained, distributed in 6 classes (average of 13 students per class); each class had nine hours training and the grades obtained ranged from 7.5 to 10. At UTM, 200 employees were trained distributed in 9 classes (average of 22 students per class); their notes ranged from 8.8 to 10. Finally, at UMP 151 employees were trained, in 5 classes (average of 31 students per class); their grades ranged from 8.6 to 9.0. That year, a total of 180 hours were spent for training 430 employees, with no effective rebuke. Currently employees are trained when they arrive at their Units, and all along the year in small classes, as the general training has been definitely abolished. (author)

  10. Critical evaluation of the external occupational exposure in nuclear medicine services in Brazil

    International Nuclear Information System (INIS)

    Kubo, Ana Luiza Silva Lima

    2016-01-01

    Currently in Brazil (2016), there are 421 Nuclear Medicine Services (NMS). In nuclear medicine, the possibility of occupational internal contamination and external exposure is unavoidable. The chest individual monitoring, to estimate the effective dose, is mandatory, but the extremity monitoring is not always made. The aim of this study was to conduct a survey of data for external exposure of NMS professionals in Brazil from 1987 to 2010, analysing them in terms of trends and comparing them with measurements carried out in this work and in other countries. Although most of the NMS is still located in large urban centres (54% in the Southeast region), there is no state without any NMS. The increasing number of NMS has generated the need for more professionals. In the year 1987, they were 755 workers and, in 2010, 4134, with the following distribution of specialties: 29% of Nuclear Medicine Technicians (NMT), 23% of Nursing professionals, 29% of Physicians and 3% of Physicists. The average annual effective dose reached more than 3.0 mSv in some regions of the country, from 1987 to 2010, but tends to 1.0 mSv in 2010. The highest doses, as expected, are received by NMT and Nursing. The professionals who handle radiopharmaceuticals have their hands much more exposed than the chest. During 2010, only 31% of NMT and 16% of Nursing used extremity dosimeters as compared to chest dosimeters. The data from the measurements indicate that not all individual dosimeters are used properly. Generally, both in the measurements as in national registries, the hand doses were higher for professionals who prepared the radiopharmaceutical (NMT) than those who injected (Nursing). The value measured by chest dosimeters can be used to estimate the equivalent dose to the eye lenses, except for NMT at preparation practices at conventional NMS, where the equivalent dose of the lens is about 2 times higher than the dose at the chest. The most exposed areas of the hands are the tips of the index

  11. Survey of nuclear parameters from the TRIGA Mark I IPR R1 Brazilian reactor with concentric configuration aiming the application of K{sub 0} neutron activation technique; Levantamento de parametros nucleares do reator TRIGA Mark I IPR R1 com configuracao concentrica visando a aplicacao da tecnica de ativacao neutronica K{sub 0}

    Energy Technology Data Exchange (ETDEWEB)

    Franco, Milton Batista

    2006-07-01

    This research intended to determine the nuclear parameters a, f, spectral index and neutron temperature in several irradiations positions of the TRIGA Mark 1 IPR-R1 reactor, for use on the parametric method K{sub 0} in the CDTN. K{sub 0} is a monostandard method of neutron activation analysis. It is, on the whole, experimentally simple, flexible and an important tool for accurate and convenient standardization in instrumental multi-element analysis. At the time the parameters were determined at the rotatory rack, lower layer and in the central thimble: alpha was calculated applying the three bare monitor method using {sup 197}Au, {sup 94}Zr and {sup 96}Zr; f determination was done according to the bare bi-isotopic method; neutron temperature was calculated through the direct method using {sup 176}Lu, {sup 94}Zr, {sup 96}Zr and {sup 197}Au and the Westcott's g(Tn) function for the {sup 176}Lu was calculated and the result was interpolated in the Grintakis and Kim (1975) Table, determining the neutron temperature. The procedure to check the parameters consisted in using standard solutions of Au (metal foil, NBS), Lu (LuO{sub 2}, Johnson Mattey Company - JMC) and Zr (ZrO{sub 2} and metal foil, Johnson Mattey Company 99,99% and Zry - 4: 98,14% of Zr, National Bureau of Standard- NBS). Several certified reference materials and two samples of intercomparisons (samples of sediment of the IAEA/ARCAL XXVI project) have been analysed by means of k{sub 0}- INAA in order to verify the efficiency of the method and the quality of the parameters. The certified reference materials were: GXR-2, GXR-5 and GXR-6 of the United States Geological Survey (USGS) and Soil-5, Soil-7 and SL-1 of the International Atomic Energy Agency (IAEA). (author)

  12. Study of the viability of the production of lutetium - 177 in the nuclear reactor IEA-R1 at IPEN/CNEN-SP; Estudo da viabilidade de producao do lutecio - 177 no reator nuclear IEA-R1 do IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Giovana Pasqualini da

    2008-07-01

    The {sup -} emitter {sup 177} Lu is a promising therapeutic radioisotope for the curative treatment of cancer using labelled proteins. It has a half - life of 6.71 day and maximum and average (3 energies of 421 and 133 keV, respectively, resulting in a short range of irradiation of tissue. The decay is accompanied by the emission of low energy -radiation of 208.3 keV (11%) and 113 keV (6.4%), suitable for simultaneous imaging. Lu can be produced by two different routes, namely, by irradiation of natural Lu{sub 2}O{sub 3} target ({sup 176}Lu, 2.6%) or enriched (in {sup 176}Lu) Lu{sub 2}O{sub 3} target, and also by irradiation of Yb target (Yb{sub 2}O{sub 3}) followed by radiochemical separation of Lu from Yb isotopes. The objective of this work is the development of a method of the production of {sup 177} Lu through of the (n, gamma) nuclear reaction, by the direct and indirect method of production. Targets of lutetium oxide and ytterbium oxide were irradiated for evaluation of the activity produced and the chemical separation of lutetium and ytterbium was studied using different ion exchange resins. For the direct method, the best results were obtained using the target Lu{sub 2}O{sub 3} enriched in 39.6%. The best results for the indirect method were achieved with the process of separation using 0.25M - HlBA as eluent. The results showed that it is possible to produce {sup 177} Lu of low specific activity for labeling molecules used for bone pain relief and in radiosynoviortesy. (author)

  13. Reator anaeróbio compartimentado para o tratamento de águas residuárias de suinocultura

    Directory of Open Access Journals (Sweden)

    Roberto Alves de Oliveira

    2014-12-01

    Full Text Available A poluição da água e do solo causada pela suinocultura provoca impactos ambientais severos nas regiões produtoras. Uma alternativa eficiente para atenuar esse problema pode ser a utilização de reatores anaeróbios de alta taxa. Neste trabalho, avaliou-se o efeito das águas residuárias de suinocultura com concentrações de sólidos suspensos totais em torno de 6.000 mg.L−1 no desempenho do reator anaeróbio compartimentado, com três câmaras. O volume da primeira câmara foi de 210 L e da segunda e terceira de 160 L. O reator anaeróbio compartimentado foi submetido a tempos de detenção hidráulica de 56, 28 e 18 horas e a cargas orgânicas volumétricas de 5,0 a 10,1 g DQOtotal (L.d−1. As maiores remoções de demanda química de oxigênio total, de 42 a 68%, e das produções volumétricas de metano, de 0,261 a 0,454 L CH4 (L reator d−1, ocorreram na segunda câmara.

  14. Modelagem e simulação de um reator trickle-bed para hidrogenação de propeno

    OpenAIRE

    Rodrigo Simion Hunger

    2002-01-01

    Neste trabalho foi modelado um reator catalítico heterogêneo, pressurizado, adiabático e provido de reciclo. O leito deste reator está dividido em duas partes, sendo que a primeira opera como um reator trickle-bed, enquanto a segunda opera como um reator de leito fixo, onde os regentes estão em fase líquida. Um Sistema de Hidrogenação de Propeno em operação no Pólo Petroquímico do Sul foi utilizado para fornecer os dados necessários à validação do modelo proposto. Neste sistema, a reação de h...

  15. Tratamento de efluentes de abatedouro de frangos por meio de reator UASB seguido de filtro anaeróbio

    Directory of Open Access Journals (Sweden)

    L.S. Rodrigues

    2016-02-01

    Full Text Available O Brasil é um dos maiores produtores de aves do mundo e se destaca na exportação de carne de frango, que tem papel relevante na economia do país. Como resultado do crescimento da indústria de processamento do frango, há também um significativo aumento na geração de efluentes. Uma alternativa interessante para o tratamento desses resíduos são os reatores anaeróbios. Este trabalho teve como objetivo avaliar o desempenho do sistema reator UASB-Filtro anaeróbio no tratamento de efluentes de abate de frangos. O estudo foi desenvolvido em um abatedouro avícola, situado na região metropolitana de Belo Horizonte, Minas Gerais. O sistema de tratamento foi composto por peneira estática, caixa de gordura, reator UASB e filtro anaeróbio. A vazão média diária de efluentes do abatedouro foi de 30m³/dia. A carga orgânica aplicada no reator UASB foi de 0,71kg DQO/m³.d. O monitoramento do sistema foi realizado por meio de análises físico-químicas do afluente e dos efluentes da caixa de gordura, reator UASB e filtro anaeróbio. Os parâmetros avaliados foram: temperatura, pH, demanda química de oxigênio (DQO, demanda bioquímica de oxigênio (DBO, sólidos suspensos totais (SST, e sólidos suspensos voláteis (SSV. Os valores efluentes médios encontrados para DBO, DQO e SST foram 106, 290 e 56mg/L, respectivamente. A eficiência de remoção do sistema para DBO variou de 83 a 99%, e para DQO de 50 a 98%. A eficiência de remoção média de SST e SSV foi de 92%. Conclui-se que o sistema reator UASB seguido de filtro anaeróbio apresentou alto desempenho na remoção de sólidos e carga orgânica. Dessa forma, esses reatores tornam-se uma alternativa viável para o tratamento de águas residuárias de frigoríficos, já que oferecem bons resultados de remoção de poluentes.

  16. Utilização de reator de leito fluidizado trifásico aeróbio em sistema de tratamento combinado de águas residuárias

    OpenAIRE

    Campos, Rosane Hein de

    2001-01-01

    Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnológico. Programa de Pós-Graduação em Engenharia Ambiental Neste trabalho, foram desenvolvidos estudos em um sistema de tratamento combinando reator anaeróbio (tanque séptico) com reator aeróbio (leito fluidizado trifásico), tendo como objetivo avaliar o comportamento do reator aeróbio no tratamento de esgoto sanitário e do restaurante universitário (RU), da UFSC. Utilizou-se um reator de leito fluidizado trifásico...

  17. Quality evaluation of radiopharmaceuticals in nuclear medicine services in the states of Alagoas and Sergipe - Brazil

    International Nuclear Information System (INIS)

    Santos, Poliane Angelo de Lucena; Andrade, Wellington Gomes de; Lima, Fernando Roberto de Andrade; Lima, Fabiana Farias de

    2011-01-01

    Radiopharmaceuticals are compounds associated with a radionuclide. They can be considered as vectors that have some specificity for an organ or a physiological or pathophysiological function. Assessing the radiopharmaceutical's quality is essential to obtain adequate images, avoiding repetition of examinations and unnecessary absorbed dose to the patient. Resolution no. 8 (RCD 38) of 06/04/2008 by Agencia Nacional de Vigilancia Sanitaria (ANVISA) states the obligation of performing a minimum of tests in the routines of nuclear medicine services (NMS). The aim of this work was to evaluate the radiochemical purity and pH of radiopharmaceuticals used in NMS in states of Alagoas and Sergipe - Brazil. Radiochemical purity was determined by thin layer chromatography where a paper Whatman and TLC were used as steady state and the solvents were used related to the appropriate radiopharmaceutical, both as recommended by the manufacturer's directions. The chromatographic strips were placed in closed containers to avoid contact with the walls. After, the strips were cut in 1cm pieces and the activity was determined in each NMS's activity calibrators. The radiopharmaceuticals pH was evaluated by using universal pH paper (Merck) and the obtained color was compared with its range of colors. It was observed that 33.34% and 2.3% of the tested radiopharmaceuticals showed PRQ (radiochemical purity) and pH values, respectively, are outside of the limits described by the manufacturers. The results show that the radiochemical purity assessment in the NMS's routine can indicate problems with a radioisotope tagging, allowing their exclusion before administration. (author)

  18. Groundwater assessment in water resources management at Nuclear and Energy Research Institute, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Sabrina M.V.; Marques, Joyce R.; Monteiro, Lucilena R.; Stellato, Thamiris B.; Silva, Tatiane B.S.C.; Faustino, Mainara G.; Silva, Douglas B. da; Cotrim, Marycel E.B.; Pires, Maria Aparecida F., E-mail: sabrinamoura@usp.br, E-mail: joyce.marques@usp.br, E-mail: luciremo@uol.com.br, E-mail: thamistellato@gmail.com, E-mail: tatianebscs@live.com, E-mail: mainarag@usp.br, E-mail: douglas.sbatista@yahoo.com.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    To comply with the guidelines for environmental control and legal requirements, the Nuclear and Energy Research Institute (IPEN/ CNEN - Brazil/ SP) performs the Environmental Monitoring Program for Chemical Stable Compounds (PMA-Q) since 2007, in attendance to the Term for the Adjustment of Conduct (TAC) signed between IPEN and the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA). The PMA-Q program includes the assessment of the IPEN's wastewater released in water body, and the groundwater assessment, which is carried out in nine monitoring wells. In groundwater is analyzed, by ion chromatography, species regulated by CONAMA 396/08 [01] fluoride, chloride, nitrite-N, nitrate-N, sulfate, sodium, potassium, ammonium, magnesium and calcium, besides other parameters. Furthermore, based on legal requirements, each year the program is reviewed and improvement actions are planned and implemented. Therefore, the integrated monitoring of groundwater should provide information on the quality and dynamics of the aquifer compared to seasonal variations and anthropogenic effects. Thus, this study intends to evaluate the chemical features of the institute groundwater, evaluating the database of the monitoring program from 2011 to 2014, for the ions chloride, nitrate-N, sulfate, sodium, potassium, magnesium, calcium and bicarbonate, using these information diagrams will be developed for the characterization of the wells. This assessment will be essential to support the control actions of environmental pollution and the management of water resources. Making possible the establishment of groundwater Quality Reference Figures (QRF), according to the CONAMA 396/08 [01] rating, in order to demonstrate that the activities developed at IPEN are not affecting on the aquifer features. (author)

  19. The feasibility of uranium enrichment in Brazil for use in nuclear bombs and the conceptual project of a nuclear explosive

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-05-01

    This work reports the steps to define a brazilian system of nuclear safeguards under the congress responsibility. It discusses as well the feasibility of uranium enrichment for nuclear weapons, the construction of a nuclear submarine and the conceptual project of a nuclear explosive. (A.C.A.S.)

  20. The Guadalajara Accord between Brazil and Argentina: a tentative step toward the nuclear weapons-free Latin America envisioned by the Treaty of Tlatelolco

    OpenAIRE

    Martin, Francis Xavier

    1991-01-01

    Approved for public release; distribution is unlimited In 1967, the treaty of Tlatelolco declared Latin America to be a nuclear weapons-free zone, but this goal remains unfulfilled. Argentina and Brazil, the :Latin American nations most capable of building nuclear weapons, refuse to comply with the treaty. Argentine and Brazilian military leaders pursued the development of nuclear weapons fro the 1970's to the late 1980's. The emergence of democratic regimes from the 1980's encouraged t...

  1. Strategic management at IPEN - Institute of Nuclear and Energetic Research, S P, Brazil

    International Nuclear Information System (INIS)

    Rodrigues, Claudio; Zouain, Desiree M.

    2000-01-01

    This panel presents an overview on the strategic management of the IPEN, S P, Brazil, with emphasis on the history, the main installations, the nature of the activities and training activities of the institute

  2. ABACC - Brazil-Argentina Agency for Accounting and Control of Nuclear Materials, a model of integration and transparence; ABACC - Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares, un ejemplo de integracion y transparencia

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Antonio A.; Do Canto, Odilon Marcusso, E-mail: oliveira@abacc.org.br, E-mail: odilon@abacc.org.br [Agencia Brasileno Argentina de Contabilidad y Control de Materiales Nucleares (ABACC), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    Argentina and Brazil began its activities in the nuclear area about the same time, in the 50 century past. The existence of an international nuclear nonproliferation treaty-TNP-seen by Brazil and Argentina as discriminatory and prejudicial to the interests of the countries without nuclear weapons, led to the need for a common system of control of nuclear material between the two countries to somehow provide assurances to the international community of the exclusively peaceful purpose of its nuclear programs. The creation of a common system, assured the establishment of uniform procedures to implement safeguards in Argentina and Brazil, so the same requirements and safeguards procedures took effect in both countries, and the operators of nuclear facilities began to follow the same rules of control of nuclear materials and subjected to the same type of verification and control. On July 18, 1991, the Bilateral Agreement for the Exclusively Peaceful Use of Nuclear Energy created a binational body, the Argentina-Brazil Agency for Accounting and Control of Nuclear Materials-ABACC-to implement the so-called Common System of Accounting and Control of Nuclear materials - SCCC. The deal provided, permanently, a clear commitment to use exclusively for peaceful purposes all material and nuclear facilities under the jurisdiction or control of the two countries. The Quadripartite Agreement, signed in December of that year, between the two countries, ABACC and IAEA completed the legal framework for the implementation of comprehensive safeguards system. The 'model ABACC' now represents a paradigmatic framework in the long process of economic, political, technological and cultural integration of the two countries. Argentina and Brazil were able to establish a guarantee system that is unique in the world today and that consolidated and matured over more than twenty years, has earned the respect of the international community.

  3. 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)

  4. Standardization of 123I and 18F for providing traceability of activity meters performed in the Radiopharmaceutical Production Service of the Instituto de Engenharia Nuclear, RJ, Brazil

    International Nuclear Information System (INIS)

    Andrade, E.A.L.; Delgado, J.U.; Iwahara, A.; Contic, C.C.

    2013-01-01

    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 123 I and 18 F activity measurements in Radiopharmaceuticals Production Service placed in Institute of Nuclear Engineering, Rio de Janeiro, RJ, Brazil. (author)

  5. Síntese em reator de hidrometalurgia de nanopartícula de ferrita de cobalto

    OpenAIRE

    Araújo, Elton John Nunes de

    2017-01-01

    Investigamos a síntese de nanopartículas de ferrita de cobalto por precipitação hidrotérmica, em reator de hidrometalurgia em temperaturas entre 100 e 250°C. Foram variados os parâmetros: temperatura de síntese, composição do meio reacional, concentração da base e presença de agente complexante. As nanopartículas obtidas foram caracterizadas do ponto de vista estrutural por difração de raios-X, sua composição foi verifica por medidas de espectroscopia por energia dispersiva de raios-x (EDX) e...

  6. Annual report 1999 - Brazil Nuclear Industry (INB); Relatorio anual 1999 - Industrias Nucleares do Brasil S.A

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This document presents the 1999 annual report covering the following activities: nuclear fuel, resources and application, ISO 9001, environment social activities, personnel, financial indicators, and countability.

  7. Evaluation of upper limit of accident probability in a nuclear reactor in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1979-01-01

    This work calls attention to the great probability of accident in a pessimist vision regarding optimist one. The author uses the upper limit presented in Ford Foundation report and applies it on brazilian case to an evaluation of risk of reactor accident in Brazil. (C.M.)

  8. 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)

  9. 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)

  10. Second national report of Brazil for the nuclear safety convention - introduction

    International Nuclear Information System (INIS)

    2001-01-01

    This document was prepared for fulfilling the Brazilian obligations under the Convention on Nuclear Safety. Chapter 1 presents some historical aspects of the Brazilian nuclear policy, targets to be attained for increasing the nuclear energy contribution for the national production of electric energy

  11. Second national report of Brazil for the nuclear safety convention - introduction

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-01

    This document was prepared for fulfilling the Brazilian obligations under the Convention on Nuclear Safety. Chapter 1 presents some historical aspects of the Brazilian nuclear policy, targets to be attained for increasing the nuclear energy contribution for the national production of electric energy.

  12. Risks in the operation of hydroelectric power plants and nuclear power in Brazil

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1986-01-01

    A comparison between the utilization of electrical energy generated by hydroelectric power plant and nuclear power plant is made. The risks from nuclear installations and the environmental effects of hydroelectric power plants and nuclear power plants are presented. (E.G.) [pt

  13. Radiometric analysis performed by the Environment Monitoring Service from IPEN (Institute of Energy and Nuclear Research), Brazil, between 1988 and 1991

    International Nuclear Information System (INIS)

    Venturini, L.; Nisti, M.B.; Pecequilo, B.R.S.

    1993-03-01

    This report presents the radiometric analyses made by the Environmental Monitoring Service from the Institute of Energy and Nuclear Research (IPEN), Brazil, in the period 1988-1991. The experimental procedures, the products analysed and their respective quantities are described. (F.E.). 11 refs, 3 tabs

  14. Methodology to monitor and diagnostic vibrations of the motor-pumps used in the primary cooling system of IEAR-1 nuclear research reactor; Metodologia para monitoracao e diagnostico de vibracao das bombas moto-operadas do circuito primario de refrigeracao do Reator IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Benevenuti, Erion de Lima

    2004-07-01

    The objectives of this study are to establish a strategy to monitor and diagnose vibrations of the motor pumps used in the primary reactor cooling system of the IEA-R1 nuclear research reactor, to verify the possibility of using the existing installed monitoring vibration system and to implement such strategy in a continuous way. Four types of mechanical problems were considered: unbalancing, misalignment, gaps and faults in bearings. An adequate set of analysis tools, well established by the industry, was selected. These are: global measurements of vibration, velocity spectrum and acceleration envelope spectrum. Three sources of data and information were used; the data measured from the primary pumps, experimental results obtained with a Spectra Quest machine used to simulate mechanical defects and data from the literature. The results show that, for the specific case of the motor-pumps of IEA-R1 nuclear research reactor, although the technique using the envelope of acceleration, which is not available in the current system used to monitor the vibration of the motor pumps, is the one with best performance, the other techniques available in the system are sufficient to monitor the four types of mechanical problems mentioned. The proposed strategy is shown and detailed in this work. (author)

  15. 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)

  16. Potential radiological impact assessment related to the visit of nuclear submarines to the port of Rio de Janeiro, Brazil

    International Nuclear Information System (INIS)

    Pereira, Jose Francisco; Rochedo, Elaine R.R.

    2005-01-01

    Brazil is signatory of international protocols for receiving the visit of nuclear ships and submarines. Such naval units, during their stays in Brazilian ports, inform that there is no release of radioactive material to the environment. However, there is always the possibility of an accident, leading to environmental release of radioactive material. This work had the objective of assessing the potential radiological environmental impact due to the eventual occurrence of an accident during the permanence of ships and submarines of nuclear propulsion in the port of the city of Rio de Janeiro, in Guanabara Bay. The accident scenarios considered include releases to the marine environment and to the atmosphere. Previous results indicated that, in normal operation conditions, no significant radiological impact is foreseen due to the visits of nuclear submarines to the city, even if small routine radionuclide releases occur. The analysis of the accidental releases, however, indicates that the anchorage points should be located at a minimum distance of 2,5 km of inhabited areas in the contour the Bay. (author)

  17. Innovation and knowledge generation in cooperation nets: challenges for regulations in the nuclear safety area in Brazil

    International Nuclear Information System (INIS)

    Staude, Fabio

    2014-01-01

    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)

  18. Workplace and occupational health: The first metal evaluation using nuclear and analytical techniques in the State of Minas Gerais, Brazil

    International Nuclear Information System (INIS)

    Barros Correia Menezes, M.A. de; Vilhena Schayer Sabino, C. de; Melo Mattos, S.V. de; Santos Filho, S.; Diniz, E.

    1998-01-01

    Belo Horizonte, the capital of the State of Minas Gerais and its neighbourhood are the second industrial center of Brazil, concentrating many industries in several areas mainly metal refining and transformation. There are no registers about the level of metal concentration in the environmental air in the industry, nor even of the level of workers' contamination. The overall objective of this Project is to make a survey of the exposures to metals related to occupational diseases in galvanizing industry, which is responsible for the majority of occurrences of occupational diseases. The survey will be accomplished using as bio-indicators hair, nails, blood, urine, and individual air filters. These matrixes will indicate the incorporation of metals and the exposure level. The analytical techniques that will be applied are the neutron activation joined to related non nuclear analytical techniques, such as atomic absorption. (author)

  19. Workplace and occupational health: The first metal evaluation using nuclear and analytical techniques in the State of Minas Gerais, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Barros Correia Menezes, M.A. de; Vilhena Schayer Sabino, C de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Comissao Nacional de Energia Nuclear (CNEN), Sector de Radioquimica, Belo Horizonte, Minas Gerais (Brazil); Melo Mattos, S.V. de [FUNED, Divisao de Bromatologia e Toxicologia, Servico de Quimica Especializada, Belo Horizonte, MG (Brazil); Santos Filho, S [Secretaria Minicipal de Saude de Belo Horizonte, Belo Horizonte, MG (Brazil); Diniz, E [FUNDACENTRO/BH, Belo Horizonte, MG (Brazil)

    1999-12-31

    Belo Horizonte, the capital of the State of Minas Gerais and its neighbourhood are the second industrial center of Brazil, concentrating many industries in several areas mainly metal refining and transformation. There are no registers about the level of metal concentration in the environmental air in the industry, nor even of the level of workers` contamination. The overall objective of this Project is to make a survey of the exposures to metals related to occupational diseases in galvanizing industry, which is responsible for the majority of occurrences of occupational diseases. The survey will be accomplished using as bio-indicators hair, nails, blood, urine, and individual air filters. These matrixes will indicate the incorporation of metals and the exposure level. The analytical techniques that will be applied are the neutron activation joined to related non nuclear analytical techniques, such as atomic absorption. (author) 7 refs, 2 tabs

  20. Procedures, activities and doses in nuclear medicine cycle in Brazil; Procedimentos, atividades e doses no ciclo da medicina nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Silvia Maria Velasques de

    2005-07-01

    With the aim of characterizing nuclear medicine procedures performed in Brazil, activities of radiopharmaceuticals used and effective doses to patients, data was collected from nuclear medicine institutions in three regions of the country, namely the Southeast, the Northeast and the South regions, representing public hospitals, university hospitals, private and philanthropic institutions with low, medium and high levels of consumption of radiopharmaceuticals. The three chosen regions are responsible for 92% of radiopharmaceutical consumption and imaging equipment in the country. Accordingly, it was requested of some participating institutions to fulfill manually from individual patients data, to record gender, age, weight, height and activities used, for each type of exam as well as the equipment used. In others, the researcher collected data personally. Per institution, nuclear medicine diagnostic procedures ranged from 700 to 13,000 per year, most of which are myocardial and bone imaging procedures, and imaging equipment ranged, from 1 to 8 machines, one or two head SPECT's (hybrid or not). 26.782 patients protocols were analysed, 24.371 adults and 2.411 children and teenagers. For adult patients, differences were observed in the amount of activities used in diagnostic procedures between public and private institutions, with lower average activities used in public institutions. Activities administered to children and their effective doses were difficult to evaluate due to the incompleteness of individual records. Appropriate individual patient records could be adopted without affecting hospitals routine and contributing for a comprehensive evaluation of the radiation protection of nuclear medicine patients. Data from 8.881 workers were analysed, 346 working at nuclear medicine institutions. For monitored workers and measurably exposed workers in nuclear medicine, the values 2.3 mSv and 5.4 mSv, respectively, for effective annual doses are greater than data

  1. Factors in low-carbon energy transformations: Comparing nuclear and bioenergy in Brazil, Sweden, and the United States

    International Nuclear Information System (INIS)

    Hultman, Nathan E.; Malone, Elizabeth L.; Runci, Paul; Carlock, Gregory; Anderson, Kate L.

    2012-01-01

    Policies to address climate change by reducing greenhouse gas emissions might be made more effective if we can better understand the pathways by which transformative technologies become significant components of energy systems. Indeed, the central question of mitigation revolves around the scope of policy to influence or accelerate the diffusion of low-carbon technology. While market forces clearly influence technology deployment, understanding the longer-term and large-scale changes in the energy system requires a broader understanding of the relative influence of institutional, behavioral, and social factors. This paper presents the results of an interview-based, comparative case approach to investigating systematically the relative importance of these non-economic factors influencing technological change across technology and country contexts. We identified two low-carbon energy sectors (bioenergy and nuclear power) that underwent significant changes over the past 50 years in the energy portfolio of three countries: Brazil, Sweden, and the United States. We identified nine categories of factors that might contribute to these large technological transformations, and then evaluated, via interviews with sector participants in each country, which factors were viewed as being determinative or highly influential in the trajectory of that technology in their country context. We also draw out policy implications and directions for future research. - Highlights: ► Study of energy transformations in bioenergy and nuclear energy in Brazil, Sweden, and the US. ► Data include survey and 78 interviews across 3 countries and 2 sectors. ► Across all countries and sectors, domestic policy was seen as the major factor in transitions. ► Other key factors with more variance were technological characteristics and industry structure. ► Study adds empirical detail to understanding of relative weights of factors in energy transitions.

  2. Activities of the IPEN laboratory (CNEN/SP - Brazil) of nuclear metrology

    International Nuclear Information System (INIS)

    Dias, M.S.; Koskinas, M.F.; Pocobi, E.; Silva, C.A.M.; Machado, R.R.

    1987-01-01

    The determination of radionuclide activity for radioactive sources and standardized solutions is reported as the main purpose of the IPEN laboratory of nuclear metrology. The measurement systems installed in the laboratory, the measurable activity intervals and some of the standardized radionuclides (emphasizing the ones used in nuclear medicine) are presented. (M.A.C.) [pt

  3. Aspects and progresses of the Program for Regulatory Inspection of Nuclear Medicine in Brazil

    International Nuclear Information System (INIS)

    Alves, Carlos Eduardo Gonzalez Ribeiro

    2004-01-01

    This work aims to show the advances in the Nuclear Medicine auditing field performed by the Nuclear Medicine Group of the Division of Radiotherapy and Nuclear Medicine of the Inst. of Radiation Protection and Dosimetry. The main aspects observed during the auditing are presented as well as the evolution of the non-conformities. It is shown that the occurrence of these non-conformities decreases year by year, primarily as a function of the severity of the auditing and the consciousness of the personal of Nuclear Medicine Services. Results point clearly to the importance of the coercion actions to guarantee a radiation protection level in compliance with the standards established by the Brazilian Nuclear Energy Commission. (author)

  4. Survey or quality for radiopharmaceuticals and activimeters available in services of nuclear medicine from Recife, Pernambuco State, Brazil

    International Nuclear Information System (INIS)

    Nogueira, Fernanda Maria Dornellas Camara

    2001-08-01

    The radiopharmaceutical used in Nuclear Medicine must present high chemical and radiochemical purities in order to obtain images with contrast and clearness adequate for the diagnosis. Test should be made by the Nuclear Medicine institutes to evaluate the presence of molybdenum, aluminium and the free Tc O 4 - /TC-HR in the radiopharmaceutical before they use it. On the other hand, the activity to be administered to the patient is determined by the activimeters available in the Nuclear Medicine institutions. So it is necessary to perform tests to verify operating conditions of the activimeter to guarantee that the dose received by patient is the prescribed by the physician. In Brazil, few clinics of Nuclear Medicine are implanting the tests of the radiopharmaceutical and of the activimeters. The objective of this work is to establish the procedures for the radiopharmaceutical tests and to evaluate the quality of the radiopharmaceutical used at the clinics of Recife, as well as the operation conditions of the activemeters in these institutions. The results show that all the activimeters analyzed present a good performance and that the equipment with Geiger-Muller detectors present larger instability than the ones that use ionization chamber. Concerning the Mo/Tc generators, it was observed that only one presented Mo in the generator eluate with concentration over the acceptable limits and that the concentration of Al found in the samples analyzed were below the limits. On the other hand, in 73% of the MIBI analyzed samples were observed problems with its preparation that were caused by the procedures adopted at the clinics, which do not follow the manufacturers recommendations. (author)

  5. Modelagem e simulação de reator de leito expandido aplicado ao hidroprocessamento de oleos pesados e residuos de destilação

    OpenAIRE

    João Capistrano Nobre de Abreu

    1995-01-01

    Resumo: O presente trabalho apresenta a modelagem e simulação de um reator de leito fluidizado trifásico aplicado ao hidroprocessamento de óleos pesados e resíduos de destilação. Duas reações principais foram consideradas no desenvolvimento do modelo, o hidrocraqueamento e a hidrodemetalização tendo sido a primeira considerada como exclusivamente térmica e a segunda como catalítica. O grau de mistura do reator foi representado de duas maneiras distintas. Inicialmente, considerou-se o sistem...

  6. Neutronic characterization of cylindrical core of minor excess reactivity in the nuclear reactor IPEN/MB-01 from the measure of spatial and energetic distribution of neutron flux distribution; Caracterizacao do nucleo cilindrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuicao espacial e energetica do fluxo de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Aredes, Vitor Ottoni Garcia

    2014-07-01

    In this work was conducted the mapping of the thermal and epithermal neutrons flux and the energy spectrum of the neutrons in the reactor core IPEN/MB-01 for a cylindrical core configuration with minor excess reactivity, which is 28 x 28 fuel rods arranged in north-south and east-west directions. The calibration of control rods for this configuration determined their excess reactivity. The lower excess reactivity in the core decreased neutron flux disturbance caused by the neutron absorbing rods , given that the nuclear reactor was operated with the rods almost completely removed . Was used the 'Activation Analysis Technique' with the thin foil activation detectors ( infinitely diluted and hyper-pure), of different materials that work in different energy ranges, to calculate the saturation activity, used for determining the neutron flux and in the SANDBP code as input for the calculation of the neutrons energy spectrum. To discriminate thermal and epithermal flux , was used the 'Cadmium RatioTechnique' . The activation detectors were distributed in a total of 140 radial and axial positions in the reactor core and 16 irradiation, with bare and covered with cadmium activation foils. A model of this configuration was simulated by MCNP-5 code to determine the cadmium correction factor and comparison of the results obtained experimentally. The cylindrical configuration desired, with 17% less fuel than the standard rectangular configuration (28 x 26 fuel rods), reached criticality with the control rods approximately 90% removed, which decreased considerably the disturbance in neutron flux. Given the highest power density of the 28 x 28 cylindrical core, the neutron flux increased by over 50% in the central regions of the core compared to the values of the 28 x 26 standard rectangular core. (author)

  7. Usage and conditions of radiation protection of nuclear meters in Brazil

    International Nuclear Information System (INIS)

    Guimarães, E.F.; Silva, F.C.A. da

    2017-01-01

    The industries of mining, pulp, oil, etc. which require a quality control in the processes, use the nuclear meters with sealed radioactive sources coupled to a radiation detector that generate accurate and fast answers regarding the level, thickness, density and humidity of different types of materials. Nuclear meters are classified as fixed or portable and use transmission, backscatter or reactive systems. As they use radioactive sources with various ranges of activities, they are classified by the International Atomic Energy Agency - AIEA as Category 3 and 4, of medium and low radiological risk, and must therefore have a suitable level of radiation protection for safe use in the installation. The Brazilian National Energy Commission - CNEN controls approximately 500 authorized facilities with nuclear meters. The paper technically describes the nuclear meters and the radiological protection procedures that must be followed for the safety of the IOEs (occupationally exposed individuals) and individuals from the public, based on the specific nuclear meter test program for CNEN radiation protection supervisor. The professionals who handle these nuclear meters should be aware of the radiological risk to their own protection and to individuals in the public. For safe operation with nuclear meters, a number of requirements must be observed according to the type and need of the installation

  8. Implementation of internal monitoring programs for workers occupationally exposed by 131I in nuclear medicine services in Brazil

    International Nuclear Information System (INIS)

    Oliveira, S.M.; Dantas, A.L.A.; Dantas, B.M.

    2017-01-01

    In nuclear medicine services (NMS), workers routinely handle radionuclides for diagnostic and therapy. This practice represents a risk of incorporation by these radionuclides. The International Atomic Energy Agency (IAEA) recommends the implementation of an internal monitoring program on workers exposed to annual effective doses greater than 1 mSv, as for example, those who handle 131 I for therapy in NMS. Currently, in Brazil, there are not enough available laboratories qualified to provide internal monitoring services to attend all possible demand of internal monitoring if it such regulation were applied by the Brazilian Nuclear Regulatory Board (CNEN). The objective of this work is to disseminate simple and inexpensive methods for in vivo routine thyroid monitoring of 131 I using equipment available in the NMS. Devices available in two public hospitals located in the city of Rio de Janeiro were calibrated for use in occupational internal monitoring. The equipment evaluated in this work presented enough sensitivity for such application, being suitable to access intakes of 131 I in the thyroid and able to estimate doses below 1 mSv. (author)

  9. Implementation of internal monitoring programs for workers occupationally exposed by {sup 131}I in nuclear medicine services in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, S.M.; Dantas, A.L.A.; Dantas, B.M., E-mail: salomao.marques@ymail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Dosimetria

    2017-07-01

    In nuclear medicine services (NMS), workers routinely handle radionuclides for diagnostic and therapy. This practice represents a risk of incorporation by these radionuclides. The International Atomic Energy Agency (IAEA) recommends the implementation of an internal monitoring program on workers exposed to annual effective doses greater than 1 mSv, as for example, those who handle {sup 131}I for therapy in NMS. Currently, in Brazil, there are not enough available laboratories qualified to provide internal monitoring services to attend all possible demand of internal monitoring if it such regulation were applied by the Brazilian Nuclear Regulatory Board (CNEN). The objective of this work is to disseminate simple and inexpensive methods for in vivo routine thyroid monitoring of {sup 131}I using equipment available in the NMS. Devices available in two public hospitals located in the city of Rio de Janeiro were calibrated for use in occupational internal monitoring. The equipment evaluated in this work presented enough sensitivity for such application, being suitable to access intakes of {sup 131}I in the thyroid and able to estimate doses below 1 mSv. (author)

  10. Study of the economic viability of the innovative nuclear reactor SMART in Brazil

    International Nuclear Information System (INIS)

    Escanhoela, Cordelia Mara Fazzio; Lima, Ana Cecilia de Souza; Sabundjian, Gaianê

    2017-01-01

    The main objective of this study is to evaluate the economic viability of the installation and operation of the innovative System - Integrated Modular Advanced Reactor (SMART) in Brazil. SMART, developed by the Korea Atomic Energy Research Institute (KAERI), is a small and modular Power Water Reactor (PWR), presents electric power of 100 MW and thermal power of 330 MW; it has a passive safety system and integral refrigeration configuration, characteristics that, allied with modularization, simplification and technological improvements, give SMART greater reliability and economy when compared to conventional reactors. SMART presents, in addition to electricity production, the functions of seawater desalination and district heat generation. The research is based on projections of energy demand in the medium and long term with emphasis on electricity and search for the reduction of greenhouse gases. These previsions indicate the need for energy expansion and diversification of the current sources in Brazil, predominantly water sources. The methodology used is based on the cost of electric generation, production capacity and construction time of SMART, adopting the investment model similar to the Angra 3 plant and the use of mirrored costs between the plants. The feasibility of the project was evaluated through the financial criteria: Internal Rate of Return (IRR), Net Present Value (NPV) and Weighted Average Cost of Capital (WACC), whose revenue should be generated through a tariff passed on to the consumer. (author)

  11. Study of the economic viability of the innovative nuclear reactor SMART in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Escanhoela, Cordelia Mara Fazzio; Lima, Ana Cecilia de Souza; Sabundjian, Gaianê, E-mail: liafazzio@hotmail.com, E-mail: aclima@ipen.br, E-mail: gdjian@ipen.br [Centro de Engenharia Nuclear - CEN, Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The main objective of this study is to evaluate the economic viability of the installation and operation of the innovative System - Integrated Modular Advanced Reactor (SMART) in Brazil. SMART, developed by the Korea Atomic Energy Research Institute (KAERI), is a small and modular Power Water Reactor (PWR), presents electric power of 100 MW and thermal power of 330 MW; it has a passive safety system and integral refrigeration configuration, characteristics that, allied with modularization, simplification and technological improvements, give SMART greater reliability and economy when compared to conventional reactors. SMART presents, in addition to electricity production, the functions of seawater desalination and district heat generation. The research is based on projections of energy demand in the medium and long term with emphasis on electricity and search for the reduction of greenhouse gases. These previsions indicate the need for energy expansion and diversification of the current sources in Brazil, predominantly water sources. The methodology used is based on the cost of electric generation, production capacity and construction time of SMART, adopting the investment model similar to the Angra 3 plant and the use of mirrored costs between the plants. The feasibility of the project was evaluated through the financial criteria: Internal Rate of Return (IRR), Net Present Value (NPV) and Weighted Average Cost of Capital (WACC), whose revenue should be generated through a tariff passed on to the consumer. (author)

  12. Consolidated progress report for 1975 on nuclear data activities in the NDS service area: Argentina, Bangladesh, Brazil, Bulgaria, Hungary, India, Iran, Iraq, Israel, Pakistan, Poland, Romania, South Africa, Yugoslavia

    International Nuclear Information System (INIS)

    1976-01-01

    A consolidated progress report for 1975 on nuclear data activities in the NDS service area is presented for the following countries: Argentina, Bangladesh, Brazil, Bulgaria, Hungary, India, Iran, Iraq, Israel, Pakistan, Poland, Romania, South Africa, Yugoslavia

  13. Evolutionary history of Phakopsora pachyrhizi (the Asian soybean rust in Brazil based on nucleotide sequences of the internal transcribed spacer region of the nuclear ribosomal DNA

    Directory of Open Access Journals (Sweden)

    Maíra C. M. Freire

    2008-01-01

    Full Text Available Phakopsora pachyrhizi has dispersed globally and brought severe economic losses to soybean growers. The fungus has been established in Brazil since 2002 and is found nationwide. To gather information on the temporal and spatial patterns of genetic variation in P. pachyrhizi , we sequenced the nuclear internal transcribed spacer regions (ITS1 and ITS2. Total genomic DNA was extracted using either lyophilized urediniospores or lesions removed from infected leaves sampled from 26 soybean fields in Brazil and one field in South Africa. Cloning prior to sequencing was necessary because direct sequencing of PCR amplicons gave partially unreadable electrophoretograms with peak displacements suggestive of multiple sequences with length polymorphism. Sequences were determined from four clones per field. ITS sequences from African or Asian isolates available from the GenBank were included in the analyses. Independent sequence alignments of the ITS1 and ITS2 datasets identified 27 and 19 ribotypes, respectively. Molecular phylogeographic analyses revealed that ribotypes of widespread distribution in Brazil displayed characteristics of ancestrality and were shared with Africa and Asia, while ribotypes of rare occurrence in Brazil were indigenous. The results suggest P. pachyrhizi found in Brazil as originating from multiple, independent long-distance dispersal events.

  14. Licensing authority's control of radiation sources and nuclear materials in Brazil

    International Nuclear Information System (INIS)

    Binns, D.A.C.

    2002-01-01

    Full text: The Brazilian Nuclear Energy Commission is the national licensing authority and among its responsibilities is the control of nuclear materials and radiation sources. This control is carried out in three different ways: 1) Control of the import and export of nuclear materials and radiation sources. To be able to import or export any nuclear material or radiation source, the user has to have an explicit permission of the licensing authority. This is controlled by electronic means in which the user has to fill a special form found on the licensing authority's home page, where he has to fill in his name, license number, license number of his radiation protection officer and data of the material to be imported or exported. These data are checked with a data base that contains all the information of the licensed users and qualified personnel before authorization is emitted. The airport authorities have already installed x-ray machines to check all baggages entering or leaving the country. 2) Transport and transfer permit for radiation sources. In order to transport and/or transfer radiations sources and nuclear materials within the country, the user(s) have to submit an application to the licensing authority. The user(s) fill out an application form where he fills in his company's name, licensing I.D., radiation protection officer's name and I.D and identification of the sources involved. These information are checked with the licensing operations data before the operations is permitted. 3) Inspections and radiation monitoring systems. Routine and regulatory inspections are continuously carried out where the user's radiation sources and nuclear materials inventory are checked. Also the physical security and protection of these materials are verified. The installation of monitoring systems is an item that is being discussed with the airport authorities so as to increase the possibilities of detecting any illegal transport of these materials. (author)

  15. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2008-01-01

    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 [es

  16. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2007-01-01

    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

  17. Enriquecimento de microrganismos metanotróficos a partir de lodo de reator UASB tratando esgotos domésticos

    Directory of Open Access Journals (Sweden)

    Luciene Alves Batista Siniscalchi

    2016-03-01

    Full Text Available RESUMO Nesse estudo, microrganismos metanotróficos foram enriquecidos a partir de lodo proveniente de um reator UASB tratando esgotos domésticos em reator em batelada sequencial (RBS com meio autotrófico contendo nitrito e nitrato. As eficiências médias de remoção de nitrito e nitrato foram de 68% e 53%, respectivamente, provavelmente devido à atividade heterotrófica desnitrificante. A detecção de arquéias dos grupos ANME-I e ANME-II foram realizadas por PCR durante todo período de cultivo. A estrutura da comunidade microbiana presente no inóculo e enriquecida no RBS após 100 dias de operação foi estudada por pirosequenciamento. Os resultados das análises demonstraram que a comunidade enriquecida no reator foi diferente à inoculada. Os filos dominantes no inóculo foram Synergistestes , Firmicutes e Euryarchaeota , ao passo que na biomassa enriquecida Planctomycetes, Verrucomicrobia, Chloroflexi e Proteobacteria predominaram. As condições de cultivo do RBS reduziram a abundância de Methanobacterium (8% para 1% e selecionaram bactérias metanotróficas como Methylocaldum , Methylocistis e Methylosinus . As sequências de Methylocaldum sp. apresentaram abundância relativa de 2.5%. A presença e elevada predominância do filo Verrucomicrobia na biomassa enriquecida do RBS sugere que outras espécies de metanotróficas, ainda pouco conhecidas, relacionadas a este filo podem estar presentes no reator. O potencial de oxidação anaeróbia do metano foi determinado para ambas amostras e revelaram que a atividade metanotrófica da biomassa foi aproximadamente três vezes maior que a do inóculo. Em suma, estes resultados sugerem que o inóculo usado e as condições de cultivo aplicadas foram adequados para o enriquecimento de metanotróficas.

  18. Comportamento de reator de leito fluidizado trifásico aeróbico utilizando diferentes materiais suporte

    OpenAIRE

    Martins, Cláudia Lavina

    2003-01-01

    Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnológico. Programa de Pós-Graduação em Engenharia Ambiental. Este trabalho apresenta estudos realizados com reator de leito fluidizado trifásico aeróbio (RLFTA), aplicado ao tratamento de esgoto sanitário, tendo como objetivo avaliar seu comportamento utilizando diferentes materiais suporte: PET, OSBG® e PVC. Foram aplicadas cargas orgânicas volumétricas (COV) de 13 a 29 Kg DQO/m3.dia e tempo de retenção hidráulica ...

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  20. SUS in nuclear medicine in Brazil: analysis and comparison of data provided by Datasus and CNEN.

    Science.gov (United States)

    Pozzo, Lorena; Coura Filho, George; Osso Júnior, João Alberto; Squair, Peterson Lima

    2014-01-01

    To investigate the outpatient access to nuclear medicine procedures by means of the Brazilian Unified Health System (SUS), analyzing the correspondence between data provided by this system and those from Comissão Nacional de Energia Nuclear (CNEN) (National Commission of Nuclear Energy). Data provided by Datasus regarding number of scintillation chambers, outpatient procedures performed from 2008 to 2012, administrative responsibility for such procedures, type of service providers and outsourced services were retrieved and evaluated. Also, such data were compared with those from institutions certified by CNEN. The present study demonstrated that the system still lacks maturity in terms of correct data input, particularly regarding equipment available. It was possible to list the most common procedures and check the growth of the specialty along the study period. Private centers are responsible for most of the procedures covered and reimbursed by SUS. However, many healthcare facilities are not certified by CNEN. Datasus provides relevant data for analysis as done in the present study, although some issues still require attention. The present study has quantitatively depicted the Brazilian reality regarding access to nuclear medicine procedures offered by/for SUS.

  1. SUS in nuclear medicine in Brazil: analysis and comparison of data provided by Datasus and CNEN*

    Science.gov (United States)

    Pozzo, Lorena; Coura Filho, George; Osso Júnior, João Alberto; Squair, Peterson Lima

    2014-01-01

    Objective To investigate the outpatient access to nuclear medicine procedures by means of the Brazilian Unified Health System (SUS), analyzing the correspondence between data provided by this system and those from Comissão Nacional de Energia Nuclear (CNEN) (National Commission of Nuclear Energy). Materials and Methods Data provided by Datasus regarding number of scintillation chambers, outpatient procedures performed from 2008 to 2012, administrative responsibility for such procedures, type of service providers and outsourced services were retrieved and evaluated. Also, such data were compared with those from institutions certified by CNEN. Results The present study demonstrated that the system still lacks maturity in terms of correct data input, particularly regarding equipment available. It was possible to list the most common procedures and check the growth of the specialty along the study period. Private centers are responsible for most of the procedures covered and reimbursed by SUS. However, many healthcare facilities are not certified by CNEN. Conclusion Datasus provides relevant data for analysis as done in the present study, although some issues still require attention. The present study has quantitatively depicted the Brazilian reality regarding access to nuclear medicine procedures offered by/for SUS. PMID:25741070

  2. General directives in the planning of the nuclear sector in Brazil

    International Nuclear Information System (INIS)

    Carvalho, J.F. de

    1990-01-01

    Due mostly to the use of radio-isotopes in activities such as medicine, industry, agriculture and scientific research, notable progress has been made in recent decades in industrial and agricultural production, as well as in the prolongation of life expectancy, in practically every part of the world. Moreover, since 1948, nuclear reactors have been in commercial operation for the generation of electrical energy which has enabled countries such as France, Belgium, Japan and others to continue to benefit from large scale use of electricity. The employment of radio-isotopes, however, and the operation of nuclear power stations is dependent upon a complex cycle of activities, ranging from the mining and processing of uranium minerals to the final disposal of radio-active waste. The present work traces some directives which should be followed in the planning of the nuclear sector and illustrates the principal benefits and responsabilities arising out of the use of radio-isotopes and of nuclear generation of electrical power, at short, medium and long term. (author)

  3. Síntese de redes de reatores para condições isotérmicas - DOI: 10.4025/actascitechnol.v30i2.5494

    Directory of Open Access Journals (Sweden)

    Lincoln Kotsuka da Silva

    2008-10-01

    Full Text Available No presente trabalho apresenta-se um procedimento computacional para síntese de redes de reatores (SRR operando em condições isotérmicas. Uma superestrutura de rede de reatores formada por reatores ideais CSTR e PFR é proposta e o problema apresenta uma formulação de programação não linear (PNL. São consideradas reações complexas (série/paralelas. A função objetivo é baseada no rendimento ou na seletividade em relação ao produto desejado, sujeito a diferentes condições de operação. As restrições ao problema são provenientes dos balanços de massa e da configuração da superestrutura considerada. No procedimento computacional é proposto um Algoritmo Genético (AG para obtenção do arranjo ótimo de reatores com máximo rendimento ou seletividade com menor volume reacional. Os resultados obtidos são condizentes com os obtidos na literatura.

  4. Analysis of the distribution of radiopharmaceuticals for nuclear medicine in Brazil

    International Nuclear Information System (INIS)

    Kuahara, Lilian T.; Correa, Eduardo L.; Potiens, Maria P.A.

    2013-01-01

    The objective of this study was to analyze the distribution of radiopharmaceuticals produced by Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN), as part of a project to develop a methodology for control and calibration of activimeters used by these Nuclear Medicine Services. This survey was conducted using registry data of registered customers and, with bases in such information, we analyzed the number of clinics all over the country. Considering the distribution of radiopharmaceuticals and what the most used in 2011, there was a total of 365 clinics, and this distribution as follows: Southeast with 56%, South 18%, Northeast 15%, North 4%, and Midwest with 7%. Among the various radioisotopes provided 26 were sold and most in demand are the 67 Ga, 131 I and IPEN-tec (technetium generator)

  5. Current situation of management of radioactive wastes in the Instituto de Engenharia Nuclear, Brazil

    International Nuclear Information System (INIS)

    Zidan, Priscila M.; Silva, Joao C.P.; Echternacht, Marcus V.

    2000-01-01

    As its own legal responsibility, Nuclear Engineering Institute - IEN has received radioactive wastes generated in Rio de Janeiro and Espirito Santo states. But, from July 1997 to June 1999, IEN was not able to receive wastes because of the lack of space in the temporary repository. Recent studies show that increasing the treatment facilities could contribute to optimize the disposal of wastes. According to National Commission of Nuclear Energy resolutions, IEN was several times requested for discarding of lightning rods containing Am-241 and Ra-226. This fact motivated IEN to look for options to make possible the receiving of wastes until a new deposit were built. A temporary place was prepared and since last July it has been receiving wastes again. In this paper it is described the current structure of radioactive waste management at IEN, objectives and goals to be reached until December 2000. (author)

  6. Uranium recovery from waste of the nuclear fuel cycle plants at IPEN-CNEN/SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Freitas, Antonio A.; Ferreira, Joao C.; Zini, Josiane; Scapin, Marcos A.; Carvalho, Fatima Maria Sequeira de, E-mail: afreitas@ipen.b, E-mail: jcferrei@ipen.b, E-mail: jzini@ipen.b, E-mail: mascapin@ipen.b, E-mail: fatimamc@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Sodium diuranate (DUS) is a uranium concentrate produced in monazite industry with 80% typical average grade of U{sup 3}O{sup 8}, containing sodium, silicon, phosphorus, thorium and rare earths as main impurities. Purification of such concentrate was achieved at the nuclear fuel cycle pilot plants of uranium at IPEN by nitric dissolution and uranium extraction into an organic phase using TBP/Varsol, while the aqueous phase retains impurities and a small quantity of non extracted uranium; both can be recovered later by precipitation with sodium hydroxide. Then the residual sodium diuranate goes to a long term storage at a safeguards deposit currently reaching 20 tonnes. This work shows how uranium separation and purification from such bulk waste can be achieved by ion exchange chromatography, aiming at decreased volume and cost of storage, minimization of environmental impacts and reduction of occupational doses. Additionally, the resulting purified uranium can be reused in nuclear fuel cycle.(author)

  7. Control system and nuclear materials inventory at IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Araujo, Jose Adroaldo de; Enokihara, Cyro Teiti

    2002-01-01

    The history, requirements, organization, and operation of the State System of Accounting and Control from the Institute for Energetic and Nuclear Research (IPEN-CNEN/SP) are described. The implementation system at the institution take into consideration the national and international safeguards requirements. It has started by the nuclear material (U, Pu and Th) physical inventory taking, including their provenance and transformation. The earlier computerized accounting system used for control has been replaced by a new one developed by the National Authority (CNEN/CSG). The optimized system has more flexibility, giving a more effective answer to any occurred change on Material Balance Area. The present system make use of an effective methodology. (author)

  8. Pós-tratamento de efluente nitrificado da parboilização de arroz utilizando desnitrificação em reator UASB Post-treatment a nitrified parboilized rice wastewater using denitrification in UASB reactor

    Directory of Open Access Journals (Sweden)

    Loraine Andre Isoldi

    2005-12-01

    Full Text Available Um sistema combinado reator UASB-reator aeróbio foi utilizado para a remoção de nitrogênio total e DQO de efluente de parboilização de arroz. O experimento foi realizado em reatores de bancada, com volumes de 4 L (UASB e 3,6 L (reator aeróbio. Os parâmetros de operação pH, temperatura, alcalinidade e concentração de ácidos voláteis foram monitorados durante o período experimental. Para o reator aeróbio de mistura completa, foi determinada, também, a concentração de oxigênio dissolvido. O sistema combinado reator UASB-reator aeróbio apresentou uma eficiência de remoção de carbono de 84% e uma eficiência de remoção de nitrogênio total Kjeldahl de 83%. O sistema proposto, nas condições experimentais, demonstrou ser adequado para remoção, simultânea, de DQO e de compostos oxidados de nitrogênio, em reator UASB.An UASB-aerobic reactor system was used for the removal of total nitrogen and COD of effluent from industries of parboilized rice. The experiment was performed in reactors with volumes of 4 L (UASB reactor and 3,6 L (aerobic reactor, respectevely. Temperature, pH, alkalinity and volatile acids concentration were monitored during the experiment. Dissolved oxygen concentration was determined for the aerobic reactor. The UASB-aerobic reactor system showed 84% carbon removal efficiency and 83% total Kjeldahl nitrogen removal efficiency. This system was able to remove, efficiently, COD and nitrogen in an UASB reactor.

  9. Partida de reator anaeróbio compartimentado em série com um reator anaeróbio de manta de lodo, utilizando parâmetros de sedimentabilidade para formação da biomassa

    Directory of Open Access Journals (Sweden)

    Cristine Serafine Neves

    2015-12-01

    Full Text Available RESUMO Este estudo objetivou avaliar a formação da biomassa de boa qualidade tanto no reator anaeróbio compartimentado (RAC quanto no reator anaeróbio de manta de lodo (UASB, aplicando parâmetros adequados à sedimentação dos sólidos sedimentáveis (SS presentes na água residuária de suinocultura (ARS. O RAC e o UASB operaram em série com os tempos de detenção hidráulica (TDHs de 15 e 9h, respectivamente, correspondendo a cargas orgânicas volumétricas (COVs médias de 53,8 e 36,2 kg.m³.d¹ em termos de DQOT, respectivamente. As eficiências médias de remoção de DBO520°C, durante o processo de partida e formação da biomassa, foram: 68% para RAC e 55% para UASB, e em termos de DQO: 78% para RAC e 70% para UASB, respectivamente. Os autores concluíram que é possível, mediante os parâmetros de sedimentação adotados, formar uma biomassa peletizada, mesmo operando o sistema com altas cargas orgânicas.

  10. Dissimilar welding in nuclear reactors: review of the main aspects related to dissimilar welding of carbon steel and stainless steel with addition of nickel alloys; Soldas dissimilares em reatores nucleares: revisão dos principais aspectos relacionados à soldagem dissimilar de aço carbono e aço inoxidável com adição de ligas de níquel

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Vladimir Soler

    2015-07-01

    This work presents a review of the literature about Stress Corrosion Cracking, which is one of the main damage mechanisms that affect PWR and BWR type nuclear reactor. It deals with issues related to one of the sources of the problem, which are the trative residual stress caused by the thermal cycle of welding. It also addressed measurement techniques of residual stresses, with emphasis on technique the center hole drilling. It is shown that, once found the problem, there are means to mitigate the damage, which allow prolonging the life of the component. (author)

  11. Quality assessment of radiopharmaceuticals in nuclear medicine services at Northeast states, Brazil

    International Nuclear Information System (INIS)

    Andrade, Wellington Gomes de

    2012-01-01

    The radiopharmaceuticals are used in the field nuclear medicine services (NMS) as tracer in the diagnoses and treatment of many diseases. Radiopharmaceuticals used in nuclear medicine and usually have a minimum of pharmacological effect. The procedures for labelling Radiopharmaceuticals should be observed in order to minimize risks to patients, employees and individuals from the public, and to be administered in humans, must be sterile and free of pyrogens and possess elements all measures of quality controls required a conventional drug. The 'Agencia Nacional de Vigilancia Sanitaria (ANVISA)' in its 'Resolucao de Diretoria Colegiada' (RDC) No. 38 of June 4 th 2008, decided that the NMS must perform quality control in the generators eluate and radiopharmaceuticals according to recommendations of manufacturers and scientific evidence accepted by ANVISA. Thus, this study proposes to evaluate the quality of the generator 99M o- 99m Tc eluate and radiopharmaceuticals labeled with 99m Tc used in most NMS of some states in the Northeast, in relation to radionuclide, chemical, radiochemical purity and pH and promote the inclusion of procedure for quality control of radiopharmaceuticals in routine NMS. The results show that 90% radionuclidic purity, 98.2% purity chemical and radiochemical purity of 46% and 100% of the eluates are in agreement with international pharmacopoeias; already radiopharmaceuticals showed 82.6% purity and all radiochemical pH values are also in accordance with international pharmacopoeias. Even with so many positive results, staff the majority of MNS was not able to perform the quality control of the eluates and radiopharmaceuticals. Showing the importance of implementing of quality control programs of the eluates and radiopharmaceuticals in nuclear medicine. (author)

  12. Evaluation of radiochemistry purity and p H of radiopharmaceuticals in nuclear medicine services at Pernambuco, Brazil

    International Nuclear Information System (INIS)

    Andrade, Wellington; Lima, Fabiana Farias de; Santos, Poliane A.L.; Lima, Fernando Roberto de Andrade; Lima, Fabiana Farias de

    2011-01-01

    Radiopharmaceuticals are cellular or molecular structures that have a radionuclide in its composition and they are used for diagnosing or treating diseases. The evaluation of the radiochemical purity of radiopharmaceuticals is essential to produce images with artifacts free, as well as avoid unnecessary absorbed dose to the patient. Since they are administered in humans is important and necessary that they undergo rigorous quality control. Due to this fact, the norm in ANVISA RDC 38/2008 declaring the mandatory completion of a minimum of tests in routine nuclear medicine services before human administration. (author)

  13. Nuclear geophysics in space and atmospheric reserch at INPE/BRAZIl

    International Nuclear Information System (INIS)

    Nordemann, D.J.R.; Pereira, E.B.; Marinho, E.V.A.; Sircilli Neto, F.

    1986-05-01

    During the last years, INPE's research in Nuclear Geophysics has developed in fields of interest to the Institute, the scientific community and the society in general. In the space research field it may be considered as a contribution to the history of meteorite falls in our planet or possible collision with big meteorites which may have been the cause of important effects such as biological extinction and extraterrestrial matter gathering. In the atmospheric research field, spatial and temporal variations of radon measurements in the lower atmosphere allow correlations from micrometeorology to worlwide scale through mesoscale, in the interpretation of phenomena which deal with the dynamics of air masses. (Author) [pt

  14. Critical evaluation of the external occupational exposure in nuclear medicine services in Brazil; Avaliacao critica da exposicao ocupacional externa nos servicos de medicina nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Kubo, Ana Luiza Silva Lima

    2016-07-01

    Currently in Brazil (2016), there are 421 Nuclear Medicine Services (NMS). In nuclear medicine, the possibility of occupational internal contamination and external exposure is unavoidable. The chest individual monitoring, to estimate the effective dose, is mandatory, but the extremity monitoring is not always made. The aim of this study was to conduct a survey of data for external exposure of NMS professionals in Brazil from 1987 to 2010, analysing them in terms of trends and comparing them with measurements carried out in this work and in other countries. Although most of the NMS is still located in large urban centres (54% in the Southeast region), there is no state without any NMS. The increasing number of NMS has generated the need for more professionals. In the year 1987, they were 755 workers and, in 2010, 4134, with the following distribution of specialties: 29% of Nuclear Medicine Technicians (NMT), 23% of Nursing professionals, 29% of Physicians and 3% of Physicists. The average annual effective dose reached more than 3.0 mSv in some regions of the country, from 1987 to 2010, but tends to 1.0 mSv in 2010. The highest doses, as expected, are received by NMT and Nursing. The professionals who handle radiopharmaceuticals have their hands much more exposed than the chest. During 2010, only 31% of NMT and 16% of Nursing used extremity dosimeters as compared to chest dosimeters. The data from the measurements indicate that not all individual dosimeters are used properly. Generally, both in the measurements as in national registries, the hand doses were higher for professionals who prepared the radiopharmaceutical (NMT) than those who injected (Nursing). The value measured by chest dosimeters can be used to estimate the equivalent dose to the eye lenses, except for NMT at preparation practices at conventional NMS, where the equivalent dose of the lens is about 2 times higher than the dose at the chest. The most exposed areas of the hands are the tips of the index

  15. Effective doses in diagnostic nuclear medicine in Brazil: Possibilities of optimisation

    International Nuclear Information System (INIS)

    Veslasques de Oliveira, S. M.; Tauhata, L.; Lipsztein, J. L.; Boasquevisque, E. M.

    2006-01-01

    With the aim of analysing protection of patient in diagnostic nuclear medicine, this study present data collected from sixteen nuclear medicine public and private institutions in three regions of the country, namely Northeast, Southeast and South regions 26,782 patients protocols were analysed, 24,371 adults and 2,411 children and teen-ages. Myocardial perfusion and bone imaging were responsible, respectively, for 53% and 23% of all diagnostic procedures. For 3.010 adults with age and weight registered, 96% had more than 40 years and mean weight was (69.9±14.1) kg for both genders. Due to similarities in physical characteristics between Brazilian adults patients and ICRP Reference Man, effective doses were estimated using ICRP conversion factors. For adults, the ratio mean activities per mean weigh was higher for female than male for the majority of procedures. For children and teen-ages, this ratio was higher for younger ages. Protocols should consider mean corporal weight for female and activities may be reduced accordingly. For children and teen-ages, effective doses may be reduced for younger ages. High absolved doses in bone surfaces of children due to 67Ga citrate imaging and bone scintigraphies should be investigated. (Author)

  16. Mutual cooperation with Brazil

    International Nuclear Information System (INIS)

    Orstein, Roberto M.

    1998-01-01

    The history of the nuclear cooperation between Brazil and Argentina is outlined in the framework of the changing political circumstances. Reference is made to the agreements between both countries and to its implementation

  17. The role of nuclear emulsions in the institutionalization of research in experimental physics in Brazil; O papel das emulsoes nucleares na institucionalizacao da pesquisa em fisica experimental no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, Cassio Leite [Instituto Ciencia Hoje, Rio de Janeiro, RJ (Brazil); Videira, Antonio A.P. [Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil); Conselho Nacional de Desenvolvimento Cientifico e Tecnologico (CNPq), Brasilia, DF (Brazil)

    2011-07-01

    In this paper, we describe and analyze the introduction and the use of the nuclear emulsions technique in Brazil. Even though consistent researches in cosmic ray physics had been done since the forties of the last century in this country, physicists here only began using this technique after Cesar Lattes' works in Bristol (England) and Berkeley (US). Despite being the implantation of the technique in this country posterior to the origin of the method itself dated from late 1900s, Brazilian scientists were quickly familiarized with it and adopted it not only in cosmic rays, but also in particle physics and nuclear physics, employing it until recently. In our work, we will be concerned with the reasons of this longevity. In other words, why were the nuclear emulsions technique employed for so many years in Brazil, even after its vanishing in physics researches centers in the world? We advance here that the answer to this question involves the institutionalization of science in Brazil mainly physics and economical, social, and geographic reasons. (author)

  18. A critical review of an extremity monitoring program at the Instituto de Engenharia Nuclear in Brazil

    International Nuclear Information System (INIS)

    Fajardo, Patricia Wieland; Rosa, Luiz Antonio Ribeiro da

    1993-01-01

    Eventually the cyclotron of the Instituto de Engenharia Nuclear (IEN) may need maintenance; Its components are made of copper and they become highly activated after irradiations producing extensive 65 Zn sources. The individual monitoring of the maintenance workers is based on film badges and TLD rings. Both systems are calibrated in terms of 'Photon Dose Equivalent' and the extremity dosemeter is not able to discriminate the gamma and beta contributions to the total dose. Conservatively, it was possible to estimate, using another extremity dosemeter, that beta doses received by the workers' hands are three times higher than the gamma doses. Considering this result, and the ring TL responses, it was possible to estimate Hp(0.07), in the case of the hands, for all the IEN cyclotron maintenance workers, since 1983. The results show that Hp(0.07) values are about 2.88 times higher than the previous reported extremity doses in mSv. (author)

  19. A comparison of nuclear power systems for Brazil using plutonium and binary cycles

    International Nuclear Information System (INIS)

    Ishiguro, Y.; Fernandes, J.E.

    1985-01-01

    Nuclear power systems based on plutonium cycle and binary cycle are compared taking into account natural uranium demand and reactor combination. The systems start with PWR type reactors (U5/U8) and change to systems composed exclusively of FBR type reactors or PWR-FBR symbiotic systems. Four loading modes are considered for the PWR and two for the FBR. The FBR is either a LMFBR loaded with PU/U or a LMFBR loaded the binary way. A linear and a non-linear capacity growth and two different criteria for the FBR introduction are considered. The results show that a 100 GWe permanent system can be established in 50 years in all cases, based on 300000 t of natural uranium and in case of delay in the FBR introduction and if a thermal-fast symbiotic system is chosen, a binary cycle could be more advantageous than a plutonium cycle. (F.E.) [pt

  20. Initiating a national program in Brazil for the implementation of quality control procedures for radionuclide ''Dose Calibrators and Scintillation Cameras in Nuclear Medicine''. Final report for the period 1987 -1988

    International Nuclear Information System (INIS)

    Mendes, L.

    1988-01-01

    In 1984 the Nuclear Energy Commission of Brazil and the IAEA established a research programme on Nuclear Medicine Quality Control. The programme will be carried out using educational, technical and clinical means to ensure the quality control of the dose calibrators and scintillation cameras

  1. Interpretation of the results from individual monitoring of workers at the Nuclear Fuel Fabrication Facility, Brazil

    International Nuclear Information System (INIS)

    Castro, Marcelo Xavier de

    2005-01-01

    In nuclear fuel fabrication facilities, workers are exposed to different compounds of enriched uranium. Although in this kind of facility the main route of intake is inhalation, ingestion may occur in some situations, and also a mixture of both. The interpretation of the bioassay data is very complex, since it is necessary taking into account all the different parameters, which is a big challenge. Due to the high cost of the individual monitoring programme for internal dose assessment in the routine monitoring programmes, usually only one type of measurement is assigned. In complex situations like the one described in this study, where several parameters can compromise the accuracy of the bioassay interpretation it is need to have a combination of techniques to evaluate the internal dose. According to ICRP 78 (1997), the general order of preference of measurement methodologies in terms of accuracy of interpretation is: body activity measurement, excreta analysis and personal air sampling. Results of monitoring of working environment may provide information that assists in the interpretation on particle size, chemical form, solubility and date of intake. A group of fifteen workers from controlled area of the studied nuclear fuel fabrication facility was selected to evaluate the internal dose using all different available techniques during a certain period. The workers were monitored for determination of uranium content in the daily urinary and faecal excretion (collected over a period of 3 consecutive days), chest counting and personal air sampling. The results have shown that at least two types of sensitivity techniques must be used, since there are some sources of uncertainties on the bioassay interpretation, like mixture of uranium compounds intake and different routes of intake. The combination of urine and faeces analysis has shown to be the more appropriate methodology for assessing internal dose in this situation. The chest counting methodology has not shown

  2. Determination of the presence of molybdenum-99 in the technetium-99m solutions used at the nuclear medicine services of Recife, Pernambuco, Brazil

    International Nuclear Information System (INIS)

    Sena, Thiago G. de; Souza, Fernanda R. de L.; Lopes Filho, Ferdinand de J.; Vieira, Jose W.; Lima, Fernando R. de A.

    2009-01-01

    The main objective of this work is to calculate the percentage of 99 Mo in the eluates of the 99 mTc used at the nuclear medicine services localized at the Recife city, Pernambuco, Brazil. At the present moment three nuclear medicine services were evaluated verifying the 99 Mo in the eluates of 99 mTc, and in two services, the contamination were superior to the limits stipulated by the international organism adopted as reference in this work. The work follows in other nuclear medicine institutions evaluating and orienting the professionals on these quality control not only for the optimization of the patient dose, but also for the improvement of the image to be used for the diagnostic

  3. Genetic and environmental influences on blood pressure and physical activity: a study of nuclear families from Muzambinho, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Forjaz, C.L.M.; Bartholomeu, T. [Laboratório de Hemodinâmica da Atividade Motora (LAHAM), Escola de Educação Física e Esporte, Universidade de São Paulo, São Paulo, SP (Brazil); Rezende, J.A.S. [Escola Superior de Educação Física de Muzambinho, Muzambinho, MG (Brazil); Oliveira, J.A.; Basso, L.; Tani, G. [Laboratório de Comportamento Motor (LACOM), Escola de Educação Física e Esporte, Universidade de São Paulo, São Paulo, SP (Brazil); Prista, A. [Faculdade de Educação Física e Desporto, Universidade Pedagógica, Maputo (Mozambique); Maia, J.A.R. [CIFI2D, Laboratório de Cineantropometria e Gabinete de Estatística Aplicada, Faculdade de Desporto, Universidade do Porto, Porto (Portugal)

    2012-09-07

    Blood pressure (BP) and physical activity (PA) levels are inversely associated. Since genetic factors account for the observed variation in each of these traits, it is possible that part of their association may be related to common genetic and/or environmental influences. Thus, this study was designed to estimate the genetic and environmental correlations of BP and PA phenotypes in nuclear families from Muzambinho, Brazil. Families including 236 offspring (6 to 24 years) and their 82 fathers and 122 mothers (24 to 65 years) were evaluated. BP was measured, and total PA (TPA) was assessed by an interview (commuting, occupational, leisure time, and school time PA). Quantitative genetic modeling was used to estimate maximal heritability (h{sup 2}), and genetic and environmental correlations. Heritability was significant for all phenotypes (systolic BP: h{sup 2} = 0.37 ± 0.10, P < 0.05; diastolic BP: h{sup 2} = 0.39 ± 0.09, P < 0.05; TPA: h{sup 2} = 0.24 ± 0.09, P < 0.05). Significant genetic (r{sub g}) and environmental (r{sub e}) correlations were detected between systolic and diastolic BP (r{sub g} = 0.67 ± 0.12 and r{sub e} = 0.48 ± 0.08, P < 0.05). Genetic correlations between BP and TPA were not significant, while a tendency to an environmental cross-trait correlation was found between diastolic BP and TPA (r{sub e} = -0.18 ± 0.09, P = 0.057). In conclusion, BP and PA are under genetic influences. Systolic and diastolic BP share common genes and environmental influences. Diastolic BP and TPA are probably under similar environmental influences.

  4. Genetic and environmental influences on blood pressure and physical activity: a study of nuclear families from Muzambinho, Brazil

    Directory of Open Access Journals (Sweden)

    C.L.M. Forjaz

    2012-12-01

    Full Text Available Blood pressure (BP and physical activity (PA levels are inversely associated. Since genetic factors account for the observed variation in each of these traits, it is possible that part of their association may be related to common genetic and/or environmental influences. Thus, this study was designed to estimate the genetic and environmental correlations of BP and PA phenotypes in nuclear families from Muzambinho, Brazil. Families including 236 offspring (6 to 24 years and their 82 fathers and 122 mothers (24 to 65 years were evaluated. BP was measured, and total PA (TPA was assessed by an interview (commuting, occupational, leisure time, and school time PA. Quantitative genetic modeling was used to estimate maximal heritability (h², and genetic and environmental correlations. Heritability was significant for all phenotypes (systolic BP: h² = 0.37 ± 0.10, P < 0.05; diastolic BP: h² = 0.39 ± 0.09, P < 0.05; TPA: h² = 0.24 ± 0.09, P < 0.05. Significant genetic (r g and environmental (r e correlations were detected between systolic and diastolic BP (r g = 0.67 ± 0.12 and r e = 0.48 ± 0.08, P < 0.05. Genetic correlations between BP and TPA were not significant, while a tendency to an environmental cross-trait correlation was found between diastolic BP and TPA (r e = -0.18 ± 0.09, P = 0.057. In conclusion, BP and PA are under genetic influences. Systolic and diastolic BP share common genes and environmental influences. Diastolic BP and TPA are probably under similar environmental influences.

  5. Genetic and environmental influences on blood pressure and physical activity: a study of nuclear families from Muzambinho, Brazil

    International Nuclear Information System (INIS)

    Forjaz, C.L.M.; Bartholomeu, T.; Rezende, J.A.S.; Oliveira, J.A.; Basso, L.; Tani, G.; Prista, A.; Maia, J.A.R.

    2012-01-01

    Blood pressure (BP) and physical activity (PA) levels are inversely associated. Since genetic factors account for the observed variation in each of these traits, it is possible that part of their association may be related to common genetic and/or environmental influences. Thus, this study was designed to estimate the genetic and environmental correlations of BP and PA phenotypes in nuclear families from Muzambinho, Brazil. Families including 236 offspring (6 to 24 years) and their 82 fathers and 122 mothers (24 to 65 years) were evaluated. BP was measured, and total PA (TPA) was assessed by an interview (commuting, occupational, leisure time, and school time PA). Quantitative genetic modeling was used to estimate maximal heritability (h 2 ), and genetic and environmental correlations. Heritability was significant for all phenotypes (systolic BP: h 2 = 0.37 ± 0.10, P < 0.05; diastolic BP: h 2 = 0.39 ± 0.09, P < 0.05; TPA: h 2 = 0.24 ± 0.09, P < 0.05). Significant genetic (r g ) and environmental (r e ) correlations were detected between systolic and diastolic BP (r g = 0.67 ± 0.12 and r e = 0.48 ± 0.08, P < 0.05). Genetic correlations between BP and TPA were not significant, while a tendency to an environmental cross-trait correlation was found between diastolic BP and TPA (r e = -0.18 ± 0.09, P = 0.057). In conclusion, BP and PA are under genetic influences. Systolic and diastolic BP share common genes and environmental influences. Diastolic BP and TPA are probably under similar environmental influences

  6. Adaptation of the QUANUM platform for internal audits in Nuclear Medicine in Brazil

    International Nuclear Information System (INIS)

    Paula, V.M.; Andrade, E.R. de; Sá, L.V. de

    2017-01-01

    Audit is an ongoing review of all processes involving a particular service to ensure that each process is developed systematically and in accordance with specific regulations. The IAEA developed an internal audit process named QUANUM - Quality Management Audits in Nuclear Medicine and available in their website. This tool offers support to management quality audits, assisting teams in the evaluation of quality management system. QUANUM tool was developed based on the European Community guidelines and international recommendations. In order to be better applied in a country, national regulations should be followed not to generate non-conformities. Based on the current legal framework a review was performed under light of the normative items from national regulators which should be in compliance with the international recommendations. Also, national requirements not addressed by international recommendations were considered. Therefore, a single model was designed to meet both requirements, national and international standards and regulations. An Internal Audit model was elaborated helping to quantify risk levels concerned to the process as a whole demonstrating that national regulations meet 0,63 % of the international QUANUM requirements This tool systematizes and improves the quality management policy and, at last, be able to attend the Regulatory Audit, minimizing non-conformities. (author)

  7. Adaptation of the QUANUM platform for internal audits in Nuclear Medicine in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Paula, V.M.; Andrade, E.R. de, E-mail: vitor_moura06@hotmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil); Sá, L.V. de, E-mail: lidia@ird.gov.br, E-mail: fisica.dna@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    Audit is an ongoing review of all processes involving a particular service to ensure that each process is developed systematically and in accordance with specific regulations. The IAEA developed an internal audit process named QUANUM - Quality Management Audits in Nuclear Medicine and available in their website. This tool offers support to management quality audits, assisting teams in the evaluation of quality management system. QUANUM tool was developed based on the European Community guidelines and international recommendations. In order to be better applied in a country, national regulations should be followed not to generate non-conformities. Based on the current legal framework a review was performed under light of the normative items from national regulators which should be in compliance with the international recommendations. Also, national requirements not addressed by international recommendations were considered. Therefore, a single model was designed to meet both requirements, national and international standards and regulations. An Internal Audit model was elaborated helping to quantify risk levels concerned to the process as a whole demonstrating that national regulations meet 0,63 % of the international QUANUM requirements This tool systematizes and improves the quality management policy and, at last, be able to attend the Regulatory Audit, minimizing non-conformities. (author)

  8. Datafile: Brazil

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    There is as yet little to show for the enormous investment made by Brazil over the past 20 years in nuclear power and the fuel cycle. The only nuclear power plant (657MWe PWR) in operation has had a poor performance record and the two reactors (1309MWe PWRs) under construction are more than ten years behind the original schedule. Aspirations of building commercial fuel cycle facilities have proved extremely optimistic. In the latest reorganization of the industry, the construction and operation of nuclear power stations is entrusted to the national utility and the various civilian/military R and D efforts in the fuel cycle are being integrated under civilian supervision. This should lead to greater accountability and efficiency in the future. (author)

  9. Determination of radon-222 concentration in inside environments of the Instituto de Engenharia Nuclear, Brazil

    International Nuclear Information System (INIS)

    Gouvea, Vandir de Azevedo; Cardoso, Domingos d'Oliveira; Castro, Carlos Alberto Carvalho

    2000-01-01

    The gotten concentrations of radon-222 in the installations of the IEN had been determined using the active and passive methods. The active method consisted on the use of the alpha spectrometry with a portable equipment Tracerlab Instruments WLM- Plus. In the determination for the passive method, one used detectors of nuclear strokes of type LEXAN. The raised values had been gotten in the wastes deposit and its annexes, room of the press and laboratory of wastes handling. It was observed, in this sector, an instantaneous measure of alpha spectrometry, concentrations around 1000 Bq.m-3, which had over all to the function of storage, the sector, a great volume of natural radioactive materials, especially of radium-226. This determination was carried through in an extreme situation of ventilation zero, where the gates had been kept closed during the execution of the same one. It was observed, however, a considerable fall, with values ten times inferior, after to submit the environment to a ventilation forced by means of fans and exhaust fans. The results gotten in the alpha spectrometry had been confirmed by the detectors of strokes, over all in that it says respect ace trends of storage of the gas in environments little ventilated. Some suggestions had been made on procedures to be adopted, aiming at the security of the people in these environments. The other places studied in the IEN had been, the room of the Argonauta reactor, laboratories and caves of the Cyclotron, diverse laboratories of the sector of chemistry and rooms of staff. The present study it objectified the establishment of a methodology of inquiry of the radon in occupational areas, besides considering solutions for the minimization of the concentrations of the gas, in similar environments of work to the ones of the IEN

  10. 14CO2 dispersion around two PWR nuclear power plants in Brazil.

    Science.gov (United States)

    Dias, Cíntia Melazo; Stenström, Kristina; Bacelar Leão, Igor Luiz; Santos, Roberto Ventura; Nícoli, Iêda Gomes; Skog, Göran; Ekström, Peter; da Silveira Corrêa, Rosangela

    2009-07-01

    Atmospheric air samples were taken within 3 km from power plants encompassing five different distances and wind directions. Samples were taken between 2002 and 2005 aiming to evaluate the environmental (14)C enrichment due to the operation of Brazilian nuclear power plants. The sampling system consisted of a pump connected to a trapping column filled with a 3M NaOH solution. The trapped CO(2) was analyzed for (14)C by using a single stage accelerator mass spectrometry (SSAMS). All sampling sites revealed measurable (14)C excess values. The maximum excesses were of 15 and 14 mBq/m(3) for sampling sites placed at NE of the power plants, which is the main wind direction in the area. The mean excesses values were 12 mBq/m(3) to the NE direction, 8 mBq/m(3) to the E, 10 mBq/m(3) to the N, 8 mBq/m(3) to the WNW and 7 mBq/m(3) to the W direction (increasing distances from NE to W). Compared to other Light Water Reactors (LWR) data, these means' values are significantly higher than the average worldwide reported value of 3 mBq/m(3). Available data indicate that the observed values are not related to (14)C emission by the power plants vent stack. Other factors, such as topography, seem to have an important role because it affects wind dispersion thus favoring (14)C accumulation in the sampled area. Moreover, the high elevations around the power plants enhance the chances to measure high values of (14)C since the plume can be intercepted before it is drawn to the ground. Modeling of the plume has shown that its dispersion does not follow a Gaussian model and that agreement between atmospheric CO(2) and vegetation (14)C activities occurs only for sampling sites placed at NE of the power plants.

  11. The BSC implanting process in a nuclear research center in Brazil

    International Nuclear Information System (INIS)

    Oliveira, Cezar Augusto de; Guimaraes, Regia Ruth Ramirez; Filgueiras, Sergio Almeida Cunha

    2007-01-01

    The dynamics of the economical development founded due to the markets globalization and also to the increasing of the competition based on innovation, whose leadership belongs to the richest countries, presses for changes and moves the national and regional innovating systems. In a world of constant change, getting along with the external changes became one of the most relevant factors of the organizational success. Knowing and interpreting the external reality; monitoring the transformations; finding the opportunities and being able to answer fast and adequately; neutralize or minimize the threats: these and other abilities are constantly done by the most successful organizations, as part of a structured and conscious process focused on results . The technological research institutes were created in order to support the industries in their effort to overcome the competition by innovating. It is related, in last instance, to be an integrating part of the national or local innovating system, essential to the economical development and also to the improvement of life quality. However, they are put in this mutation atmosphere and fight for adapting to the new premises of the organizational success in order to have their mission fulfilled. In this context, the Development Center for Nuclear Technology - CDTN, makes an effort to adequate its strategically planning, by introducing and adapting the best administrating practices known nowadays. Among them, the Balanced Scorecard - BSC. This paper presents a brief form of each elaborating form of the strategic planning and also of the BSC implantation, it also clears up the level achieved by the organization and discusses the difficulties it faced. (author)

  12. Conflict between constitutional norms: monopoly of nuclear ore and the social function of property in Brazil; Conflito entre normas constitucionais: monopolio do minerio nuclear e a funcao social da propriedade no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Costa-de-Moura, Jorge

    2014-07-01

    This monograph broaches about the conflict existing between the social Constitution of 1988, in relation to what is disposed in the Article 5, XXIII and XXIV, entrenchment clause of immediate application that determines the social function of property in Brazil, and articles 21, XXIII, and 177, V, that stipulate the monopoly of ores containing nuclear elements, i.e., those containing the chemical elements uranium, thorium, and plutonium in economically exploitable amounts. Initially, the work deals with legal definitions for nuclear ore, nuclear policy of some countries, the economical concepts of the social function of property and the negative aspects related to the maintenance of the nuclear ore in the state monopole regime in confrontation with the economic and social interest also expressed in the Constitutional Valance of 1988. Finally, it is presented an actualized compilation of nuclear laws related to the Brazilian nuclear policy and a glossary of terms used in the nuclear policy conducted by the Brazilian Nuclear Regulatory Agency (CNEN). (author)

  13. Liver damages and nuclear abnormalities in erythrocytes of Atherinella brasiliensis (Actynopterigii, Atherinopsidade from two beaches in Southeast of Brazil

    Directory of Open Access Journals (Sweden)

    Welingtom S. Fernandez

    2011-06-01

    Full Text Available There are few environmental studies using biomarkers for the species Atherinella brasiliensis in Brazil. In the present work, the presence of hepatic histopathological lesions and nuclear abnormalities in erythrocytes were investigated in A. brasiliensis from Lamberto, a beach under influence of domestic wastes and marine activities. For comparison, fish were also sampled in Puruba, a non-polluted beach, located in the northeastern of São Paulo State. The frequency of lesions found in liver was in higher numbers in individuals from Lamberto than Puruba beach. The most critical injuries observed in A. brasiliensis were the presence of necrotic areas, leucocytes infiltration and piknotic nucleus. A high occurrence of cells with vacuolization was also observed. The hepatic lesion index of the fish from Lamberto beach showed significant high values (Iorg=13 when compared with fish from Puruba beach (Iorg=7 suggesting the influence of the several human activities in the studied site. Notched and blebed nucleous were observed in this study, and significant differences were found between the studied sites. However, these differences did not reflect the total nuclear alterations.Existem poucos estudos no Brasil usando biomarcadores em Atherinella brasiliensis. No presente trabalho foram investigadas a presença de lesões histopatológicas hepáticas e as alterações nucleares em eritrócitos de A. brasiliensis amostrados na praia do Lamberto, local submetido à influência de resíduos domésticos e atividades humanas. Para comparação, indivíduos da espécie foram também amostrados na praia de Puruba, local não impactado, localizado no noroeste do estado de São Paulo. Peixes provenientes da praia do Lamberto apresentaram lesões hepáticas em número maior do que aqueles da praia de Puruba. Áreas necróticas, infiltração de leucócitos e núcleos picnóticos foram os danos de maior importância observados em A. brasiliensis, apesar de uma

  14. The TERRA project, a space nuclear micro-reactor case study

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Lamartine N.F.; Nascimento, Jamil A.; Borges, Eduardo M.; Lobo, Paulo D. Castro, E-mail: guimarae@ieav.cta.br, E-mail: jamil@ieav.cta.br, E-mail: eduardo@ieav.cta.br [Divisao de Energia Nuclear. Instituto de Estudos Avancados, Sao Jose dos Campos, SP (Brazil); Placco, Guilherme M.; Barrios Junior, Ary G. [Faculdade de Tecnologia Sao Francisco (FATESF), Jacarei, SP (Brazil)

    2011-07-01

    The TEcnologia de Reatores Rapidos Avancados project, also known as TERRA Project is been conducted by the Institute for Advanced Studies IEAv. The TERRA project has a general objective of understanding and developing the key technologies that will allow (Brazil) the use of nuclear technology to generate electricity in space. This electricity may power several space systems and/or a type of plasma based engine. Also, the type of reactor intended for space may be used for power generation in very inhospitable environment such as the ocean floor. Some of the mentioned technologies may include: Brayton cycles, Stirling engines, heat pipes and its coupled systems, nuclear fuel technology, new materials and several others. Once there is no mission into which apply this technology, at this moment, this research may be conducted in many forms and ways. The fact remains that when this technology becomes needed there will be no way that we (Brazilians) will be able to buy it from. This technology, in this sense, is highly strategic and will be the key to commercially explore deep space. Therefore, there is the need to face the development problems and solve them, to gain experience with our own rights and wrongs. This paper will give a brief overview of what has been done so far, on experimental facilities and hardware that could support space system development, including a Brayton cycle test facility, Tesla turbine testing, and Stirling engine development and modeling. Our great problem today is lack of human resources. To attend that problem we are starting a new graduate program that will allow overcoming that, given the proper time frame. (author)

  15. The TERRA project, a space nuclear micro-reactor case study

    International Nuclear Information System (INIS)

    Guimaraes, Lamartine N.F.; Nascimento, Jamil A.; Borges, Eduardo M.; Lobo, Paulo D. Castro; Placco, Guilherme M.; Barrios Junior, Ary G.

    2011-01-01

    The TEcnologia de Reatores Rapidos Avancados project, also known as TERRA Project is been conducted by the Institute for Advanced Studies IEAv. The TERRA project has a general objective of understanding and developing the key technologies that will allow (Brazil) the use of nuclear technology to generate electricity in space. This electricity may power several space systems and/or a type of plasma based engine. Also, the type of reactor intended for space may be used for power generation in very inhospitable environment such as the ocean floor. Some of the mentioned technologies may include: Brayton cycles, Stirling engines, heat pipes and its coupled systems, nuclear fuel technology, new materials and several others. Once there is no mission into which apply this technology, at this moment, this research may be conducted in many forms and ways. The fact remains that when this technology becomes needed there will be no way that we (Brazilians) will be able to buy it from. This technology, in this sense, is highly strategic and will be the key to commercially explore deep space. Therefore, there is the need to face the development problems and solve them, to gain experience with our own rights and wrongs. This paper will give a brief overview of what has been done so far, on experimental facilities and hardware that could support space system development, including a Brayton cycle test facility, Tesla turbine testing, and Stirling engine development and modeling. Our great problem today is lack of human resources. To attend that problem we are starting a new graduate program that will allow overcoming that, given the proper time frame. (author)

  16. Results of solid state nuclear track detector technique application in radon detection, by alpha particles tracks, for uranium prospecting in Caetite (BA-Brazil)

    International Nuclear Information System (INIS)

    Moraes, M.A.P.V. de; Khouri, M.T.F.C.

    1988-11-01

    The solid state nuclear track detector technique has been used in radon detection, by alpha particles tracks for uranium prospecting on the ground in Caetite city (Bahia-Brazil). The sensitive film to alpha particles used were CA 8015 exposed during 15 days and the results of three anomalies of this region are showed in a form of maps, made with the density of tracks obtained, and were compared with scintillation counter measurements. The technique showed to be simple and an effective auxiliary for the prospection of uranium ore bodies. The initial uranium exploration costs can be reduced by using this technique. (author) [pt

  17. Desenvolvimento de um sensor por software para avaliação de biomassa em reatores anaeróbios

    OpenAIRE

    Rodríguez, Jaime Eduardo Navarrete

    2003-01-01

    Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnológico. Programa de Pós-Graduação em Engenharia Química. Um sensor por software para a determinação da concentração de biomassa em reatores anaeróbicos, em regime acetoclástico é apresentado. O sensor por software é baseado em medições de pressão do sistema experimental e um observador de estados não linear. O projeto do observador de estados é realizado a partir dos balanços de massa das espécies químicas e bioló...

  18. Reactor network synthesis for isothermal conditions = Síntese de redes de reatores para condições isotérmicas

    Directory of Open Access Journals (Sweden)

    Lincoln Kotsuka da Silva

    2008-07-01

    Full Text Available In the present paper, a computational systematic procedure for isothermal Reactor Network Synthesis (RNS is presented. A superstructure of ideal CSTR and PFR reactors is proposed and the model is formulated as a constrained Nonlinear Programming (NLP problem. Complex reactions (series/parallel reactions are considered. The objective function is based on yield or selectivity, depending on the desired product, subject to different operational conditions. The problem constraints are mass balances in the reactorsand in the considered reactor network superstructure. A systematic computational procedure is proposed and a Genetic Algorithm (GA is developed to obtain the optimal reactor arrangement with the maximum yield or selectivity and minimum reactor volume. Results are as good as or better than those reported in the literature.No presentetrabalho apresenta-se um procedimento computacional para síntese de redes de reatores (SRR operando em condições isotérmicas. Uma superestrutura de rede de reatores formada por reatores ideais CSTR e PFR é proposta e o problema apresenta uma formulação de programação não linear (PNL. São consideradas reações complexas (série/paralelas. A função objetivo é baseada no rendimento ou na seletividade em relação ao produto desejado, sujeito a diferentes condições de operação. As restrições ao problema são provenientes dos balanços de massa e da configuração da superestrutura considerada.No procedimento computacional é proposto um Algoritmo Genético (AG para obtenção do arranjo ótimo de reatores com máximo rendimento ou seletividade com menor volume reacional. Os resultados obtidos são condizentes com os obtidos na literatura.

  19. Neutron radiography in Brazil

    International Nuclear Information System (INIS)

    Rogers, J.D.

    1983-01-01

    Neutron radiography studies being carried out in reactor centres in Brazil are discussed. These research projects are under way using the 5 MW swimming pool reactor at the Institute of Energy and Nuclear Research (IPEN) in Sao Paulo and the Argonaut reactor at the Institute of Nuclear Engineering (IEN) in Rio de Janeiro. (Auth.)

  20. Eficiência de lagoas de polimento no pós-tratamento de reator UASB no tratamento de águas residuárias de suinocultura

    Directory of Open Access Journals (Sweden)

    A.C.A. Pinto

    2014-04-01

    Full Text Available Avaliou-se o desempenho de um sistema de lagoas seriadas que recebeu efluentes de reator UASB, no tratamento de águas residuárias de suinocultura. O sistema foi composto de reator anaeróbio de chicanas (RAC, reator UASB, em escala real, e uma série de lagoas (uma lagoa facultativa e três de maturação, em escala piloto. As análises físico-químicas realizadas foram: pH, demanda bioquímica de oxigênio (DBO, demanda química de oxigênio (DQO, sólidos suspensos totais (SST, sólidos suspensos voláteis (SSV, nitrogênio amoniacal (N-am., fósforo total (Pt, coliformes totais (CT e Escherichia coli (EC. As lagoas de pós-tratamento contribuíram eficientemente para remoção de nutrientes, matéria orgânica e sólidos, fornecendo um efluente com qualidade para o reuso agrícola ou lançamento em corpos d'água.

  1. Simulação computacional do processamento catalítico do glicerol em reator de leito gotejante para a obtenção 1,2-propanodiol e etilenoglicol

    OpenAIRE

    MELO, Rafael Araújo

    2015-01-01

    O uso de sistemas contínuos é extensivamente empregado na indústria química uma vez que essa prática acarreta em processos mais eficientes que os descontínuos. No patamar atual, a reação de hidrogenólise do glicerol foi conduzida em reatores descontínuos do tipo leito de lama, tais reatores são indicados apenas para uso em produções em baixa escala como laboratórios e pequenas unidades industriais. Esse trabalho visou à possibilidade da implantação desta reação em reator de leito gotejante (c...

  2. Annual report 2001. ABACC 10 years - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, RJ, Brazil

    International Nuclear Information System (INIS)

    2001-01-01

    This document represents the 2001 Annual report. ABACC 10 years - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials during the year of 2000, covering safeguards, accounting and control of nuclear materials

  3. Annual report 2000. ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, RJ, Brazil

    International Nuclear Information System (INIS)

    2000-01-01

    This document reports the general activities of the ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials during the year of 2000, covering safeguards, accounting and control of nuclear materials

  4. Annual report 2004 of ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, RJ, Brazil

    International Nuclear Information System (INIS)

    2004-01-01

    This document reports the general activities of the ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials during the year of 2004, covering safeguards, accounting and control of nuclear materials

  5. 18F-fluorocholine production at Center of Nuclear Technology Development, Brazil: synthesis and in vitro cytotoxicity studies

    International Nuclear Information System (INIS)

    Costa, Flavia Mesquita

    2014-01-01

    18 F-fluorocholine ( 18 FCH) is promising biomarker for imaging of tumors using PET technology, being effective in the diagnosis of metastatic tumors and specific for the brain tumors, prostate, lung, among others. Despite already being used in some countries like France, Germany, Slovenia, Poland, Romania and Portugal, the 18 FCH is not yet produced or marketed in Brazil. This work proposed the development of a new radiopharmaceutical based on choline labeled with 18 F isotope for diagnostic PET imaging which is an increasing demand of the nuclear medicine national. It was also proposed the development of quality control assays in order to evaluate the radiopharmaceutical prior to its use in patients; in vitro test of toxicity in non-tumor cells (MRC-5), evaluating possible changes in cell proliferation caused by radiopharmaceutical impurities; and, to test the interaction's saturation of 18 FCH with the tumor cells (PC-3 and U-87) and the competition with HC-3 and DMAE, performed to characterize the efficiency of the radiotracer uptake by tumor cells that express the choline transporter CHT. 18 FCH was synthesized in two main steps, first by reaction with dibromomethane with fluoride-18, assisted by Kryptofix2.2.2, forming 18 F-fluorobromomethane ( 18 FBrCH 2 ) and, then, the 18 FBrCH 2 reacted with the second precursor DMAE generating the final product, 18 FCH. Synthesis duration was 45 minutes. 18 FCH was obtained in 4.68 - 8.32% radiochemical yield, radiochemical purity greater than 99% and it was stable for up to 8 hours after production. The tested analytical methodologies were suitable for routine use in the quality control of 18 FCH. The evaluation of the cytotoxic potential of impurities 18 FCH, by clonogenic assay, showed that at the concentrations evaluated, the components do not alter the proliferative capacity of human healthy cells. The interaction of 18 FCH with cell lines was saturable, with specific binding greater than 94%, attesting to the

  6. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the application of safeguards

    International Nuclear Information System (INIS)

    2000-01-01

    The document reproduces the text of the Exchange of Letters concerning an agreement with the Federative Republic of Brazil in connection with the Treaty on the Non-Proliferation of Nuclear Weapons and the Treaty for the Prohibition of Nuclear Weapons in Latin America and the Caribbean. The agreement reflected in the Exchange of Letters was approved by the Board of Governors on 20 September 1999, and entered into force on that date

  7. Radiometric analysis performed by the Environment Monitoring Service from IPEN (Institute of Energy and Nuclear Research), Brazil, between 1988 and 1991; Analises radiometricas realizadas pelo Servico de Monitoracao Ambiental do IPEN de 1988 a 1991

    Energy Technology Data Exchange (ETDEWEB)

    Venturini, L; Nisti, M B; Pecequilo, B R.S.

    1993-03-01

    This report presents the radiometric analyses made by the Environmental Monitoring Service from the Institute of Energy and Nuclear Research (IPEN), Brazil, in the period 1988-1991. The experimental procedures, the products analysed and their respective quantities are described. (F.E.). 11 refs, 3 tabs.

  8. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the applications of safeguards

    International Nuclear Information System (INIS)

    1998-01-01

    The document reproduces the text of an Agreement by exchange of letters with the Federative Republic of Brazil in connection with the Treaty for the Prohibition of Nuclear Weapons in Latin America and the Caribbean. The agreement reflected in the Exchange of Letters was approved by the Board of Governors on 10 June 1997 and entered into force on that date

  9. Determinação das espécies de cromo nas cinzas da incineração de couro wet-blue em reatores de leito fixo e leito fluidizado

    OpenAIRE

    Clauren Moura Martins

    2001-01-01

    Este trabalho tem como objetivo a determinação quantitativa da concentração de cromo (III, VI e total) nas cinzas de serragem de couro wet-blue, incineradas em reatores de leito fixo nas temperaturas de 450, 550 e 650 C e reator de leito fluidizado nas temperaturas de 730, 780, 830 e 850 C, verificando se estes resultados estão dentro dos limites permitidos pelas normas ambientais brasileiras e, consequentemente, se em relação à concentração de cromo, os processos de incineração utilizados sã...

  10. Tratamento de resíduos sólidos de centrais de abastecimento e feiras livres em reator anaeróbio de batelada Treatment of solid waste from supply centers and free markets in batch anaerobic reactor

    Directory of Open Access Journals (Sweden)

    Valderi D. Leite

    2003-08-01

    Full Text Available Em feiras livres e centrais de abastecimento são produzidas quantidades bastante significativas de resíduos sólidos, com características favoráveis ao aproveitamento integral em processo de bioestabilização anaeróbia. O processo de bioestabilização é realizado em reatores anaeróbios de batelada (RAB, com tempo de detenção de sólidos variando de 250 a 300 dias originando, como produtos finais, o biogás, com cerca de 60% de gás metano, além de composto orgânico parcialmente bioestabilizado. Neste trabalho, foram utilizados resíduos sólidos orgânicos tipicamente vegetais, advindos de centrais de abastecimento, feiras livres e lodo de esgoto sanitário. O sistema experimental utilizado era constituído basicamente por um reator anaeróbio de batelada, com capacidade unitária de 2200 litros, além de outros dispositivos complementares. O sistema experimental foi instalado e monitorado na Estação Experimental de Tratamento Biológico de Esgoto Sanitário, situada no Bairro do Tambor, na cidade de Campina Grande, Estado da Paraíba, no período de janeiro a setembro de 2001. No processo de monitoração foram realizadas caracterizações sistemáticas das frações sólidas, líquidas e gasosas. Após análise dos dados, ficou evidenciada a viabilidade desta alternativa de tratamento, restando ser investigada ainda a viabilidade econômica, quando comparada com outras alternativas tecnológicas de tratamento de resíduos sólidos orgânicos.Significant quantity of organic solid waste with favorable characteristics for integral utilization in anaerobic biostabilization is produced in free markets and supply centers. The process is conducted in anaerobic batch reactors (ABR, with detention time of solids varying from 250 to 300 days, producing biogas with about 60% of methane, besides the partially biostabilized organic compost as the final product. In this study, the organic solid waste used was typically of vegetables

  11. Communication from the Permanent Missions of Brazil and Romania to the International Atomic Energy Agency Regarding Guidelines for the Transfers of Nuclear-Related Dual-Use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2003-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbale from the Permanent Missions of Brazil and Romania, dated 28 February 2003, providing information on the export policies and practices of the Governments of Brazil and Romania with respect to the export of nuclear-related dual-use equipment, materials, software and related technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbale is attached. The attachment referenced in the Note Verbale was issued previously as INFCIRC/254/Rev.5/Part 2

  12. Effects of the regulatory inspections on nuclear medicine services executed by the Radioprotection and Dosimetry Services, Brazil

    International Nuclear Information System (INIS)

    Alves, C.E.G.R.; Farias, C.; Azevedo, E.M.; Nanni, G.J.; Vasconcellos, L.; Mendes, L.C.G.; Souza, L.A.C.; Franca, W.F.L.; Goncalves, M.

    2005-01-01

    The advances in the Nuclear Medicine auditing field performed by Nuclear Medicine Group of the Radiotherapy and Nuclear Medicine Division of the Institute of Radiation Protection and Dosimetry are shown. The main aspects observed during the auditing are presented as well as the evolution of the non-conformities. Its is also shown that the occurrence of these non-conformities decreases year by year, primarily as a function of the severity of the auditing and the consciousness of the personal of Nuclear Medicine Services. Results point clearly to the importance of the coercion actions to guarantee a radiation protection level in compliance with the standards established by the Brazilian Nuclear Energy Commission. (author)

  13. The role of the IPR-R1 TRIGA Mark I research reactor in nuclear education and training in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Andrea V.; Mesquita, Amir Z.; Maretti Junior, Fausto; Souza, Rose Mary G.P.; Dalle, Hugo M.; Paiano, Silvestre, E-mail: avf@cdtn.br, E-mail: amir@cdtn.br, E-mail: fmj@cdtn.br, E-mail: souzarm@cdtn.br, E-mail: dallehm@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The revival of the Brazilian nuclear program has anticipated a large demand for training in nuclear technology. The Nuclear Technology Development Center (CDTN), a research institute of the Brazilian Nuclear Energy Commission (CNEN), offers the Operator Training Course on Research Reactors (CTORP). This course has existed since 1974 and about 258 workers were certificated by CTORP. This article describes the activities of CTORP and presents a proposal for its activities expansion in order to provide the current demand in the nuclear technology. Experimental research projects programs would be created in the postgraduate course at CDTN. In addition to the normal reactor physics topics addressed by CTORP, new subjects such as thermal hydraulic and instrumentation should be added and discussed too. (author)

  14. The role of the IPR-R1 TRIGA Mark I research reactor in nuclear education and training in Brazil

    International Nuclear Information System (INIS)

    Ferreira, Andrea V.; Mesquita, Amir Z.; Maretti Junior, Fausto; Souza, Rose Mary G.P.; Dalle, Hugo M.; Paiano, Silvestre

    2011-01-01

    The revival of the Brazilian nuclear program has anticipated a large demand for training in nuclear technology. The Nuclear Technology Development Center (CDTN), a research institute of the Brazilian Nuclear Energy Commission (CNEN), offers the Operator Training Course on Research Reactors (CTORP). This course has existed since 1974 and about 258 workers were certificated by CTORP. This article describes the activities of CTORP and presents a proposal for its activities expansion in order to provide the current demand in the nuclear technology. Experimental research projects programs would be created in the postgraduate course at CDTN. In addition to the normal reactor physics topics addressed by CTORP, new subjects such as thermal hydraulic and instrumentation should be added and discussed too. (author)

  15. 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)

  16. 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)

  17. AVALIAÇÃO DE UM REATOR BIOLÓGIGO ROTATIVO DE CONTATO (RBC) APLICADO AO TRATAMENTO DE EFLUENTE DE UM ABATEDOURO DE SUÍNOS E AVES.

    OpenAIRE

    Bervey Schwerz

    2012-01-01

    Com a expansão da sociedade industrial, se iniciou uma geração de resíduos de forma intensa, surgindo uma questão latente, referente a destinar-se corretamente todos os resíduos gerados durante o processo industrial. Mais especificamente, o processamento de carne gera durante suas inúmeras etapas uma enorme vazão de efluentes líquidos. Uma alternativa para o tratamento deste tipo de resíduo são os reatores de biodiscos. Este trabalho tem por objetivo a construção e aplicação...

  18. 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

    International Nuclear Information System (INIS)

    Mattos, Luis Antonio Terribile de

    2013-01-01

    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)

  19. 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)

  20. Definition of criteria related to occupational exposure for use in multi-criteria decision making process for nuclear accidents in Brazil

    International Nuclear Information System (INIS)

    Silva, Diogo N.G.; Guimaraes, Jean R.D.; Rochedo, Elaine R.R.

    2013-01-01

    After the occurrence of nuclear or radiological accidents, the selection of strategies for remediation of contaminated areas and of protective measures for members of public should be based on previously established criteria. Hence, it becomes possible to reduce the stress of population and to prevent the exposure of workers, especially if an implemented measure is not effective in reducing doses for each particular situation. When an accident with radioactive material causes environmental contamination, decisions about remediation of affected areas are complex because there are many factors associated with decontamination processes. Such complexity is related to technical procedures, public acceptance, the feasibility of implementing the measure, costs and legal aspects. This work is part of a project which aims to develop a multi-criteria tool to provide support for decision making processes in cases of nuclear or radiological accidents in Brazil. Primarily, a database containing information about protective and remediation measures for contaminated areas which can be applied nationally was created. Some criteria have already been defined for the classification of these measures regarding aspects of relevance of pathways to public exposure and of the infrastructure necessary to implement the measure. In this paper, the issues related to the exposure of the workforce are assessed and compared to the dose averted to members of the public resulting from the implementation of each remediation procedure. The procedures described in the database are then ranked according to selected criteria. In the next step, these ratings will be incorporated by the multi-criteria tool. (author)

  1. Evaluation of the influence of percent labeling of 99mTc-MIBI on nuclear medicine procedures in Recife, Pernambuco State, Brazil

    International Nuclear Information System (INIS)

    Pereira, Jucilene Maria

    2003-08-01

    The aim of this work was to evaluate the influence of percent labeling of the radiopharmaceutical 99m Tc-MIBI on the procedures adopted by the nuclear medicine clinics in Recife, Pernambuco State, Brazil, and their possible interference with image quality in myocardial perfusion examinations. This work was performed at two nuclear medicine services in Recife that use pharmaceuticals provided by two different manufacturers: Cardiolite, provided by Dupont and Cardiosyd, provided by SYDMA. The pH, percent labeling and stability of samples of 99m Tc-MIBI and the percent uptake in heart and liver of a number of patients were evaluated. The results showed that the pH values measured in all samples of both radiopharmaceuticals were within the limits recommended. In 48% of the Cardiolite samples, the percent labeling was less than 90%, which is the minimum recommended limit. On the other hand, 87,5% of the Cardiosyd samples measured values above 98%. Both radiopharmaceuticals had good labeling stability, even in samples with low percent labeling efficiencies. In spite of the higher percent labeling of Cardiosyd its heart uptake is similar to that observed with the Cardiolite, even when the percent labeling is lower than 90%. On the other hand, the image quality, according to physicians, evaluation was poorer for Cardiosyd images, due to high noise and poor sharpness. (author)

  2. Definition of criteria related to occupational exposure for use in multi-criteria decision making process for nuclear accidents in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo N.G.; Guimaraes, Jean R.D., E-mail: dneves@biof.ufrj.br, E-mail: jeanrdg@biof.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto de Biofisica Carlos Chagas Filho; Rochedo, Elaine R.R., E-mail: elainerochedo@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2013-07-01

    After the occurrence of nuclear or radiological accidents, the selection of strategies for remediation of contaminated areas and of protective measures for members of public should be based on previously established criteria. Hence, it becomes possible to reduce the stress of population and to prevent the exposure of workers, especially if an implemented measure is not effective in reducing doses for each particular situation. When an accident with radioactive material causes environmental contamination, decisions about remediation of affected areas are complex because there are many factors associated with decontamination processes. Such complexity is related to technical procedures, public acceptance, the feasibility of implementing the measure, costs and legal aspects. This work is part of a project which aims to develop a multi-criteria tool to provide support for decision making processes in cases of nuclear or radiological accidents in Brazil. Primarily, a database containing information about protective and remediation measures for contaminated areas which can be applied nationally was created. Some criteria have already been defined for the classification of these measures regarding aspects of relevance of pathways to public exposure and of the infrastructure necessary to implement the measure. In this paper, the issues related to the exposure of the workforce are assessed and compared to the dose averted to members of the public resulting from the implementation of each remediation procedure. The procedures described in the database are then ranked according to selected criteria. In the next step, these ratings will be incorporated by the multi-criteria tool. (author)

  3. Desenvolvimento e operação de reator anaeróbio de manta de lodo (UASB no tratamento dos efluentes da suinocultura em escala laboratorial Development and operation of an upflow anaerobic sludge blanket reactor (UASB treating liquid effluent from swine manure in laboratory scale

    Directory of Open Access Journals (Sweden)

    Cláudio Milton Montenegro Campos

    2006-02-01

    Full Text Available A atividade suinícola vem, desde meados da década de 70, sendo uma das mais poluidoras atividades agroindustriais no Estado de Minas Gerais. Sendo assim, objetivou-se desenvolver um Reator Anaeróbio de Manta de Lodo (UASB-Upflow Anaerobic Sludge Blanket visando tratar os dejetos produzidos com máxima eficiência dentro de um tempo e com custo reduzidos. Para tanto um experimento em escala laboratorial foi projetado e monitorado no Laboratório de Análise de Água do Departamento de Engenharia da Universidade Federal de Lavras (LAADEG, sendo composto por um Tanque de Acidificação e Equalização (TAE, um Reator Anaeróbio de Manta de Lodo e uma Lagoa Aerada Facultativa (LAF, o qual foi alimentado com fluxo contínuo. As análises físico-químicas realizadas foram: DQO, DBO5, Sólidos Totais (Fixos e Voláteis, Temperatura, pH, Nitrogênio, Fósforo, Acidez e Alcalinidade Total. O sistema proporcionou eficiência de remoção média de 93% de DQO, 84% de DBO5 e 85% de Sólidos Totais Voláteis, demonstrando adequada adaptação aos diversos tempos de detenção hidráulica adotados (55, 40, 30, 25, 18 e 15 horas. Os parâmetros adotados na partida do reator UASB foram: COV: 1,11kgDQO.m-3.d-1, COB: 0,019 kgDBO5.kgSVT-1.d-1 e TDH: 55h.The swine production, since 70th , is one of the most pollutant agro-industrial activities in the Minas Gerais State, Brazil. The objective of this research was to develop an Upflow Anaerobic Sludge Blanket Reactor (UASB, aiming at treating the effluent generated within a maximum efficiency and minimum time and cost. Therefore, a lab-scale reactor was built up and monitored in the laboratory of Engineering Department at the Federal University of Lavras (UFLA. The system consisted of an Acidification and Equalization Tank (AET, an Upflow Anaerobic Sludge Blanket reactor (UASB, and an Aerated Facultative Pond (AFP. The system was fed continuously. The physical-chemical analyses carried out were: COD, BOD5, Total

  4. Nuclear energy and environment

    International Nuclear Information System (INIS)

    Alves, R.N.

    1987-01-01

    A general view about the use of energy for brazilian development is presented. The international situation of the nuclear field and the pacific utilization of nuclear energy in Brazil are commented. The safety concepts used for reactor and nuclear facilities licensing, the environmental monitoring program and radiation protection program used in Brazil are described. (E.G.) [pt

  5. Estimation of environmental radiological implications arising from the operation of the Nuclear Engineering Institute - IEN, locate at Fundao Island, Rio de Janeiro, RJ, Brazil

    International Nuclear Information System (INIS)

    Peres, Sueli da Silva

    1999-07-01

    The Nuclear Engineering Institute is located at the Fundao Island in the City of the Rio de Janeiro, Brazil. The Institute works in several fields such as reactors, physics, radiation protection and radioactive waste management, instrumentation and control, chemistry and metallurgy. It has a nuclear installation, represented by the Argonauta reactor, and the other installations are classified as radioactive. During the operation of these installations, some radioactive liquid and gaseous effluents are generated and released into the sanitary sewerage system and in the atmosphere, respectively. The main radioactive effluents are generated during the radioisotopes production and processing. The critical radionuclides released by Institute, in the period covered by this work, from 1985 to 1995, were 65 Zn and 123 l, respectively for the aquatic and atmospheric pathways. This study has shown that the main radiation exposure pathways to man were the inhalation of 123 l contaminated plume and external exposure to the 65 Zn contaminated sewage sludge - coming from the final treatment of the liquid effluents at the Sewage Treatment Plant - in the Sanitary landfilling. Considering the conditions of operation studied, the individual equivalent doses received by the critical groups of the population did not exceed 1/500 of the annual limit of 1 mSv.ano -1 established by the Brazilian Nuclear Energy Commission for the members of the public. These values do not represent any significant radiological risk increase for the local population. Therefore, the exposure calculated in this work, 2 (μSv.year -1 , can be considered acceptable. However, any future dose increment should be carefully evaluated in terms of cost-benefit analysis, according to the system of dose limitation established in the national rules and in the recommendations of the ICRP. (author)

  6. Survey or quality for radiopharmaceuticals and activimeters available in services of nuclear medicine from Recife, Pernambuco State, Brazil; Estudo da qualidade dos radiofarmacos e dos activimetros utilizados nos servicos de medicina nuclear do Recife

    Energy Technology Data Exchange (ETDEWEB)

    Nogueira, Fernanda Maria Dornellas Camara

    2001-08-01

    The radiopharmaceutical used in Nuclear Medicine must present high chemical and radiochemical purities in order to obtain images with contrast and clearness adequate for the diagnosis. Test should be made by the Nuclear Medicine institutes to evaluate the presence of molybdenum, aluminium and the free Tc O{sub 4}{sup -}/TC-HR in the radiopharmaceutical before they use it. On the other hand, the activity to be administered to the patient is determined by the activimeters available in the Nuclear Medicine institutions. So it is necessary to perform tests to verify operating conditions of the activimeter to guarantee that the dose received by patient is the prescribed by the physician. In Brazil, few clinics of Nuclear Medicine are implanting the tests of the radiopharmaceutical and of the activimeters. The objective of this work is to establish the procedures for the radiopharmaceutical tests and to evaluate the quality of the radiopharmaceutical used at the clinics of Recife, as well as the operation conditions of the activemeters in these institutions. The results show that all the activimeters analyzed present a good performance and that the equipment with Geiger-Muller detectors present larger instability than the ones that use ionization chamber. Concerning the Mo/Tc generators, it was observed that only one presented Mo in the generator eluate with concentration over the acceptable limits and that the concentration of Al found in the samples analyzed were below the limits. On the other hand, in 73% of the MIBI analyzed samples were observed problems with its preparation that were caused by the procedures adopted at the clinics, which do not follow the manufacturers recommendations. (author)

  7. Protocol to suspend the application of safeguards pursuant to the Agreement of 26 February 1976 between the Agency, the Government of the Federative Republic of Brazil and the Government of the Federal Republic of Germany in the light of the provisions for the application of safeguards pursuant to the Quadripartite Safeguards Agreement between Argentina, Brazil, the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials and the IAEA

    International Nuclear Information System (INIS)

    1999-01-01

    The document reproduces the text of the Protocol of 16 October 1998 suspending the application of safeguards under the Safeguards Agreement (INFCIRC/237) of 26 February 1976 between the Agency, Brazil and the Federal Republic of Germany in the light of the provisions for the application of safeguards pursuant to the Quadripartite Safeguards Agreement between the Agency, Brazil, the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials and the IAEA. The Protocol entered into force on 21 October 1999

  8. Radiometric survey of Radon-222 in Instituto de Engenharia Nuclear - IEN/CNEN-Brazil; Levantamento de radonio-222 no Instituto de Engenharia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gouvea, Vandir de Azevedo; Cardoso, Domingos d' Oliveira; Pedro, Carlos Roberto [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil). Div. de Seguranca e Radioprotecao]. E-mail: vandir@cnen.gov.br; Castro, Carlos Alberto Carvalho [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Dept. de Engenharia Nuclear

    2001-07-01

    The radioecological concentrations of Radon-222 indoor and outdoor nuclear facility of IEN, have been determined.The present study has established a radon investigation methodology in occupational areas, besides to suggest solutions for gas concentration minimization, in others work environment like to IEN.

  9. Tratamento de efluente sintético de laticínio em reatores em batelada inoculados com Aspergillus niger AN400

    Directory of Open Access Journals (Sweden)

    Luana Viana Costa e Silva

    2013-12-01

    Full Text Available Indústrias de laticínios contêm elevada concentração de matéria orgânica que podem causar poluição. Este trabalho propôs estudar a remoção de matéria orgânica e de nutrientes de um efluente sintético de laticínio, disposto em reatores em bateladas repetidas inoculados com Aspergillus niger AN400. O sistema foi composto por reatores com diferentes configurações e, para cada tipo de montagem, variou-se o material-suporte. O estudo foi realizado em quatro ciclos de cinco dias, com retiradas diárias de alíquotas. A análise dos resultados mostrou eficiência de remoção de demanda química de oxigênio com picos de até 71,7%, concluindo-se que a tecnologia mostrou-se viável na remoção de matéria orgânica. Em relação aos nutrientes, o sistema pôde remover satisfatoriamente nitrato; contudo, para remoção de amônia, não se apresentou promissor.

  10. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards

    International Nuclear Information System (INIS)

    1994-03-01

    The text of the Agreement (and the Protocol thereto) between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards is reproduced in this document for the information of all Members. The Agreement was approved by the Agency's Board of Governors on 7 December 1991 and signed in Vienna on 13 December 1991

  11. Main Activities to Improve the Control of Radioactive Sources and Maintain an Effective Regulatory Nuclear Systems in Brazil

    International Nuclear Information System (INIS)

    Marechal, M.H.

    2016-01-01

    Since 2006, the Directorate of Nuclear Safety and Security, DRS, of National Nuclear Energy Commission, CNEN, has gone through many improvements. In 2006 CNEN signed the commitment to the recommendations of the Code of Conduct on The Safety and Security of Radioactive Sources and the Guidance on The Import and Export of Radioactive Sources. The DRS is responsible for the licensing and control of nuclear facilities, fuel cycle, waste management and the control of radioactive sources and authorizations of medical and industrial installations. In 2009 the department responsible for the control of radioactive sources and authorizations of medical and industrial installations implemented an “Electronic Management System” in which this System integrates the transport department and waste management department. The Electronic Management System is linked to the register of radioactive sources and facilities and there is an access on line to the Customs, making the control of import and export of radioactive sources robust, efficient and fast. During the period from 2006 until 2015 the most relevant regulations related to the control of radioactive sources and authorizations of medical and industrial installations were reviewed and some were elaborated and issued. These documents were in line with the Categorization of Radioactive Sources and the International Basic Safety Standards, issued in the IAEA Safety Standard Series as General Safety Requirements Part 3 (GSR Part 3). The paper describes all the steps that were adopted in order to implement these systems and the improvements on our Nuclear Regulatory Systems. (author)

  12. Analysis of the systems for management of radioactive wastes from nuclear medicine clinics of the city of Recife, Pernambuco, Brazil

    International Nuclear Information System (INIS)

    Lira, Renata Farias de; Lopes, Ferdinand de Jesus; Passos, Robson Silva; Silva, Valeria Cosma Bento da; Belo, Igor Burgo; Santos, Marcus Aurelio Pereira dos

    2009-01-01

    In nuclear medicine compounds marked with radionuclides, called radiopharmaceuticals, for obtention diagnostic information and for diseases treatment. The physicochemical characteristics of the radiopharmaceuticals determine his fixation at target-organ, and the physical characteristics determine the compound application in diagnostic or therapy. The handling of radiopharmaceuticals generates solid, liquid and gas wastes. The presence of these wastes implies in a adequate management according to regulation standards established by the Brazilian Nuclear Energy Commission (CNEN). The objective of safe management of radioactive wastes is to protect the human being and the preservation of the environment, limiting possible radiological impacts for the future generation, and comprehend a set of technical and administrative activities involved in the collection, segregation, handling, conditioning, transportation, storage, control and elimination, or the final deposition. This work intends to verify if the radioactive waste management systems from the nuclear medicine clinics at the city of Recife are conformal with te normative regulations issued by the CNEN. The initial obtained results are used to elaboration of conformal verification spreadsheet and its application in six nuclear medicine clinics at Recife

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

    International Nuclear Information System (INIS)

    1977-05-01

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

  14. Validation of dose-response curve of CRCN-NE - Regional Center for Nuclear Sciences from Northeast Brazil for 60Co: preliminary results

    International Nuclear Information System (INIS)

    Mendonca, Julyanne C.G.; Mendes, Mariana E.; Hwang, Suy F.; Lima, Fabiana F.; Santos, Neide

    2014-01-01

    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 ( 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 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

  15. 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)

  16. Quality assessment of radiopharmaceuticals in nuclear medicine services at Northeast states, Brazil; Avaliacao da qualidade de radiofarmacos em servicos de medicina nuclear de estados da regiao nordeste

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Wellington Gomes de

    2012-07-01

    The radiopharmaceuticals are used in the field nuclear medicine services (NMS) as tracer in the diagnoses and treatment of many diseases. Radiopharmaceuticals used in nuclear medicine and usually have a minimum of pharmacological effect. The procedures for labelling Radiopharmaceuticals should be observed in order to minimize risks to patients, employees and individuals from the public, and to be administered in humans, must be sterile and free of pyrogens and possess elements all measures of quality controls required a conventional drug. The 'Agencia Nacional de Vigilancia Sanitaria (ANVISA)' in its 'Resolucao de Diretoria Colegiada' (RDC) No. 38 of June 4{sup th} 2008, decided that the NMS must perform quality control in the generators eluate and radiopharmaceuticals according to recommendations of manufacturers and scientific evidence accepted by ANVISA. Thus, this study proposes to evaluate the quality of the generator {sup 99M}o-{sup 99m}Tc eluate and radiopharmaceuticals labeled with {sup 99m}Tc used in most NMS of some states in the Northeast, in relation to radionuclide, chemical, radiochemical purity and pH and promote the inclusion of procedure for quality control of radiopharmaceuticals in routine NMS. The results show that 90% radionuclidic purity, 98.2% purity chemical and radiochemical purity of 46% and 100% of the eluates are in agreement with international pharmacopoeias; already radiopharmaceuticals showed 82.6% purity and all radiochemical pH values are also in accordance with international pharmacopoeias. Even with so many positive results, staff the majority of MNS was not able to perform the quality control of the eluates and radiopharmaceuticals. Showing the importance of implementing of quality control programs of the eluates and radiopharmaceuticals in nuclear medicine. (author)

  17. Quality assessment of radiopharmaceuticals in nuclear medicine services at Northeast states, Brazil; Avaliacao da qualidade de radiofarmacos em servicos de medicina nuclear de estados da regiao nordeste

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Wellington Gomes de

    2012-07-01

    The radiopharmaceuticals are used in the field nuclear medicine services (NMS) as tracer in the diagnoses and treatment of many diseases. Radiopharmaceuticals used in nuclear medicine and usually have a minimum of pharmacological effect. The procedures for labelling Radiopharmaceuticals should be observed in order to minimize risks to patients, employees and individuals from the public, and to be administered in humans, must be sterile and free of pyrogens and possess elements all measures of quality controls required a conventional drug. The 'Agencia Nacional de Vigilancia Sanitaria (ANVISA)' in its 'Resolucao de Diretoria Colegiada' (RDC) No. 38 of June 4{sup th} 2008, decided that the NMS must perform quality control in the generators eluate and radiopharmaceuticals according to recommendations of manufacturers and scientific evidence accepted by ANVISA. Thus, this study proposes to evaluate the quality of the generator {sup 99M}o-{sup 99m}Tc eluate and radiopharmaceuticals labeled with {sup 99m}Tc used in most NMS of some states in the Northeast, in relation to radionuclide, chemical, radiochemical purity and pH and promote the inclusion of procedure for quality control of radiopharmaceuticals in routine NMS. The results show that 90% radionuclidic purity, 98.2% purity chemical and radiochemical purity of 46% and 100% of the eluates are in agreement with international pharmacopoeias; already radiopharmaceuticals showed 82.6% purity and all radiochemical pH values are also in accordance with international pharmacopoeias. Even with so many positive results, staff the majority of MNS was not able to perform the quality control of the eluates and radiopharmaceuticals. Showing the importance of implementing of quality control programs of the eluates and radiopharmaceuticals in nuclear medicine. (author)

  18. Information model for management and preservation of scientific digital memory of the Institute of Nuclear Engineering, Brazil

    International Nuclear Information System (INIS)

    Sales, Luana Farias; Sayao, Luis Fernando

    2013-01-01

    In the context of the data-oriented science (eScience), a considerable part of the results of research activities has been created in digital formats. This means that the memory of the scientific institutions involved in this new scientific paradigm may be at risk of being lost by rapid technological obsolescence, the known fragility of digital media and also by the fragmentation of information and knowledge scattered across multiples repositories. Thus, management of research data in a digital networked and distributed environment becomes an increasing challenge for the research world and the whole area of information: information science, librarianship, knowledge management, archival science and information technology; moreover, in the dynamic environment featuring eScience, there is a need for novel concepts of documents establishing a linkage between traditional documents - printed or digital - stored in repositories, with the data sets stored in data repositories. In this new research environment, an important issue is how to preserve these new complex documents so that they maintain their structure, meaning and authenticity and also its ability to be retrieved, accessed and reused through time and space. In this sense, this paper proposes an information model focused on the curation of scientific memory of the Institute of Nuclear Engineering of the Brazilian Commission of Nuclear Energy (CNEN/IEN). The model considers the traditional scientific documents (theses, articles, books, etc.) in digital formats and all other relevant data and information related to them, such as: scientific data, software, simulations, photos, videos, historical facts, news, etc., compounding an enhanced publication type oriented to the nuclear area. (author)

  19. Information model for management and preservation of scientific digital memory of the Institute of Nuclear Engineering, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Sales, Luana Farias, E-mail: lsales@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Sayao, Luis Fernando, E-mail: isayao@cnen.gov.br [Centro de Informacoes Nucleares (CIN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    In the context of the data-oriented science (eScience), a considerable part of the results of research activities has been created in digital formats. This means that the memory of the scientific institutions involved in this new scientific paradigm may be at risk of being lost by rapid technological obsolescence, the known fragility of digital media and also by the fragmentation of information and knowledge scattered across multiples repositories. Thus, management of research data in a digital networked and distributed environment becomes an increasing challenge for the research world and the whole area of information: information science, librarianship, knowledge management, archival science and information technology; moreover, in the dynamic environment featuring eScience, there is a need for novel concepts of documents establishing a linkage between traditional documents - printed or digital - stored in repositories, with the data sets stored in data repositories. In this new research environment, an important issue is how to preserve these new complex documents so that they maintain their structure, meaning and authenticity and also its ability to be retrieved, accessed and reused through time and space. In this sense, this paper proposes an information model focused on the curation of scientific memory of the Institute of Nuclear Engineering of the Brazilian Commission of Nuclear Energy (CNEN/IEN). The model considers the traditional scientific documents (theses, articles, books, etc.) in digital formats and all other relevant data and information related to them, such as: scientific data, software, simulations, photos, videos, historical facts, news, etc., compounding an enhanced publication type oriented to the nuclear area. (author)

  20. Avaliação de um reator de lodo ativado aplicado à nitrificação utilizando ensaios cinéticos = Evaluation of an activated sludge reactor applied to nitrification using kinetic assays

    Directory of Open Access Journals (Sweden)

    Valeria Reginatto

    2008-01-01

    Full Text Available Neste trabalho, um reator em escala laboratorial de lodo ativado, aplicado ao processo da nitrificação, foi acompanhado por meio de ensaios cinéticos de atividade específica. A atividade de nitrificação da biomassa foi determinada por respirometria nacaracterização do inóculo e na avaliação da biomassa do reator em duas condições: durante a alimentação do reator com meio sintético autotrófico; e após a sua alimentação com efluente de um reator UASB, utilizado para desnitrificação. O reator atingiu uma eficiência em torno de 90% de nitrificação em ambas as condições de operação. O modelo cinético de Andrews, que inclui uma constante da inibição pelo substrato (Ki, ajustou-se melhor aos resultados obtidos nos testes de atividade do que o de Monod. Entretanto, observou-se aumento daconstante de inibição (Ki do lodo após operação do reator em relação ao inóculo, demonstrando a adaptação da biomassa às novas condições (cargas de nitrificação.In this work, an activated sludge lab-scale reactor used fornitrification was monitored by specific activity kinetic assays. The nitrification biomass activity was carried out by respirometric methods in order to characterize the inoculum and the reactor sludge after two different operation conditions: during the feeding of the reactor with synthetic autotrophic medium, and after feeding it with effluent from an UASB reactor used for denitrification. The efficiency of nitrification reached 90% in both operation conditions. Results obtained by the kinetic activity assays were better adjusted by the kinetic model of Andrews, which includes the inhibition constant by the substrate (Ki, than the Monod model. However, an increase was observed in the inhibition constant (Ki of the sludge after the operation of the reactor as compared with the inoculum. This effect demonstrates an adaptation of the biomass to the new nitrification conditions (loading rate.

  1. Avaliação de desempenho de reator UASB no tratamento de águas residuárias de suinocultura Evaluation of performance of UASB reactor in swine wastewater treatment

    Directory of Open Access Journals (Sweden)

    Luciano S. Rodrigues

    2010-01-01

    Full Text Available Este trabalho apresenta o desenvolvimento e a avaliação de um sistema de tratamento de águas residuárias de suinocultura constituído de decantador e seguido de reator anaeróbio de manta de lodo (reator UASB, em escala real. O reator UASB foi construído de alvenaria e concreto armado. Coletaram-se amostras do esgoto bruto e do efluente do decantador e reator UASB, e se monitoraram os seguintes parâmetros: temperatura, pH, alcalinidade, ácidos voláteis totais (AVT, sólidos suspensos totais (SST, sólidos suspensos voláteis (SSV, demanda bioquímica de oxigênio (DBO e demanda química de oxigênio (DQO, de acordo com os métodos estabelecidos pelo Standard Methods (APHA, 1998. Os resultados médios de remoção total de DQO e de DBO foram de 93 e 92%, respectivamente. As concentrações médias de DQO, DBO e SST no efluente final foram de 0,8, 1,8 e 0,8 g L-1, respectivamente. A carga orgânica volumétrica (COV aplicada no reator UASB variou de 1,1 a 17,5 kg DQO m-3 d-1. O sistema decantador-reator UASB apresenta-se como alternativa promissora para o tratamento de águas residuárias de suinocultura.This research presents the development and evaluation of a system for treatment of swine wastewaters constituted by slat settler, followed by upflow anaerobic sludge blanket (UASB reactor, at full scale. The UASB reactor was completely made of masonry and reinforced concrete. The evaluation of the treatment system was carried out through samples collected in the influent and effluent from the settler and UASB reactor. The following parameters were analyzed: temperature, pH, alkalinity, total volatile acids (VFA, suspended solids (TSS, volatile suspended solids (VSS, biochemical oxygen demand (BOD, chemical oxygen demand (COD, according to the methods established by the Standard Methods (APHA, 1998. The mean results of COD and BOD removal were 93 and 92%, respectively. The mean concentrations of COD, BOD and TSS in the final effluent were

  2. Modelagem de um reator integral aplicado na reação de reforma a vapor de metano = Modeling of integral reactor applied methane steam reforming

    Directory of Open Access Journals (Sweden)

    Giane Gonçalves

    2007-07-01

    Full Text Available Freqüentemente, a validação de modelos matemáticos aplicados a reatores industriais esbarra na dificuldade de obtenção de medidas experimentais confiáveis. Uma maneira de contornar esta limitação corresponde à implantação de uma unidade em escala de bancada devidamente instrumentada, na qual são obtidos dados experimentais emcondições controladas. Neste contexto, foram efetuados ensaios em um reator integral de reforma a vapor de metano em escala de bancada, em diversas condições experimentais. As medidas de temperatura no leito foram efetuadas por meio de um termopar multiponto em seis posições axiais distintas, enquanto a composição do efluente do reator foi determinada por cromatografia gasosa. Estes dados experimentais foram comparados com as previsões de um modelo pseudo-homogêneo, unidimensional e dinâmico. Os resultados indicam que o modelo é adequado, sendo que tanto a atividade catalítica como a conversão são sensíveis à temperatura operacional, enquanto a temperatura do leito é praticamente insensível à vazão nas condições experimentais exploradas.Frequently, the validation of applied mathematical models of industrial reactors dash into the difficulty of obtaining reliable experimental data. A way to overcome this limitation is the proper use and operation or a in bench scale, experimental setup from whichexperimental data can be obtained in controlled conditions. In this context, experiments were carried out in an integral reactor of steam reform, in different experimental conditions. Thermocouples were placed along the catalyst bed to allow for temperature monitoring in six equally spaced and distinct positions of the reactor, the composition of the effluent of the reactor was determined by gas chromatography. These experimental data were compared with the theoretical results of a pseudo-homogeneous one-dimensional,dynamic mathematical model. The results indicate that the model can successfully

  3. Tratamento de efluentes de refinaria de petróleo em reatores com Aspergillus niger Treatment of petroleum refinery wastewater by reactors inoculated with Aspergillus niger

    Directory of Open Access Journals (Sweden)

    Sandra Tédde Santaella

    2009-03-01

    Full Text Available Neste trabalho, avaliou-se o efeito do tempo de detenção hidráulica (TDH no desempenho de três reatores aeróbios inoculados com Aspergillus niger AN400, usados para tratamento de efluentes de refinarias de petróleo. Cada reator foi operado com um tempo de detenção hidráulica diferente: 4, 8 e 12 horas, durante 152 dias. Eles possuíam leito fixo de espuma de poliuretano e o escoamento era ascendente e contínuo. Determinaram-se: pH, fenóis, demanda química de oxigênio (DQO, amônia, nitrito e nitrato, no afluente e efluentes dos reatores. O TDH de oito horas foi o melhor para remoção de DQOsolúvel e não houve diferença entre os TDHs para remoção de fenóis totais. No período estável não houve remoção de nitrato; no entanto ocorreu remoção de nitrito de aproximadamente 99%. Além disto, houve produção de amônia devido à amonificação a partir do nitrito presente no meio.This paper evaluated the effect of hydraulic retention time (HRT on the performance of three upflow aerobic reactors, with polyurethane foam as support material, inoculated with Aspergillus niger AN400, used for the treatment of petroleum refinery wastewater. Each reactor was operated with a different HRT: 4, 8 and 12 hours, during 152 days. The performance was evaluated based on pH; phenols; COD, nitrate and nitrite. The results show that for the COD removal, it is more reasonable to operate the reactor with HRT of eight hours. However, there was no difference among results of phenol removal efficiency of the different HRTs. During steady state condition, nitrite was removed in approximately 99%, but there was no reduction on the nitrate concentration. Ammonia was produced in all reactors, probably due to ammonification of nitrite.

  4. Geologic studies on the Rio Una region (Iguape - Sao Paulo County), Brazil, for the construction of nuclear power plants

    International Nuclear Information System (INIS)

    Hassano, S.; Mueller, M.; Stein, J.H.

    1984-01-01

    The main objective of the project was the geological and seismological characterization of 230 Km 2 along the coastal region between the Barro Branco and Jureia massifs in order to pinpoint one or more local areas showing adequate geological, morphological and geotechnical conditions suitable for construction of nuclear power plants. Results of the investigations, as well as the methodology used for determination of main interesting areas are presented. The best areas for construction are believed to be situated along the coast where Precambrian basement rocks crop out close to the shoreline. The Tertiary-Quaternary sedimentary cover reaches a thickness of 50 or more meters and the character of the sediments does not allow direct emplacement of foundations for heavy-weight constructions. Historical analysis of seismic activity of the region, as well as the study of faults and fracture zones identified in the area demonstrate the absence of active faults such as defined by internationally accepted safety criteria. (Author) [pt

  5. Mapping and analysis of natural radioactivity in external environments at the Center for the Development of Nuclear Technology, MG, Brazil

    International Nuclear Information System (INIS)

    Taveira, Natália F.; Duarte, Mayara P.; Santos, Talita O.; Neto, Aimoré D.; Rocha, Zildete

    2017-01-01

    Natural radiation occurs due to two main contributors: particles of high energy cosmic rays incident on the Earth's atmosphere and radionuclides that are present in the earth's crust since its formation, also referred to as primordial radionuclides. For most people, these natural exposures are more significant than exposures caused by artificial sources. The most significant primordial radionuclides are related to the elements Thorium (Th), Uranium (U) and Potassium (K). This work aims to map and analyze the natural radioactivity in external environments in the Center for the Development of Nuclear Technology (CDTN), in order to observe the variation of radioactivity in this locality. It is important to emphasize that, as it is an area of nuclear research center, some points indicated significant values of radiation when compared to the natural ones, being these coming from artificial sources. This study was developed with the RS-230 Radiation Solutions / CANADA spectrometer, with a Global Positioning System (GPS) coupled to quantitatively and qualitatively identifying environmental radionuclides, such as 40 K, 238 U and 232 Th. The results were exported to the ArcGis® program where a geospatial analysis was performed to correlate the data of the RS-230 with the coordinates obtained from the GPS. According to the values the results were classified into five classes: very low, low, medium, high and very high. The article therefore sought to distinguish between the contributions of natural and artificial radioactivity to the environment in the external environments of the CDTN and to provide an information base for future applications in other similar environments

  6. Avaliação microscópica da endogenia microbiana em reatores UASB concêntricos, tratando água residuária do processamento dos frutos do cafeeiro por via úmida - doi: 10.4025/actascitechnol.v33i2.8291

    Directory of Open Access Journals (Sweden)

    Júlia Ferreira da Silva

    2011-04-01

    Full Text Available Com a utilização de duas técnicas de microscopia, eletrônica de varredura (MEV e de epifluorescência, objetivou-se investigar o processo de endogenia da biomassa presente em reatores de manta de lodo e fluxo ascendente (UASB, do inglês upflow anaerobic sludge blancket. Dois reatores UASB concêntricos, funcionando em série, inseridos em um sistema-piloto de tratamento de águas residuárias do processamento dos frutos do cafeeiro por via úmida, foram monitorados quanto aos parâmetros físico-químicos e microbiológicos. Os reatores UASB operaram em campo, com oscilação de temperatura ambiente entre 16,5 e 38,8°C; as temperaturas do afluente e efluente dos reatores variaram de 16,3 a 27,3°C, respectivamente. Os dados iniciais obtidos para a demanda química de oxigênio (DQO foram de 1.349 e 1.173 mg L-1, sendo, ao final do monitoramento atingido os valores de 120 e 102 mg L-1 para os reatores 1 e 2, respectivamente. Concluiu-se que a microscopia aplicada ao perfil de sólidos dos reatores é muito importante e deve ser empregada como parâmetro de qualificação do lodo cultivado em reatores UASB, especialmente quando do decaimento bacteriano.

  7. Communications received from Argentina and Brazil

    International Nuclear Information System (INIS)

    1988-05-01

    The document reproduces the Joint Declaration on Nuclear Policy signed by the Presidents of Argentina and Brazil on 30 November 1985, the Protocol on Nuclear Co-operation between Argentina and Brazil signed on 10 December 1986, the Joint Declaration on Nuclear Policy signed by the two Presidents on 10 December 1986, the Joint Declaration on Nuclear Policy signed by the two Presidents on 17 July 1987 and the Joint Declaration on Nuclear Policy (IPERO Declaration) signed by the two Presidents on 8 April 1988

  8. Nuclear energy - some aspects

    International Nuclear Information System (INIS)

    Bandeira, Fausto de Paula Menezes

    2005-05-01

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

  9. 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)

  10. Remoção de BTEX por fungos em reator aeróbio de escoamento contínuo

    Directory of Open Access Journals (Sweden)

    Kelly Rodrigues

    2017-04-01

    Full Text Available RESUMO Foi estudada a remoção de compostos BTEX (benzeno, tolueno, etilbenzeno e xilenos em reator de escoamento contínuo e mistura perfeita, com inóculo de Aspergillus niger AN 400, operado sob o tempo de detenção hidráulica (TDH de 12 horas para avaliar a eficiência do sistema na biorremediação de água poluída com gasolina na presença (Etapa I e na ausência (Etapa II de glicose (0,5 g.L-1. A água poluída com gasolina foi preparada na proporção de 10:1000 mL (gasolina:água. Na primeira etapa foi ainda estudada a influência da adição de nutrientes no afluente sobre a eficiência do processo. A adição de nutrientes foi benéfica ao processo e, mesmo com a retirada da glicose, a eficiência foi mantida, devido à metabolização do etanol - presente na gasolina brasileira em 25% - pelos fungos, sendo ambos fontes de carbono de assimilação mais fácil para obtenção de energia; o etanol e a glicose, foram usados como cossubstratos na degradação dos BTEX. Assim, na Etapa 2, quando somente havia o etanol no meio, chegou-se a percentuais médios de 88% para benzeno, 90% para tolueno, 90% para etilbenzeno, e de 91% para meta, para e orto-xileno (m, p e o-xileno, com formação de subprodutos fenólicos. A população fúngica predominou no meio ao longo de toda a operação do reator.

  11. Unidade piloto em regime de batelada com sistema de reatores anaeróbios + microalgas + wetlands construídos em fluxo vertical

    Directory of Open Access Journals (Sweden)

    Matheus Wink

    2016-10-01

    Full Text Available Três configurações para operar em batelada sistemas integrados que evoluíram para Reatores Anaeróbios + Microalgas + Wetlands Construídos de Fluxo Vertical (RA + MA + WCFV foram investigadas neste trabalho, tendo as configurações as seguintes características: combinação de tanque de MA com 90L de volume útil, dotado de recirculação interna em cone de acrílico e externa com tanque de 20L, também em acrílico, sendo integrado com WCFV com tempo de detenção hidráulico (TDH de 3 dias com a macrófita Hymenachne grumosa. A configuração do sistema RAs +MA + WCFV vem em operação nos últimos 8 meses, mostrando reduções totais de N-NH4+ (com concentração inicial de 68 mg L-1 , associando 50% de redução de DQO e 70% de fósforo total. Melhorias para o controle de remoção de algas residuais devem ser feitas para aplicação do WCFV, especialmente quanto a carga volumétrica, que deverá ser com até 20 cm dia-1. Para continuidade da evolução foram considerados que devem ser pesquisados os seguintes aspectos: impossibilidade de operação do sistema em fluxo contínuo; drenagem do sistema de lodo não permite sua remoção completa nos Reatores Anaeróbios (RAs e impossibilidade de recarga simultânea dos sistemas.

  12. Tratabilidade do lodo biológico têxtil e produção de biogás em reator UASB em diferentes temperaturas

    Directory of Open Access Journals (Sweden)

    Júnia Schultz

    Full Text Available RESUMO Neste trabalho avaliou-se o comportamento de um reator UASB em escala laboratorial (16 L no tratamento de lodo biológico têxtil com produção de biogás, operando em diferentes temperaturas, 35 (mesofílica, 45 e 55ºC (termofílica, com tempo de detenção hidráulica (TDH constante de 24 h. O reator UASB apresentou-se apto a tratar o lodo têxtil, sendo influenciado positivamente pelo incremento da temperatura, mostrando maiores remoções nas temperaturas termofílicas e com altas taxas de remoção de todos os parâmetros físico-químicos monitorados: demanda química de oxigênio (DQO (97% em 45 e 55ºC, demanda bioquímica de oxigênio (DBO (95% em 45ºC e 94% em 55ºC, fósforo total (P-total (95% a 45 e 55ºC e nitrogênio total (N-total (94% a 45 e 55ºC. Quanto à produção de biogás e à concentração de metano, os maiores valores foram observados a 45ºC. Com base nos resultados alcançados, confirmam-se a tratabilidade do lodo têxtil e a produção de biogás em UASB, com melhor performance a 45ºC.

  13. Modelagem de um reator integral aplicado na reação de reforma a vapor de metano - DOI: 10.4025/actascitechnol.v29i2.705

    Directory of Open Access Journals (Sweden)

    Giane Gonçalves Lenzi

    2008-02-01

    Full Text Available Freqüentemente, a validação de modelos matemáticos aplicados a reatores industriais esbarra na dificuldade de obtenção de medidas experimentais confiáveis. Uma maneira de contornar esta limitação corresponde à implantação de uma unidade em escala de bancada devidamente instrumentada, na qual são obtidos dados experimentais em condições controladas. Neste contexto, foram efetuados ensaios em um reator integral de reforma a vapor de metano em escala de bancada, em diversas condições experimentais. As medidas de temperatura no leito foram efetuadas por meio de um termopar multiponto em seis posições axiais distintas, enquanto a composição do efluente do reator foi determinada por cromatografia gasosa. Estes dados experimentais foram comparados com as previsões de um modelo pseudo-homogêneo, unidimensional e dinâmico. Os resultados indicam que o modelo é adequado, sendo que tanto a atividade catalítica como a conversão são sensíveis à temperatura operacional, enquanto a temperatura do leito é praticamente insensível à vazão nas condições experimentais exploradas.

  14. Perspectives on Global and Regional Security and Implications of Nuclear and Space Technologies: U.S.-Brazil Strategic Dialogue, Phase 2 Report

    Science.gov (United States)

    2014-10-01

    enhanced leverage in South- South and BRICs groupings. 6 Under President Lula da Silva’s leadership, Brazil sought to actively enhance and promote its...State,” 25, 35-36; Joe Leahy and James Lamont, “ BRICs to Debate Creation of Common Bank,” Financial Times, March 20, 2012.   4   Challenges in the...conflict. As previously, mentioned, UNASUR is viewed as a proto-security community. The BRICS (Brazil-Russia-India-China-South Africa) grouping

  15. Brazil: anchoring the region

    International Nuclear Information System (INIS)

    Costamilan, L.C.L.

    1997-01-01

    The role of Brazil's state-run petroleum company, Petrobras, in providing a national supply of oil and natural gas and their products to Brazil was discussed. Petrobras is the sole state-run enterprise which carries out research, exploration, production, refining, imports, exports and the transportation of oil and gas in Brazil. Petrobras has built a complete and modern infrastructure made up of refineries, distribution bases, terminals and oil and gas pipelines. Recently (1995) the Brazilian National Assembly approved legislation that while confirming the state monopoly, also provides private contractors and other state-owned companies ways to participate in the petroleum sector. There exists a great potential for oil and gas in many of Brazil's 29 sedimentary basins. The regulatory legislation also created two new organs to deal with the partial deregulation of the petroleum sector, the National Board for Energy Policy and the National Petroleum Agency. The first of these will deal with policy issues, measures and guidelines regarding regional energy supply and demand and specific programs such as those affecting natural gas, fuel alcohol, coal and nuclear energy. The National Petroleum Agency will manage the hydrocarbon sector on behalf of the government. Its functions will include regulation and monitoring of the sector, managing the bidding process for concessions for exploration and production, and other related activities. The new legislation opens up new horizons for the Brazilian oil sector, providing opportunities for private investment, both domestic and foreign, as well as for new technological capabilities associated with these investments. 1 tab., 6 figs

  16. Reliability studies in research reactors; Estudo de confiabilidade em reatores de pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Albuquerque, Tob Rodrigues de

    2013-08-01

    Fault trees and event trees are widely used in industry to model and to evaluate the reliability of safety systems. Detailed analyzes in nuclear installations require the combination of these two techniques. This study uses the methods of FT (Fault Tree) and ET (Event Tree) to accomplish the PSA (Probabilistic Safety Assessment) in research reactors. According to IAEA (lnternational Atomic Energy Agency), the PSA is divided into Level 1, Level 2 and Level 3. At the Level 1, conceptually, the security systems perform to prevent the occurrence of accidents, At the Level 2, once accidents happened, this Level seeks to minimize consequences, known as stage management of accident, and at Level 3 accident impacts are determined. This study focuses on analyzing the Level 1, and searching through the acquisition of knowledge, the consolidation of methodologies for future reliability studies. The Greek Research Reactor, GRR-1, is a case example. The LOCA (Loss of Coolant Accident) was chosen as the initiating event and from it, using ET, possible accidental sequences were developed, which could lead damage to the core. Moreover, for each of affected systems, probabilities of each event top of FT were developed and evaluated in possible accidental sequences. Also, the estimates of importance measures for basic events are presented in this work. The studies of this research were conducted using a commercial computational tool SAPHIRE. Additionally, achieved results thus were considered satisfactory for the performance or the failure of analyzed systems. (author)

  17. Desempenho de reator anaeróbio-aeróbio de leito fixo no tratamento de esgoto sanitário Performance of anaerobic-aerobic packed-bed reactor in the treatment of domestic sewage

    Directory of Open Access Journals (Sweden)

    Sérgio Brasil Abreu

    2008-06-01

    Full Text Available Este artigo relata a avaliação do desempenho de um reator anaeróbio-aeróbio, preenchido com espuma de poliuretano, para tratamento de esgoto sanitário. Inicialmente, foram testados diferentes tempos de detenção hidráulica (TDH no reator que operou apenas em condições anaeróbias. Em seguida, foi operado o reator combinado anaeróbio-aeróbio. O melhor resultado para o reator em operação exclusivamente anaeróbia foi para o TDH de 10 horas, no qual se conseguiu reduzir a DQO de 389 ± 70 mg/L para 137 ± 16 mg/L. Para o reator anaeróbio-aeróbio, a DQO foi reduzida de 259 ± 69 mg/L para 93 ± 31 mg/L para TDH de 12 h (6 h no estágio anaeróbio e 6 h no aeróbio. A comparação de todos os resultados obtidos evidenciou a importância do pós-tratamento aeróbio na remoção de parcela de matéria orgânica não removida em tratamento unicamente anaeróbio.This paper reports on the performance evaluation of an upflow anaerobic-aerobic reactor, filled with polyurethane matrices, for domestic sewage treatment. Initially, different hydraulic retention times were assayed with the reactor operating exclusively in anaerobic condition. Afterwards, anaerobic-aerobic combined reactor was operated. The anaerobic operation with HRT of 10 h provided the best organic matter removal with COD reduction from 389 ± 70 mg/L to 137 ± 16 mg/L. Under anaerobic-aerobic condition, the COD dropped from 259 ± 69 mg/L to 93 ± 31 mg/L with HRT of 12 h (6 h in anaerobic and 6 h in aerobic stages. Finally, comparing all the obtained results, it was possible to verify the importance of the aerobic post treatment in the removal of part of the organic matter not removed in an exclusively anaerobic treatment.

  18. Safety reviews of the Brazilian multipurpose reactor; Avaliacoes de seguranca do reator multiproposito brasileiro

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Humberto Vitor

    2014-08-01

    This work presents a model developed for thermal hydraulic (TH) simulation of the Multipurpose Brazilian Reactor (RMB), whose Brazilian proposal for design, construction and operation was established in 2007. This reactor has as main proposed the production of radioisotopes for use in exams of nuclear medicine, material tests and utilization of neutrons beams. Besides of the TH modeling and safety analysis of the reactor, the application of a methodology to perform coupled calculation thermal-hydraulic/neutron kinetic (TH/NK) is also presented. Initially, the RMB was modeled in the safety analysis RELAP5 code. This code performs the thermal hydraulic calculation using point kinetics. Subsequently, the model was adapted and verified to the RELAP5-3D© code. This code performs the process of internal coupling through the option of nodal neutron kinetics calculation using the NESTLE code which solves the neutron diffusion equation. To generate the neutronic group constants, which are macroscopic cross sections that serve as input data for the neutronic codes, it was used the WIMSD-5B cell calculation code. The neutron analysis code PARCS was also used to model the 3D RMB core in order to compare the results of radial and axial average power distribution with the results generated by RELAP5-3D© code and with the available results of the CITATION neutron kinetic code. The safety analyses demonstrated safe behavior of the reactor through situations of possible transients. The 3D coupled calculations to the steady state operation also showed expected behavior, as well as the RMB neutronic analyzes performed with the codes NESTLE and PARCS.(author)

  19. Assessment of {sup 222}Rn occupational exposure at IPEN nuclear materials storage site, SP, Brazil; Avaliacao da exposicao ocupacional ao {sup 222}Rn no galpao da Salvaguardas do IPEN, SP

    Energy Technology Data Exchange (ETDEWEB)

    Caccuri, Lilian Saueia

    2007-07-01

    In this study it was assessed the occupational exposure to {sup 222}Rn at IPEN, SP, Brazil, nuclear materials storage site through the committed effective dose received by workers exposed to this radionuclide. The radiation dose was calculated through the radon concentrations at nuclear materials storage site. Radon concentrations were determined by passive detection method with solid state nuclear detectors (SSNTD). The SSNTD used in this study was the polycarbonate Makrofol E; each detector is a small square plastic of 1 cm{sup 2}, placed into a diffusion chamber type KFK. It was monitored 14 points at nuclear materials storage site and one external point, over a period of 21 months, changing the detectors every three months, from December 2004 to September 2006. The {sup 222}Rn concentrations varied from 196 {+-} 9 and 2048 {+-} 81 Bq{center_dot}m{sup -3}. The committed effective dose due to radon inhalation at IPEN nuclear materials storage site was obtained from radon activity incorporated and dose conversion factor, according to International Commission on Radiological Protection procedures. The effective committed dose received by workers is below 20 mSv{center_dot}y{sup -1}. This value is suggested as an annual effective dose limit for occupational exposure by ICRP 60. (author)

  20. Argentina and Brazil

    International Nuclear Information System (INIS)

    Gamba-Stonehouse, V.

    1991-01-01

    This paper reports that security is defined in different ways by many international actors. To some, security is tied to the definition of an external threat to borders, as in the case of the NATO countries. To other, security is related to development, as in the case of most Third World countries. but notwithstanding different definitions, all countries recognize that the essence of security is the survival of the nation-state itself. The nuclear programs of Argentina and Brazil are among the oldest, most sophisticated and advanced nuclear programs anywhere in the Third World. The programs have never been explained on the basis of threat perception, and in this regard perhaps they constitute the most atypical form of nuclear proliferation known to date. Not surprisingly, any attempt to explain the rationale for the Brazilian and Argentine nuclear programs based on common issues of threat =merely confuses the issue. Thus, nationalism, the search for national identity and pride, the need to express self-sufficiency and the desire to keep options open in an insecure and evolving world order must all be analyzed to comprehend the likelihood of future types of nuclear proliferation. Meanwhile, the study of the contemporary era of Argentine-Brazilian nuclear rapprochement may provide new insights into the complex reasoning behind the decision of countries to go nuclear

  1. The victory against Greenpeace-Brazil

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    The author writes down an interview with the President of the Brazilian association for nuclear energy (ABEN). ABEN has actively participated to the rebirth of nuclear energy in Brazil. During the beginning of the nineties Brazil underwent several anti-nuclear campaigns led by Greenpeace-Brazil, these campaigns found a favorable echo among the public because of the radiation accident of Goiania (1987) when a Cesium-137 source found in a dump site irradiated several families, killing 4 people, and of the technical difficulties that appeared during the first operating months of the Angra-1 nuclear power plant. The public controversy was so strong that it was in the air to stop the building work on the Angra-2 site. A counter campaign showing the dark sides of the Greenpeace organisation, opened the eyes to Brazilian politicians and now nuclear energy is re-established in the public esteem. (A.C.)

  2. Uso de lagoa aerada facultativa como polimento do reator anaeróbio de manta de lodo UASB no tratamento de dejetos de suínos em escala laboratorial The efficiency of an aerated pond used for treating the effluent of an UASB reactor (upflow anaerobic sludge blanket reactor treating swine manure in a lab-scale system

    Directory of Open Access Journals (Sweden)

    Fernanda Ribeiro do Carmo

    2004-06-01

    Full Text Available As atividades agroindustriais têm se voltado não somente para o aumento da produtividade, mas também para a conservação do meio ambiente. A suinocultura é, sem dúvida, uma das atividades agroindustriais mais poluidoras, principalmente no Estado de Minas Gerais. Sendo assim, objetivou-se desenvolver e operar uma Lagoa Aerada Facultativa (LAF em escala de bancada (laboratorial, e como polimento de um Reator Anaeróbio de Manta de Lodo (UASB, visando a tratar os dejetos de suínos com máxima eficiência e custo mínimo. O experimento foi conduzido no Laboratório de Análise de Água do Departamento de Engenharia (LAADEG da Universidade Federal de Lavras (UFLA, sendo composto por um tanque de acidificação e equalização (TAE, um reator anaeróbio de manta de lodo (UASB e uma lagoa aerada facultativa (LAF para polimento. As análises fisico-químicas realizadas foram: pH, DBO5, DQO T, Sólidos Totais (fixos e voláteis, Temperatura, Nitrogênio, Fósforo, Alcalinidade e Acidez Total. A unidade LAF mostrou uma eficiência média de 83 e 42% de DQO T e Nitrogênio Total, respectivamente. O sistema proporcionou remoção média de 93, 84 e 85% de DQO T, DBO5 e Sólidos Totais Voláteis, respectivamente.Nowadays the agro-industry activities have not only focused its direction to the production increasing, but also, to the environmental preservation. The swine production is amo doubt, an activity, which can be considered, one of the most pollutants, mainly in the Minas Gerais State (BRAZIL. Therefore, this research aimed at developing and operating an Upflow Anaerobic Sludge Blanket Reactor (UASB, followed by an Aerobic Facultative Pound (AFP (Lab-Scale, with the objective of treating the liquid effluent originated from swine with the maximum efficiency and lower costs. The experiment was carried out in the Laboratory of Water Analysis of the Engineering Department of the Federal University of Lavras (UFLA. The system was assembled with an

  3. Avaliação de desempenho de wetlands construídos para o tratamento de efluente de reator UASB: estudo de caso da ete vog ville

    Directory of Open Access Journals (Sweden)

    Luciano de Souza Ferreira

    2015-12-01

    Full Text Available Um sistema de tratamento de esgoto sanitário, em escala real, composto por reator UASB seguido de wetlands construídos de fluxo horizontal subsuperficial foi avaliado quanto ao comportamento, eficiências de remoção de poluentes e seus aspectos operacionais. O processo foi estudado em duas etapas caracterizadas pela presença e ausência da recirculação do efluente final em duas unidades de wetlands construídos plantadas com diferentes espécies de macrófitas. As faixas de valores das concentrações efluentes dos parâmetros analisados foram: matéria orgânica medida como DQO, 26 a 96 mgO2/L; Sólidos em Suspensão Totais, 2 a 29 mg/L; Sólidos em Suspensão Voláteis, 0 a 27 mg/L; Nitrogênio Total Kjedhal, 17,9 a 72,8 mg/L; nitrogênio amoniacal, 15,4 e 58,8 mg/L; P-PO43-: 3,9 a 9,4 mg/L; fósforo total, 5,6 a 8,5 mg/L; Coliformes Termotolerantes: 104 a 105 NMP/100mL e Coliformes Totais: 105 a 106 NMP/100mL. A aplicação do teste não paramétrico de Wilcoxon-Mann-Whitney em nível de significância igual a 5% mostrou que não houve diferença significativa entre o desempenho de remoção de poluentes durante as duas etapas da pesquisa, nem entre as unidades plantadas com macrófitas distintas. O presente estudo mostrou que wetlands construídos de fluxo horizontal subsuperficial tratando o efluente de reator UASB são capazes de atender a maioria dos padrões de lançamento preconizados na legislação ambiental vigente. O estudo, também, permitiu concluir que há necessidade de uma operação intensa e contínua para se garantir condições adequadas de funcionamento de tais sistemas. 

  4. 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.)

  5. 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.)

  6. Cost evolution of electric energy in Brazil

    International Nuclear Information System (INIS)

    Oliveira, A. de; Contreras, E.C.A.

    1981-01-01

    An analysis of electric energy costs in Brazil is presented. Hydro, coal and nuclear costs are analysed and the final conclusion seems to indicate that nuclear power plants are not economically interesting untill the Brazilian electric capacity attains 110 GW average power. (Author) [pt

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

    Energy Technology Data Exchange (ETDEWEB)

    Bandeira, Fausto de Paula Menezes

    2005-05-15

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

  8. Nuclear power plant construction

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1979-01-01

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.) [pt

  9. Financing of nuclear trade. The brazilian experience

    International Nuclear Information System (INIS)

    Andrade Cavalcanti, C. de.

    1990-01-01

    The importance of financing instruments as means for the promotion of international nuclear trade is analysed. Besides the specific characteristics of nuclear trade is examined. Furthermore the role of governmental authorities and international agencies, mainly the IAEA is discussed. Finally the presence of Brazil in the international financial market and the financing of nuclear trade in Brazil are described [pt

  10. Tratamento de água com hidrocarbonetos aromáticos por uso de reator em bateladas sequenciais com inoculo fúngico Treatment of water with aromatic hydrocarbons by use of sequential batch reactor with fungi inoculum

    Directory of Open Access Journals (Sweden)

    Kelly Rodrigues

    2012-06-01

    Full Text Available Um reator em batelada, aerado, com biomassa imobilizada de Aspergillus niger AN400 foi operado durante 10 ciclos de 7 dias para remover benzeno (200 mg.L-1, tolueno (200 mg.L-1 e xileno (50 mg.L-1 - BTX - e de nutrientes de meio basal. O reator era alimentado semanalmente com 4 L do meio e glicose - 1 g.L-1, na Fase I, e 0,5 g.L-1, na Fase II. Os BTX foram detectados até o quarto dia de operação, em todos os ciclos. As melhores eficiências médias de remoção foram na Fase I: 75%de matéria orgânica solúvel, 80% de ortofosfato e 77% de amônia. O reator pode ser uma alternativa viável para tratamento de águas poluídas com BTX, porém há a necessidade de estudar o comportamento do reator durante período de operação mais longo e com ciclos reacionais mais curtos, bem como da identificação dos metabólitos produzidos.A batch reactor with air and immobilized biomass of Aspergillus niger AN400 was operated during 10 cycles of 7 days to remove benzene (200 mg.L-1, toluene (200 mg.L-1, and xylene (50 mg.L-1 - BTX - and nutrients from basal medium. The reactor was weekly fed with 4 L of the medium and glucose - 1 g.L-1 (Phase I and 0.5 g.L-1 (Phase II. The BTX had been detected until the fourth day of operation in all cycles. The best efficiencies of removal had been in Phase I: 75% of soluble organic matter, 80% of orthophosphate and 77% of ammonia. The reactor can be a viable alternative for the contaminated water treatment with BTX. However it has the necessity to study behavior of the reactor during longer period of operation and with shorter reaction cycles, as well as the identification of the produced metabolites.

  11. UTILIZAÇÃO DA BUCHA VEGETAL DE CURCUBITÁCEA COMO MATERIAL SUPORTE EM REATOR ANAERÓBIO DE LEITO FIXO / USE OF CUCURBITACEOUS BUSH AS SUPPORT MATERIAL IN ANAEROBIC FIXED BED REACTOR

    OpenAIRE

    T. B. Magassy; J. V. C. Fagundes; A. S. Araújo; A. P. de Oliveira Netto

    2017-01-01

    Este projeto avaliou o desempenho de um sistema para tratamento de esgoto sanitário operando de modo contínuo e sem recirculação da fase líquida. O trabalho se diferencia por utilizar a bucha vegetal de curcubitácea como material suporte do reator, pouco estudada para essa finalidade de tratamento biológico de efluentes. Esse material se caracteriza por ser leve, barato e facilmente encontrado na região do alto sertão alagoano, além de ser integralmente natural e com características favorávei...

  12. The Brazilian Nuclear Energy Program

    International Nuclear Information System (INIS)

    Carvalho, H.G. de

    1980-01-01

    A survey is initially of the international-and national situation regarding energetic resources. The Brazilian Nuclear Energy Policy and the Brazilian Nuclear Program are dealt with, as well as the Nuclear Cooperation agreement signed with the Federal Republic of Germany. The situation of Brazil regarding Uranium and the main activities of the Brazilian Nuclear Energy Commission are also discussed [pt

  13. {sup 18}F-fluorocholine production at Center of Nuclear Technology Development, Brazil: synthesis and in vitro cytotoxicity studies; Producao de {sup 18}F-fluorocolina no Centro de Desenvolvimento da Tecnologia Nuclear: sintese e estudos de citotoxicidade in vitro

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Flavia Mesquita

    2014-07-01

    {sup 18}F-fluorocholine ({sup 18}FCH) is promising biomarker for imaging of tumors using PET technology, being effective in the diagnosis of metastatic tumors and specific for the brain tumors, prostate, lung, among others. Despite already being used in some countries like France, Germany, Slovenia, Poland, Romania and Portugal, the {sup 18}FCH is not yet produced or marketed in Brazil. This work proposed the development of a new radiopharmaceutical based on choline labeled with {sup 18}F isotope for diagnostic PET imaging which is an increasing demand of the nuclear medicine national. It was also proposed the development of quality control assays in order to evaluate the radiopharmaceutical prior to its use in patients; in vitro test of toxicity in non-tumor cells (MRC-5), evaluating possible changes in cell proliferation caused by radiopharmaceutical impurities; and, to test the interaction's saturation of {sup 18}FCH with the tumor cells (PC-3 and U-87) and the competition with HC-3 and DMAE, performed to characterize the efficiency of the radiotracer uptake by tumor cells that express the choline transporter CHT. {sup 18}FCH was synthesized in two main steps, first by reaction with dibromomethane with fluoride-18, assisted by Kryptofix2.2.2, forming {sup 18}F-fluorobromomethane ({sup 18}FBrCH{sub 2}) and, then, the {sup 18}FBrCH{sub 2} reacted with the second precursor DMAE generating the final product, {sup 18}FCH. Synthesis duration was 45 minutes. {sup 18}FCH was obtained in 4.68 - 8.32% radiochemical yield, radiochemical purity greater than 99% and it was stable for up to 8 hours after production. The tested analytical methodologies were suitable for routine use in the quality control of {sup 18}FCH. The evaluation of the cytotoxic potential of impurities {sup 18}FCH, by clonogenic assay, showed that at the concentrations evaluated, the components do not alter the proliferative capacity of human healthy cells. The interaction of {sup 18}FCH with cell

  14. Levels of {sup 137}Cs and {sup 40}K in marine superficial sediments near the Angra Nuclear Power Plant (Angra dos Reis, SE Brazil)

    Energy Technology Data Exchange (ETDEWEB)

    Lima Ferreira, Paulo Alves de; Farina Amorim, Lais; Marone Tura, Pedro; Medeiros Zacheo, Valter Andre; Lopes Figueira, Rubens Cesar [Universidade de Sao Paulo (IO-USP), SP (Brazil). Inst. Oceanografico

    2015-07-01

    This study evaluated the spatial distribution of two environmentally relevant radionuclides, {sup 137}Cs and {sup 40}K, in marine superficial sediments around the Angra Nuclear Power Plant, the only Brazilian nuclear power plant complex, thus establishing a baseline for bottom sediments, given the international importance of environmental monitoring around nuclear facilities. It was observed that these radionuclides are mostly present in the muddy sediments as a result of their stronger association with its fine-grained fraction, and that their lowest levels are located around the liquid effluent discharge of the plant, as a consequence of the prevented deposition of fine sediments due to the strong discharge water flux. The comparison of the {sup 137}Cs activities in the region with other locations in the world showed that the presence of this artificial nuclide is due to the atmospheric fallout from past nuclear tests made during the Cold War, not to the nuclear power plant activities.

  15. Levels of 137Cs and 40K in marine superficial sediments near the Angra Nuclear Power Plant (Angra dos Reis, SE Brazil)

    International Nuclear Information System (INIS)

    Lima Ferreira, Paulo Alves de; Farina Amorim, Lais; Marone Tura, Pedro; Medeiros Zacheo, Valter Andre; Lopes Figueira, Rubens Cesar

    2015-01-01

    This study evaluated the spatial distribution of two environmentally relevant radionuclides, 137 Cs and 40 K, in marine superficial sediments around the Angra Nuclear Power Plant, the only Brazilian nuclear power plant complex, thus establishing a baseline for bottom sediments, given the international importance of environmental monitoring around nuclear facilities. It was observed that these radionuclides are mostly present in the muddy sediments as a result of their stronger association with its fine-grained fraction, and that their lowest levels are located around the liquid effluent discharge of the plant, as a consequence of the prevented deposition of fine sediments due to the strong discharge water flux. The comparison of the 137 Cs activities in the region with other locations in the world showed that the presence of this artificial nuclide is due to the atmospheric fallout from past nuclear tests made during the Cold War, not to the nuclear power plant activities.

  16. 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.

  17. 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)

  18. The Brazil agreement - quo vadis

    International Nuclear Information System (INIS)

    Hossner, R.

    1981-01-01

    After an analysis of the power requirements of Brazil as well as of the options for covering these requirements an important nuclear power program for peaceful uses was decided. It is performed on the basis of a bilateral agreement between Brazil and the Federal Republic of Germany of 1975 by co-operation between the German and the Brazilian industry. German firms make their know-how available as well as experts for a limited period of time, in order to establish during about 20 years an independent Brazilian infrastructure for nuclear power plants and their requirements, and to realize the transfer of technology which at the same time shall transmit impulses to the industrial development of the country. (orig.) [de

  19. The atomic deal with Brazil

    International Nuclear Information System (INIS)

    Mirow, K.R.

    1980-01-01

    The author deals with the German-Brazilian nuclear treaty using sources which are meanwhile official. A roaring trade - made in 1975 - had become a public nuisance in 1979. Grand plans of German and Brazilian politicians had changed into economic crisis, unemployment and uncompleted, dilapidating buildings. While even the new government adhered to the treaty, Brazilia had begun a national instigation campaign. This was, however, superseded by Brazil's high indebtedness, an economic crisis and social unrest so that it was impossible to realize the nuclear treaty. (HSCH) [de

  20. Implementation of radioactive wastes management system in nuclear medicine service of Hospital das Clinicas of Universidade de Campinas - UNICAMP, in Sao Paulo State, Brazil

    International Nuclear Information System (INIS)

    Rinaldi Neto, A.; Coelho, R.F.; Brunetto, S.Q.

    2001-01-01

    This work reports the experience acquired at the Servico de Medicina Nuclear of the Hospital de Clinicas/UNICAMP (SMN/HC) in planning and implementing the management system of radioactive waste. This system respects the Comissao Nacional de Energia Nuclear' (CNEN) standards and has been of relatively easy and simple performance, without disturbing the SMN/HC's routine. It has also proof to keep its quality along the time. (author)

  1. Tratamento de águas residuárias de suinocultura em reator anaeróbio operado em batelada sequencial Treatment of swine wastewater in anaerobic sequencing batch reactor

    Directory of Open Access Journals (Sweden)

    Roberto Alves de Oliveira

    2009-12-01

    Full Text Available Neste estudo avaliou-se o desempenho de um reator anaeróbio operado em batelada sequencial, em escala piloto, com volume total de 280 L, no tratamento de águas residuárias de suinocultura. As cargas orgânicas volumétricas aplicadas no reator foram de 4,42; 5,27; 9,33 e 11,79 g DQOtotal (L d-1. As eficiências médias de remoção de DQOtotal, sólidos suspensos totais (SST e sólidos suspensos voláteis (SSV variaram de 56 a 87%. O nitrogênio total Kjedahl (NTK, fósforo total (P-total e magnésio (Mg foram removidos com eficiências médias de 26 a 39%. As produções volumétricas de metano variaram de 0,50 a 0,64 L CH4 (L reator d-1 e não foram observadas diferenças significativas. As relações sólidos voláteis/sólidos totais (SV/ST do lodo de tal reator variaram de 0,74 a 0,58. As maiores concentrações médias de nutrientes no lodo do reator foram para o nitrogênio, fósforo, ferro e cálcio, com valores de 30.610 a 64.400, 1.590 a 9.870, 6.180 a 8.700 e 1.180 a 6.760 mg kg-1 base seca, respectivamente.In the present study, we evaluated an anaerobic sequencing batch reactor, in pilot scale and with a total volume of 280 L, for the treatment of swine wastewater. The organic loading rates applied in such reactor were 4.42; 5.27; 9.33 and 11.79 g CODtotal (L d-1. The average efficiencies of removal of CODtotal total solids suspension (TSS and volatile suspension solids (VSS varied from 56 to 87%. The nutrients total Kjedahl nitrogen (TKN, total phosphorus (total P and Mg were removed with average efficiencies from 26 to 39%. The volumetric methane productions varied from 0.50 to 0.64 L CH4 (L reactor d-1 and did not present significant differences. The VS/TS relations of the aforementioned reactor's sludge varied from 0.74 to 0.58. The highest mean concentrations of nutrients in the reactor sludge were those of nitrogen, phosphorus, iron and calcium, with values from 30.610 to 64.400, 1.590 to 9.870, 6.180 to 8.700 and 1.180 to 6

  2. Aplicação da via curta para remoção biológica de nitrogênio de lixiviado de aterro sanitário utilizando reator em batelada sequencial

    Directory of Open Access Journals (Sweden)

    Luiz Felipe Tavares De Santana

    2015-12-01

    Full Text Available A presente pesquisa teve o objetivo de estudar a remoção biológica de nitrogênio amoniacal (N-NH3 e matéria orgânica biodegradável presente em lixiviado de aterro sanitário, aplicando a nitrificação por meio da via curta, operando um reator de polietileno, em bateladas sequenciais, com volumes úteis superiores a 400 L, ou seja, em escala piloto, aerado por meio de compressor de 1 cv. O experimento foi realizado no aterro sanitário em operação há onze anos, localizado no município de Camaçari - Bahia e operado pela empresa LIMPEC, responsável pelos serviços de coleta, transporte e destinação final dos resíduos sólidos urbanos e industriais não perigosos, gerados nos municípios de Camaçari e Dias D’Ávila, Bahia. O experimento foi conduzido durante 165 dias. Foram realizados: 7 (sete ciclos de tratamento utilizando razões de troca volumétrica de 10% e aerando o conteúdo do reator por 18 horas; 5 (cinco ciclos com razão de troca volumétrica de 20% e aerando o conteúdo do reator por 18 horas e, finalmente, 7 (sete ciclos com razão de troca volumétrica igual a 20% e aerando o conteúdo do reator por 24 horas. Todos os ciclos de tratamento foram operados com o conteúdo do reator a temperatura ambiente, sem correção de pH, e a concentração de oxigênio dissolvido (OD, durante a aeração, foi sempre inferior a 1,0 mg O2/L. Os melhores resultados de eficiência de remoção de poluentes de interesse foram obtidos quando o sistema foi operado com RTV iguais a 10 e 20% e tempos de aeração iguais a 18 e 24 horas respectivamente. Nessas condições operacionais, a remoção de N-NH3 variou entre 56 e 100%, correspondendo a concentrações efluentes entre 0,0 e 84,0 mg N-NH3/L, ou seja, durante 11 ciclos de tratamento o efluente atendeu à Resolução CONAMA 430/2011. O alcance do acúmulo de nitrito, avaliado por meio da razão nitrito/nitrogênio oxidado, mostrou-se estável durante todo o experimento. Ao longo

  3. Advanced ceramics in Brazil: actual stage and perspectives

    International Nuclear Information System (INIS)

    Zanotto, E.D.

    1986-11-01

    The development of advanced ceramics in Brazil, the perspectives of the world and Brazilian markets, the raw materials, the equipments for industry and research, the human resources, and the disposable technology, are presented. The researches on advanced ceramics in Brazil initiated in the sixty decade, with the nuclear fuel development and production projets. (M.C.K.) [pt

  4. Higienização de lodo de esgoto em reator com aquecimento solar: inativação de coliformes totais e Escherichia coli

    Directory of Open Access Journals (Sweden)

    Odinei Fogolari

    Full Text Available RESUMO O uso de lodo de esgoto na agricultura se tornou prática corrente em diversos países, sendo atrativa em muitos aspectos, principalmente no fornecimento de matéria orgânica e nutrientes ao solo. Embora os benefícios ambientais e agrícolas do uso de lodo sejam consideráveis, tal prática deve ser realizada de forma sanitariamente segura. Nesse contexto, o objetivo deste estudo foi avaliar a eficiência de um processo de higienização térmica de lodo de esgoto utilizando energia solar. O lodo era aquecido através de um trocador de calor, construído com tubos de cobre e instalado dentro do reator, no qual circula água aquecida em coletores solares planos. Foram realizados 16 ensaios experimentais em diferentes condições de irradiação solar. A inativação térmica da Escherichia coli foi avaliada através do modelo cinético de primeira ordem em condições não isotérmicas. O processo mostrou-se eficiente em ensaios realizados com irradiação solar média do período acima de 500 W.h.m-2, com redução de E. coli entre 4,2 e 7,1 log10 e de coliformes totais entre 4,8 e 7,4 log10. Os ensaios realizados em dias com menores índices de irradiação solar tiveram a eficiência de higienização comprometida, devido às baixas temperaturas atingidas pelo lodo.

  5. Argentine-Brazilian declaration on common nuclear policy

    International Nuclear Information System (INIS)

    1990-12-01

    The document reproduces the texts of the speeches made by the Presidents of Argentina and Brazil at Foz do Iguacu, Brazil, on 28 November 1990, at the signing of the Argentine-Brazilian Declaration on Common Nuclear Policy

  6. Relative costs to nuclear plants: international experience

    International Nuclear Information System (INIS)

    Souza, Jair Albo Marques de

    1992-03-01

    This work approaches the relative costs to nuclear plants in the Brazil. It also presents the calculation methods and its hypothesis to determinate the costs, and the nacional experience in costs of investment, operating and maintenance of the nuclear plants

  7. Nuclear technology and Latin America

    International Nuclear Information System (INIS)

    Raja Mohan, C.

    1980-01-01

    Developments in nuclear technology in Latin American countries, particularly in Argentina and Brazil, have been surveyed. In their efforts to acquire self-reliance in the nuclear field independently i.e. without seeking help from U.S.A., Argentina and Brazil came to accept stringent foreign controls on their nuclear programmes which envisage having a complete nuclear fuel cycle. Their struggle against the discriminatory nature of the NPT has become more or less theoretical. Moreover, the Latin American countries have signed the Tlatelolco treaty which prohibits testing, use, manufacture or acquisition of nuclear weapons. An encouraging feature is, however, growing bilateral and multilateral cooperation in the nuclear energy sector. It is illustrated by citing the example of the Argentina-Brazil nuclear cooperation agreement. The political significance of this development for the third world is discussed. (M.G.B.)

  8. Usage and conditions of radiation protection of nuclear meters in Brazil; Utilização e condições de proteção radiológica de medidores nucleares no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Guimarães, E.F. [Faculdade Casa Branca, SP (Brazil). Pós-Graduação de Proteção Radiológica em Aplicações Médicas, Industriais e Nucleares; Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro-RJ (Brazil); Silva, F.C.A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Riode Janeiro, RJ (Brazil)

    2017-07-01

    The industries of mining, pulp, oil, etc. which require a quality control in the processes, use the nuclear meters with sealed radioactive sources coupled to a radiation detector that generate accurate and fast answers regarding the level, thickness, density and humidity of different types of materials. Nuclear meters are classified as fixed or portable and use transmission, backscatter or reactive systems. As they use radioactive sources with various ranges of activities, they are classified by the International Atomic Energy Agency - AIEA as Category 3 and 4, of medium and low radiological risk, and must therefore have a suitable level of radiation protection for safe use in the installation. The Brazilian National Energy Commission - CNEN controls approximately 500 authorized facilities with nuclear meters. The paper technically describes the nuclear meters and the radiological protection procedures that must be followed for the safety of the IOEs (occupationally exposed individuals) and individuals from the public, based on the specific nuclear meter test program for CNEN radiation protection supervisor. The professionals who handle these nuclear meters should be aware of the radiological risk to their own protection and to individuals in the public. For safe operation with nuclear meters, a number of requirements must be observed according to the type and need of the installation.

  9. Avaliação do comportamento hidrodinâmico de reator anaeróbio de manta de lodo e fluxo ascendente com diferentes configurações do sistema de distribuição do afluente utilizando fluidodinâmica computacional

    Directory of Open Access Journals (Sweden)

    Diego Bongiorno Cruz

    Full Text Available RESUMO Compreender o comportamento hidrodinâmico de reatores biológicos pode auxiliar na detecção de problemas associados a falhas operacionais e de projeto, situações que prejudicam a eficiência do tratamento. Neste artigo, realizaram-se simulações da fluidodinâmica computacional (CFD de escoamento de duas fases sólida-líquida de um reator anaeróbio de manta de lodo e fluxo ascendente (UASB, em escala piloto (160 L, com tempo de detenção hidráulica (TDH de 10 h e vazão de 16 L.h-1. Um modelo Euler-Euler simplificado foi formulado para simular o comportamento hidrodinâmico da zona de reação, influenciada pela configuração do sistema de distribuição do afluente. Foram avaliadas quatro configurações do sistema de distribuição do afluente no reator: uma entrada na parte central (1 e duas entradas centrais (2, de fluxo ascendente; duas entradas nas laterais (3, de fluxo radial; e três entradas de fluxo descendente (4, utilizando geometrias bidimensionais e tridimensionais para verificar a formação de zonas mortas, curtos-circuitos hidráulicos e caminhos preferenciais. As melhores características hidrodinâmicas e a melhor distribuição do afluente foram verificadas na configuração 4, com melhor perfil de mistura do lodo com a fase líquida, na comparação com as demais configurações. Foi notada formação de vórtices na parte inferior do reator com maior concentração do lodo anaeróbio nessa configuração e de caminhos preferenciais nas laterais do reator na configuração 3, indicando mistura ineficiente do afluente com o lodo anaeróbio. O modelo demonstrou que a configuração do sistema de distribuição do afluente influencia significativamente o comportamento hidrodinâmico do reator UASB.

  10. Nuclear proliferation and the near-nuclear countries

    International Nuclear Information System (INIS)

    Marwah, O.; Schulz, A.

    1975-01-01

    The process of nuclear proliferation and its consequences for the international political system is examined by focusing on the issues in the nuclear-strategic debate that divide first and second order states. Information is included on: the US-USSR arms race; SALT agreement; the Non-Proliferation Treaty; the nuclear aspirations and policies of India, Middle Eastern countries, South Africa, Japan, Brazil, and Argentina; and assessment of the risks related to the nuclear fuel cycle and nuclear weapons

  11. Status of uranium in Brazil

    International Nuclear Information System (INIS)

    Majdalani, S.A.; Tavares, A.M.

    2001-01-01

    Uranium exploration in Brazil was started in 1952 by the Brazilian National Research Council. This led to the discovery of the first uranium deposits in Pocos de Caldas and Jacobina. These activities was later continued by the National Energy Commission/Comissao Nacional de Energia Nuclear (CNEN), formed in 1962. The founding of NUCLEBRAS at the end of 1974 marked the increasing effort of the country's uranium exploration programme. At this time only the Pocos de Caldas deposit was known with measurable resources. Due to the reorganization of the Brazilian nuclear programme in 1988, all uranium exploration in the country was stopped. By then, eight areas with uranium reserves has been identified. Brazil uranium resources in the RAR category at ≤ $80/kg U cost range are estimated to be 162,000 tonnes U, out of which 56,100 tonnes are in the ≤ $40/kg U cost range. Additional resources in the EAR-I category and the cost range ≤ 80/kg U are in the order of 100,200 tonnes U. The first production of uranium in Brazil, at the Osamu Utsumi mine (Pocos de Caldas deposit), started in 1982. Because of escalated costs and reduced demand, this activity was put on stand-by status between 1990 and 1992. The mine was restarted in 1993, but was stopped again in October 1995. The cumulative production of the mine to 1996 was 1241 tonnes U. The Lagoa Real deposit is currently being prepared as a new producing mine. (author)

  12. 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)

  13. Nuclear Proliferation: A Historical Overview

    Science.gov (United States)

    2008-03-01

    Soviet Union in 1991, Kazakhstan inherited approximately 1,410 nuclear warheads and the Semipalatinsk nuclear weapons test site . This placed Kazakhstan...Soviet Union, Kazakhstan inherited approximately 1,410 nuclear warheads and the Semipalatinsk nuclear weapons test site . See Mark D. Skootsky, “An...construction of a nuclear test site . This development moved Brazil into the Modest Weapons Potential category. In 1979 the Pilot Uranium Enrichment Plant

  14. Nuclear laws and radiologic accidents

    International Nuclear Information System (INIS)

    Frois, Fernanda

    1997-01-01

    Some aspects of the nuclear activities in Brazil, specially concerning the Goiania s accident are demonstrated using concepts from environmental and nuclear law. Nuclear and environmental competence, the impossibility of the states of making regional laws, as the lack of regulation about the nuclear waste, are discussed. The situation of Goiania when the accident happened, the present situation of the victims and the nuclear waste provisionally stored in Abadia de Goias is reported

  15. The politics of power in Brazil

    International Nuclear Information System (INIS)

    Bazin, M.

    1980-01-01

    In reviewing the present position concerning Brazil's nuclear energy programme it is shown that it is suffering not only from lack of funds but also from dissent at all levels. The history of the nuclear power plan for the country is outlined reflecting the government's total lack of esteem for its own scientists, its involvement with the United States and later with West Germany and the present position where the programme is years behind schedule and in a state of general disarray. (UK)

  16. Costs comparison of electric energy in Brazil

    International Nuclear Information System (INIS)

    Goncalves, D.; Menegassi, J.

    1981-01-01

    A cost comparison study of various sources of electric energy generation was performed using uniform analysis criteria. The results indicate higher costs for coal, followed by nuclear and hidro. It was verified that presently, large hidro-power plants can only be located far from the load centers, with increasing costs of hidro-power energy in Brazil. These costs become higher than the nuclear plant if the hidro plant is located at distances exceeding 1000 Km. (Author) [pt

  17. Organization of the individual monitoring in Brazil

    International Nuclear Information System (INIS)

    Cunha, P.

    1991-01-01

    There are about 35,000 workers monitored in Brazil. Most of them are employed onhealth and non-nuclear industrial areas. The external individual monitoring is done by 10 laboratories accredited by the Brazilian Nuclear Energy Commission, CNEN, applying specific regulation. The personal date and doses of the monitored workers are stored in a data bank. In this paper, future improvements are also discussed. (orig.)

  18. UTILIZAÇÃO DA BUCHA VEGETAL DE CURCUBITÁCEA COMO MATERIAL SUPORTE EM REATOR ANAERÓBIO DE LEITO FIXO / USE OF CUCURBITACEOUS BUSH AS SUPPORT MATERIAL IN ANAEROBIC FIXED BED REACTOR

    Directory of Open Access Journals (Sweden)

    T. B. Magassy

    2017-06-01

    Full Text Available Este projeto avaliou o desempenho de um sistema para tratamento de esgoto sanitário operando de modo contínuo e sem recirculação da fase líquida. O trabalho se diferencia por utilizar a bucha vegetal de curcubitácea como material suporte do reator, pouco estudada para essa finalidade de tratamento biológico de efluentes. Esse material se caracteriza por ser leve, barato e facilmente encontrado na região do alto sertão alagoano, além de ser integralmente natural e com características favoráveis à imobilização de biomassa. A bucha curcubitácea vem se mostrando bastante eficiente para o tratamento de efluentes líquidos, relacionando os conceitos de sustentabilidade e eficiência. Foi utilizado um reator anaeróbio, em escala de bancada, de leito fixo e fluxo contínuo de escoamento ascendente. O desempenho do sistema foi avaliado em três diferentes tempos de detenção hidráulica (TDH, 8, 6 e 4 horas. Os valores efluentes médios para nitrogênio amoniacal foram de 22,71 mg N/L; 27,97 mg N/L; e 32,40 mg N/L para tempos de detenção hidráulica (TDH, 8, 6 e 4 horas, respectivamente. Em termos de remoção de matéria orgânica representada pela DQO, o reator apresentou eficiência média de 73,0%, 59,7% e 64,0% para cada tempo estudado. Nesta pesquisa, foi desenvolvido um sistema de tratamento de esgoto sanitário estável, confiável e eficiente, em escala de bancada (experimental, baseado nos princípios do tratamento de efluentes por via biológica.

  19. Field study of the planetary boundary layer at subtropical regions of Brazil applied to investigate the dispersion conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Oliveira, A.P. de; Degrazia, G.A.; Moraes, O.L.L. de; Goedert, J.

    1993-01-01

    In this paper is shown some observational results of four field campaigns carried out in the last two years, three during summer, in March 1991, 92 and 93, and one during the winter in July 1992. The site is located in the country side of State of Sao Paulo, Brazil, (23 0 C 25'S; 47 0 C 35' W), approximately 120 km far from the Atlantic Ocean. Measurements of vertical velocity, temperature and water vapor density at three levels (3,5, and 9.40 m) and horizontal wind velocity components at one level (11.5 m) with a sample rate of 1-10 Hz were made using a 12 m tower. It was also carried out measurements of net radiation and soil heat flux, and tethered balloon and radiosonde system followed the vertical evolution of the local Planetary Boundary Layer (PBL).During daytime in the summer, the vertical evolution of the PBL is strongly dependent upon the cloud activity, that inhibits its vertical evolution. In the winter, cloud activity is reduced but the vertical extent of the PBL is constraint by the small surface heating. During the nighttime, the PBL is characterized by moderate stable conditions and low level jets observed in both seasons. (author)

  20. Communications received from Argentina and Brazil

    International Nuclear Information System (INIS)

    1989-01-01

    The document reproduces the Joint Statement on Nuclear Policy signed by the President of Argentina and the President of Brazil on 29 November 1988 at Ezeiza, Argentina, concerning the decision of the two countries to undertake a joint fast breeder reactor project

  1. 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.

  2. Nuclear facilities licensing

    International Nuclear Information System (INIS)

    Carvalho, A.J.M. de.

    1978-01-01

    The need for the adoption of a legal and normative system, defining objectives, pescriptions and the process of nuclear licensing and building of nuclear power plants in Brazil is enphasized. General rules for the development of this system are presented. The Brazilian rules on the matter are discussed. A general view of the German legal system for nuclear power plant licensing and the IAEA recommendations on the subject are finally presented. (A.L.S.L.) [pt

  3. Public acceptance of nuclear energy

    International Nuclear Information System (INIS)

    Reis, J.S.B.

    1984-01-01

    Man, being unacquainted with the advantages of Nuclear Energy associates it with the manufacture of weaponry. However, the benefits of Nuclear Energy is received daily. In Brazil the public has not taken an anti-nuclear position; it is recognized that the Nuclear Plan exists exclusively for peaceful purposes and the authorities keep the community well informed. The Comision Nacional de Energia Nuclear along with the Instituto de Radioproteccion y Dosimetria, Instituto de Ingenieria Nuclear and the Instituto de Investigaciones Energeticas y Nucleares has developed in 27 years of existence, a gradual, accute and effective long term programme for the formation of potentially receptive opinion of Nuclear Energy. (Author)

  4. APLICAÇÃO DE SISTEMAS DE WETLANDS CONTRUÍDOS OPERANDO COMO UNIDADES DE POLIMENTO DE EFLUENTES DE REATORES UASB

    Directory of Open Access Journals (Sweden)

    Luciano Matos Queiroz

    2014-08-01

    Full Text Available O presente trabalho objetivou a realização de uma análise crítica sobre a aplicação de wetlands construídoscomo unidades de polimento de efluentes de reatores UASB (Upflow Anaerobic Sludge Blanket Reactors.O estudo foi realizado a partir de informações e dados obtidos por meio de trabalhos técnicos e científicospublicados entre os anos de 2000 e 2009, os quais estudaram a capacidade de degradação da matériaorgânica e o grau de remoção de nutrientes em sistemas de wetlands construídos exclusivamente paraessa finalidade. Foi realizada uma análise estatística relacionando cada um dos parâmetros chave adotadosnos projetos dos sistemas (taxas de aplicação superficial, tipos de substrato e macrófitas com a eficiênciade remoção de poluentes. As técnicas utilizadas para verificação da correlação entre as variáveis estudadasforam a estatística descritiva e análise de regressão linear multivariada. Todos os dados foram tratados emnível de significância de 95%. Os resultados permitiram concluir que, de maneira geral, os sistemas dewetlands construídos estudados apresentaram valores médios de eficiência de remoção de 78,3%, 54,4% e66,9% para matéria orgânica, medida como DQO, Nitrogênio Total Kjedhal (NTK e fósforo (P,respectivamente. O excelente desempenho da tecnologia para remoção de DQO foi ratificado pelo teste dehipótese. Os resultados mostram que o tipo de substrato utilizado (areia e brita não é significativo para aobtenção de elevadas eficiências e remoção de poluentes nos sistemas; por outro lado, o tipo de macrófitautilizado mostrou-se relevante para a remoção de NTK e P.

  5. Uptake by benthic algae of critical radionuclides to be released in the liquid effluent of the Angra dos Reis Nuclear Power Plant, R.J., Brazil

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.

    1982-06-01

    In vitro interaction of benthic algae from the Angra dos Reis region, R.J., Brazil, was studied with critical radionuclides to be released in the liquid effluent of CNAAA (unit I). 137 Cs- 60 Co - and 125 I uptake and loss by Sargassum filipendula, Padina Vickersiae and Acanthophora Spicifera were observed. Biological half-lives and bioaccumulation factors (B.F.) were estimated. Co and I uptake were fast (apparent equilibrium in 3 to 7 days). Cs uptake was slower (2 to 3 weeks). Loss followed an inverse pattern (fast for Cs, slow for Co and I). B.F. ranged from 10 1 for Cs, to 10 3 for I and 10 3 -10 4 for Co. Higher B.F. for Co and I were found for P. vickersiae (up to 1,4 X 10 4 ) an A. spicifera (up to 7 X 10 3 ) respectively. These species represent important potential media for the transference of Co-I-and-to a much lesser extent - Cs isotopes, through food-webs. They exhibited high capacity to compete with local sandy sediments for the retention of Co and I. High B.F., rapid uptake and moderate to long biological half-lives enable S. filipendula, P. vickersiae and A. specifera to be powerful aids in the monitoring of radioactive contamination by Co and I isotopes. Since the majority of marine organisms tends to exhibit Cs B.F. similars to those reported here, these algae may also be used as monitors for Cs isotopes, the low B.F. being compensated by their abundance, wide distribution and facility of collection. (M.A.) [pt

  6. Modelagem e simulação de reator trifasico aplicado a oleos pesados com reações de hidrocraqueamento termico e catalitico, desmetalização e deposição de coque na mistura e no catalisador

    OpenAIRE

    Letivan Gonçalves de Mendonça Filho

    1998-01-01

    Resumo: Esta dissertação apresenta a modelagem e simulação de um reator tipo ?slurry bubble column? que opera em leito fluidizado trifásico (gás-liquido-solido) com arraste de sólidos para promover a hidroconversão de resíduos de vácuo em condições severas de temperatura e pressão. Nosso objetivo foi reproduzir os fenômenos responsáveis pelas paradas típicas de reatores de hidroconversão de leito fluidizado trifásico, que são separação de fases devido a precipitação ds asfaltenos, a deposição...

  7. Transferência de oxigênio em reatores de leito fluidizado com circulação em tubos concêntricos em meios bifásico e trifásico com variação da relação entre diâmetros

    OpenAIRE

    Araújo,Leandro Santos de; Dall'Aglio Sobrinho,Milton; Gebara,Dib

    2010-01-01

    A eficiência do reator de leito fluidizado com circulação em tubos concêntricos depende das condições hidrodinâmicas que influem na transferência de oxigênio ao biofilme. Este trabalho investigou a influência da relação entre diâmetros dos tubos e da concentração de meio suporte (areia), sobre o coeficiente global de transferência de oxigênio (K La). Os ensaios - em reatores de 2,6 m de altura, com diâmetro externo de 250 mm e internos de 100, 125, 150 e 200 mm - empregaram vazões de ar até 2...

  8. Intercomparison measurements of activity of 99mTc and 131I in nuclear medicine services at Recife city, Pernambuco state, Brazil

    International Nuclear Information System (INIS)

    Barreto, F.C.P.; Santos, M.A.P dos; Oliveira, M.L.; Lima, F.F. de

    2007-01-01

    The aim of this work is to present the results of the first round of intercomparison measurements of activity of 99m Tc and 131 I. This round was carried out in Recife/PE. Six nuclear medicine services (NMS), public and private, participated in this intercomparison. Additionally to the activity measurement, some information about equipment (calibration and quality control program) and human resources was obtained. All NMS participants complied with the limit established by CNEN for the accuracy of measurement (+- 10%) for 99m Tc and 131 I. Measurements will be repeated for 99m Tc and 131 I, and additional rounds will be performed including different radionuclides. (author)

  9. Spatial map dose of nuclear medicine service of the Clinical Hospital of Botucatu, SP, Brazil; Mapa espacial de dose do servico de medicina nuclear do Hospital das Clinicas de Botucatu

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Caio V.; Mendonca, Caroline; Silva, Eduardo T.; Moriguchi, Sonia M.; Koga, Katia H., E-mail: caiov_oliveira@yahoo.com.br [Universidade Estadual Paulista Julio de Mesquita Filho (UNESP), Botucatu, SP (Brazil). Faculdade de Medicina

    2013-12-15

    This study was conducted to describe levels of occupational and environmental exposure of the Nuclear Medicine Service of the Clinical Hospital of Botucatu. To this end, measurements were made of the radiometric levels of points strategically defined, in all the environments, for a period of six months, sampling different days and times, during operation normal routine of the sector. The results allow to estimate the expected dose for each environment, comparing them to the dose limitation established by the National Commission of Nuclear Energy (CNEN), allowing better targeting of occupationally exposed individuals, indicating the points where the occupation should be the minimum required, enabling the reduction of risks to potential exposures. (author)

  10. Aproveitamento de biogás e lodo excedente de reatores UASB como fonte de energia renovável em estações de tratamento de esgoto

    OpenAIRE

    André Pereira Rosa

    2013-01-01

    A pesquisa teve como objetivo avaliar o aproveitamento dos subprodutos biogás e lodo excedente de reatores UASB como fonte de energia renovável em estações de tratamento de esgoto. O objetivo 1 foi desenvolvido a partir de uma ampla revisão de literatura e visitas a ETEs que promovem a recuperação energética na Europa. No âmbito do objetivo 2, os trabalhos foram desenvolvidos na ETE Laboreaux, Itabira-MG através da caracterização do potencial energético do lodo e do biogás e a proposta de det...

  11. Partida de um reator anaeróbio horizontal para tratamento de efluentes do processamento dos frutos do cafeeiro Start-up of an anaerobic horizontal-flow reactor for treating wastewater from a coffee fruits processing

    Directory of Open Access Journals (Sweden)

    Alisson C. Borges

    2009-01-01

    Full Text Available O presente estudo teve o objetivo de avaliar a partida e a adaptação de um reator anaeróbio horizontal de leito fixo (RAHLF no tratamento de águas residuárias do processamento primário dos frutos do cafeeiro (ARC. O reator foi construído com tubos de PVC de 0,2 m de diâmetro e 3,2 m de comprimento. O sistema foi preenchido com cubos de espuma de poliuretano para imobilização de biomassa ativa. O reator apresentou volume total de 0,1 m³ e volume útil equivalente a 0,04 m³. Em média, houve remoção de 49% da matéria orgânica, com o reator trabalhando sob carga orgânica volumétrica média de 2,66 kg m-3 d-1, medida como DQO. A suplementação de alcalinidade, somada à inoculação prévia de biomassa, proporcionou partida estável do RAHLF, confirmada pelo consumo de ácidos voláteis e adaptação da microbiota ao resíduo. O sistema apresentou resistência às variações de vazão e de carga orgânica observadas, e os teores de fenol e potássio monitorados não causaram inibição da atividade biológica no RAHLF. O maior controle sobre as variações de carga é fator importante na continuidade dos estudos.This study aimed to evaluate the start-up and the adaptation of an anaerobic horizontal-flow immobilized biomass (HAIB reactor in order to treat wastewater from a primary processing of coffee fruits. The reactor was built with PVC tubes of 0.2 m in diameter and 3.2 m in length. The system was filled with cubes of polyurethane foam for immobilization of active biomass. The reactor presented a total capacity of 0.1 m³ and reaction volume equal to 0.04 m³. 49% of organic matter. Removal efficiency was observed, with medium organic volumetric loads equal to 2.66 kg m-3 d-1 (as chemical oxygen demand. The supplementary addition of alkalinity and the previous biomass inoculation provided a stable start-up of the reactor, as confirmed by the reduction of volatile acids and an adaptation of the present microbiology community

  12. Tratamento de efluentes têxteis usando reator de leito fluidizado trifásico aeróbio com pré ou pós-ozonização /

    OpenAIRE

    Alves, Kelli Cristina Grando

    2000-01-01

    Dissertação (Mestrado) - Universidade Federal de Santa Catarina, Centro Tecnológico. No presente trabalho foram desenvolvidos estudos combinando processo biológico com pré ou pós-ozonização de efluentes têxteis, para avaliar a eficiência de remoção de DQO e COD, bem como a cor do efluente. Consistiu-se basicamente de duas etapas. Na primeira, foram realizados estudos com efluente têxtil sintético em reator aeróbio de leito fluidizado trifásico para remoção da matéria orgânica, seguido da o...

  13. Efeito do retorno de lodo aeróbio sobre as características da biomassa presente em reatores UASB tratando esgoto sanitário Effect of aerobic sludge return on the characteristics of anaerobic biomass present in UASB reactors treating domestic sewage

    Directory of Open Access Journals (Sweden)

    Patrícia Procópio Pontes

    2009-06-01

    Full Text Available O presente trabalho buscou avaliar a influência do retorno do lodo produzido em filtros biológicos percoladores (FBP sobre as características da biomassa em reatores UASB utilizados para o tratamento de esgoto sanitário. Os experimentos foram conduzidos em reatores em escala piloto e em escala de demonstração, sendo que os reatores UASB foram operados com e sem retorno do lodo produzido nos FBP. Os resultados obtidos indicaram uma diminuição no diâmetro das partículas de lodo, durante as fases com retorno de lodo, mas apenas para as amostras de lodo tomadas nos pontos mais altos dos reatores anaeróbios. A estabilidade e a atividade metanogênica específica do lodo anaeróbio praticamente não se modificaram com o retorno de lodo. Conforme esperado, a produção específica de lodo anaeróbio aumentou com o retorno de lodo.This work aimed at evaluating the influence of the return of excess aerobic sludge produced in trickling filters (TF upon the biomass characteristics in UASB reactors used for the treatment of domestic sewage. The experiments were carried out in pilot and demonstration-scale reactors, with the UASB reactors being operated with and without the return of sludge produced in the TF. Smaller sludge particle sizes were observed when the aerobic sludge was returned to the UASB reactor, but only for sludge samples collected in the upper parts of the anaerobic reactors. Sludge stability and specific methanogenic activity were not affected by the return of sludge. As expected, the specific anaerobic sludge production increased with the return of sludge.

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  15. Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

    International Nuclear Information System (INIS)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

    1996-01-01

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

  16. Otimização do processo de nitrificação com o uso de conchas de ostras como material suporte em reatores aeróbios com biomassa fixa

    Directory of Open Access Journals (Sweden)

    Maria Elisa Magri

    2013-06-01

    Full Text Available A preservação dos mananciais de água traz como ponto de atuação primordial o tratamento dos esgotos sanitários a nível terciário. A partir daí destaca-se a necessidade de otimizar os sistemas de remoção de nutrientes, buscando-se processos mais estáveis, economicamente viáveis e ambientalmente sustentáveis. O objetivo desta pesquisa foi avaliar conchas de ostras como material de preenchimento em um biofiltro aerado submerso, assumindo-se a hipótese de que as mesmas podem interagir com a fase líquida do reator, fornecendo alcalinidade necessária à estabilidade do processo de nitrificação autotrófica. Uma série de condições operacionais foi avaliada visando à nitrificação; portanto, foi possível concluir que, no biofiltro aerado submerso com conchas de ostras, podem ser aplicadas taxas hidráulicas >5,2 m³.m-2.d-1 e tempo de detenção hidráulico <7,5 horas, desde que a relação carbono: nitrogênio seja mantida abaixo de quatro. As conchas de ostras mantiveram o sistema tamponado (pH=7,5±0,3, mesmo com uma intensa atividade nitrificante no reator (100%.

  17. Avaliação do desempenho de sistemas alagados construídos de escoamento horizontal subsuperficial tratando efluente de reator UASB, com base em quatro anos de monitoramento

    Directory of Open Access Journals (Sweden)

    Jocilene Ferreira Costa

    Full Text Available RESUMO Um sistema composto por um reator anaeróbio tipo upflow anaerobic sludge blanket (UASB, seguido de um sistema de alagados construídos (SAC de escoamento horizontal subsuperficial compreendendo duas unidades em paralelo (50 habitantes cada, foi avaliado para o tratamento de águas residuárias geradas na cidade de Belo Horizonte, Minas Gerais, Brasil. Uma unidade foi plantada com Typha latifolia e a outra não foi vegetada. Amostras semanais do efluente do reator UASB e do efluente das unidades do SAC foram avaliadas por um período de quatro anos de operação do sistema. Nas taxas de aplicação praticadas (média de 0,11 m3.m-2.d-1, o efluente final apresentou excelente qualidade em termos de matéria orgânica e sólidos suspensos, mas baixa capacidade de remoção de nitrogênio. Os valores médios de concentração no efluente das unidades plantadas e não plantadas foram, respectivamente, demanda bioquímica de oxigênio: 25 e 23 mg.L-1; demanda química de oxigênio: 50 e 55 mg.L-1; sólidos suspensos totais: 10 e 8 mg.L-1; nitrogênio Kjeldahl total: 30 e 31 mg.L-1; e nitrogênio amoniacal: 27 e 28 mg.L-1. Não se observou diferença significativa entre as concentrações efluentes das unidades plantada e não plantada para a maioria dos constituintes investigados.

  18. Comparativo Do Potencial De Produção De Metano Utilizando Glicerol E Sacarose Como Substrato Orgânico, Em Reatores Operados De Forma Descontínua Alimentada

    Directory of Open Access Journals (Sweden)

    Indianara Cataneo

    2016-10-01

    Full Text Available A crise energética que vem preocupando, não só o Brasil, mas todo o mundo, traz a necessidade da busca por fontes energéticas alternativas, ou seja, energias que causem menos impacto ao meio ambiente. Outro problema enfrentado atualmente é a geração de resíduos e efluentes, que demandam tratamentos e controles adequados. A utilização de biogás como fonte renovável de energia vem se mostrando atrativa, considerando a utilização de resíduos e efluentes como substrato orgânico, com produção energética através de processos de digestão anaeróbia. O objetivo deste trabalho foi comparar o potencial de geração de biogás e metano gerado pelo glicerol, subproduto oriundo de indústrias de fabricação de biodiesel, e sacarose, caracterizada por possuir fácil degradabilidade. Foram testados sistemas de digestão anaeróbia de operação descontínua alimentada em reatores de bancada (19,2L de volume útil. Três situações foram avaliadas, 3, 6 e 9% de matéria orgânica em relação ao volume útil dos reatores. O tempo de detenção hidráulica foi de 15 dias para cada situação proposta. Finalizado os experimentos, verificou-se que o glicerol possui maior potencial para a geração de biogás e metano em relação à sacarose, nas concentrações de alimentação utilizadas.

  19. Thermo-fluid analysis of water cooled research reactors in natural convection; Analise termofluidodinamica de reatores nucleares de pesquisa refrigerados a agua em regime de conveccao natural

    Energy Technology Data Exchange (ETDEWEB)

    Veloso, Maria Auxiliadora Fortini

    2004-07-01

    The STHIRP-1 computer program, which fundamentals are described in this work, uses the principles of the subchannels analysis and has the capacity to simulate, under steady state and transient conditions, the thermal and hydraulic phenomena which occur inside the core of a water-refrigerated research reactor under a natural convection regime. The models and empirical correlations necessary to describe the flow phenomena which can not be described by theoretical relations were selected according to the characteristics of the reactor operation. Although the primary objective is the calculation of research reactors, the formulation used to describe the fluid flow and the thermal conduction in the heater elements is sufficiently generalized to extend the use of the program for applications in power reactors and other thermal systems with the same features represented by the program formulations. To demonstrate the analytical capacity of STHIRP-l, there were made comparisons between the results calculated and measured in the research reactor TRIGA IPR-R1 of CDTN/CNEN. The comparisons indicate that the program reproduces the experimental data with good precision. Nevertheless, in the future there must be used more consistent experimental data to corroborate the validation of the program. (author)

  20. International nuclear trade

    International Nuclear Information System (INIS)

    Biad, A.; Cormis, F. de; Kerever, A.

    1998-01-01

    This third part is relative to the international nuclear trade it includes: the 1996 EURATOM/Usa Agreement on the peaceful Uses of nuclear energy: EURATOM Strengthened, a case study on IVO Power engineering Oy as a supplier to Russia, lessons learned from the Us/EURATOM Agreement for Cooperation, negotiating the parameters of nuclear regulation: lessons from South Africa, Good and new business in Brazil's nuclear energy field, cooperation between Russia and european union in the nuclear field: the legal basis, present status and future prospects, the industrial implications of the non proliferation policy. (N.C.)

  1. Tratamento anaeróbio de águas residuárias do beneficiamento de café por via úmida em reatores UASB em dois estágios Anaerobic treatment of wastewater from coffee pulping in upflow anaerobic sludge blanquet (UASB in two stages

    Directory of Open Access Journals (Sweden)

    Marcelo Bruno

    2008-06-01

    Full Text Available Neste trabalho, avaliou-se a eficiência do tratamento de águas residuárias do beneficiamento de café por via úmida em reatores anaeróbios de fluxo ascendente com manta de lodo (UASB, em dois estágios, em escala de bancada, submetidos a tempos de detenção hidráulica (TDH de 4,0; 5,2 e 6,2 dias e cargas orgânicas volumétricas (COV de 5,8; 3,0 e 3,6 g DQO total (L d-1, no primeiro reator (R1, e TDH de 2,0; 2,6 e 3,1 dias e COV de 5,8; 0,5 e 0,4 g DQO total (L d-1, no segundo reator (R2. Os valores médios de DQO do afluente variaram de 15.440 a 23.040 mg O2 L-1. As eficiências médias de remoção de DQO total e SST foram de 66 a 98% e de 93 a 97%, respectivamente, nos reatores UASB, em dois estágios. O teor médio de metano no biogás variou de 69 a 89%, no reator R1, e de 52 a 73%, no reator R2. A produção volumétrica máxima de metano de 0,708 L CH4 (L reator d-1 foi obtida com COV de 3,6 g DQO (Ld-1 e TDH de 6,2 d, no reator R1. Os valores médios de pH variaram de 4,7 a 7,7 e de 4,9 a 8,0 nos efluentes dos reatores R1 e R2, respectivamente. As concentrações de ácidos voláteis totais nos efluentes mantiveram-se estáveis com valores inferiores a 100 mg L-1, com TDH de 5,2 e 6,2 dias, no reator R1, e TDH de 2,6 e 3,1 dias, no reator R2. As concentrações médias de fenóis totais no afluente variaram de 80 a 97 mg L-1 e as eficiências médias de remoção nos reatores UASB, em dois estágios, foram de 72 a 90%.In this work, it was evaluated the efficiency of two stage up flow anaerobic sludge blanquet (UASB reactors, in bench scale, treating a liquid effluent from the coffee pulping, submitted to hydraulic detention time (HDT of 4.0; 5.2 and 6.2 days, resulting in organic loading rate (OLR of 5.8; 3.6 and 3.0 g COD (L d-1 in the first reactor (R1 and HDT of 2.0; 2.6 and 3.1 days with OLR of 5.8; 0.5 and 0.4 g DQO total (L d-1 in the second reactor (R2. The medium values of total COD affluent varied from 15,440 to 23,040 mg

  2. Analysis of the radiometric survey during the Argonauta reactor operation; Analise do levantamento radiometrico durante operacao do reator Argonauta

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Eara de S.L.; Cardozo, Katia K.M.; Silva, Joao Carlos P.; Santos, Joao Regis dos, E-mail: esluz@ien.gov.br, E-mail: cardozo@ien.gov.br, E-mail: jcarlos@ien.gov.br, E-mail: regis@ien.gov.br [Instituto de Engenharia Nuclear (CNEN-IEN/RJ), Rio de Janeiro - RJ (Brazil)

    2013-07-01

    The Argonaut reactor at the Institute of Nuclear Engineering-IEN/CNEN, operates normally, the powers between 1.7 and 340 W on neutrongraphy procedures, production of radionuclides and experimental reactor physics lessons to postgraduate courses. The doses from neutrons and gamma radiation are measured when the reactor is critical, inside the reactor hall and surrounding regions. A study of the data obtained was performed to evaluate the daily need of this survey in the reactor hall. Taking into account the principle ALARA, which aims to optimize and minimize the dose received by the individual, we propose, in this work, through an analysis of the acquired data in occupational radiometric surveys, a reformulation of the area monitoring routine practiced by the team of radiological protection of the Institute of Nuclear Engineering - IEN/CNEN-RJ, whereas other monitoring routines regarding the radiological protection are also applied in the routine of the reactor. The operations under review occurred with the reactor operating 340 W power at intervals of 60, 120 and 180 minutes, in monitoring points in controlled areas, supervised and free. The results showed significant dose values in the output of the J-Channel 9 when the operation occurs with this open. With 180 minutes of operation, the measured values of dose rate were lower than the values at 60 min and 120 operations min. At the point in the supervised area, offsite to the reactor hall, situated in the direction of the J-Channel 9, the value reduces more than 14% in any operating time in relation to the dose rate measured at the point opposite the canal. There is a 50% reduction in the dose rates for operations with and J-9 closed. The results suggest a new frequency of radiometric survey whose mode of operation is maintained in similar conditions, since combined with other relevant practices of radiation protection.

  3. Evaluation of the influence of percent labeling of {sup 99m}Tc-MIBI on nuclear medicine procedures in Recife, Pernambuco State, Brazil; Avaliacao da influencia do percentual de marcacao do {sup 99m}Tc-MIBI em procedimentos de medicina nuclear em Recife, PE

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Jucilene Maria

    2003-08-15

    The aim of this work was to evaluate the influence of percent labeling of the radiopharmaceutical {sup 99m}Tc-MIBI on the procedures adopted by the nuclear medicine clinics in Recife, Pernambuco State, Brazil, and their possible interference with image quality in myocardial perfusion examinations. This work was performed at two nuclear medicine services in Recife that use pharmaceuticals provided by two different manufacturers: Cardiolite, provided by Dupont and Cardiosyd, provided by SYDMA. The pH, percent labeling and stability of samples of {sup 99m}Tc-MIBI and the percent uptake in heart and liver of a number of patients were evaluated. The results showed that the pH values measured in all samples of both radiopharmaceuticals were within the limits recommended. In 48% of the Cardiolite samples, the percent labeling was less than 90%, which is the minimum recommended limit. On the other hand, 87,5% of the Cardiosyd samples measured values above 98%. Both radiopharmaceuticals had good labeling stability, even in samples with low percent labeling efficiencies. In spite of the higher percent labeling of Cardiosyd its heart uptake is similar to that observed with the Cardiolite, even when the percent labeling is lower than 90%. On the other hand, the image quality, according to physicians, evaluation was poorer for Cardiosyd images, due to high noise and poor sharpness. (author)

  4. Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

  5. The utilization of geochemical parameters for the environmental monitoring of the Nuclear Power Center of Angra I, Ribeira Bay, Rio de Janeiro, Brazil

    International Nuclear Information System (INIS)

    Bidone, E.D.; Carmo Lima, S. do.

    1984-01-01

    In order that a geochemical balance be as complete as possible and thus, reach predictive values for toxic chemical dispersion, an understanding of the hydrological, sedimentological and geological contexts is fundamental. The dispersion of a polluent (in this case radionuclides) is dependent, in part, on its chemical properties and its interaction by sorption and desorption from solid particles (in particular, sediments). This interaction needs to be incorporated in dispersion models and can influence the passage of a pollutant along the food chain. In the case of Ribeira Bay, near the nuclear power center of Angra I, it was observed, through the analysis of sedimentological and geochemical parameters (TOC, TSS, chemical and mineralogical compositions, and granularity): an increase in absorption capacity of surface sediments owing to a homogeneous grain size distribution and a varying clay composition; a possibility of remobilization and transfer of particulate material to areas outside the bay. (Author) [pt

  6. Brazil's energy industry in a crisis

    International Nuclear Information System (INIS)

    Sangmeister, H.

    1988-01-01

    In volume 8/1986 of this periodical, Brazil's moving away from the program for the building and expansion of a national nuclear power industry had been reported on back of foreign currencies and urgently necessary saving measures of the public means influence not only the construction of nuclear power plants, they also decay instruments in other areas of energy industry. In the area of electric power, some nationalisations have already taken place and in petroleum supply, the need for imports is increasing again. Furthermore, there is reason to believe that some of the energy-political solutions which Brazil had chosen as answers to the petroleum price shocks of 1973/74 and 1979/80 are likely to lead to some considerable problems in the near future. In the middle of these crises in which Brazil's energy industry has been for some time now, there is nonetheless one spectacular event. Brazil's President, Mr. Jose Sarney, announced the command of the nuclear cycle by means of national technology. (orig.) [de

  7. Study of application of protective measures for the public and remediation of contaminated areas in case of nuclear and / or radiological accidents in Brazil

    International Nuclear Information System (INIS)

    Silva, Diogo Neves Gomes da

    2011-01-01

    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 137 Cs, 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 real people

  8. Hematology, micronuclei and nuclear abnormalities in fishes from São Francisco river, Minas Gerais state, Brazil = Hematologia, micronúcleos e anomalias nucleares em peixes do rio São Francisco, Estado de Minas Gerais, Brasil

    Directory of Open Access Journals (Sweden)

    Robson Seriani

    2011-01-01

    Full Text Available This study aimed to determine the variables leukocytary, erythrocytary, frequency of micronuclei and nuclear abnormalities in peripheral erythrocytes of Prochilodus argenteus, Pimelodus maculatus and Myleus micans from São Francisco river basin, Minas Gerais State, during the summer and winter. Thrombocytes, hematocrit and leukocyte of P.argenteus series, was influenced by climatic conditions. In P. maculatus, not were significant differences for all leukocytes and thrombocytes. In M. micans, values are unprecedented in the literature, with MCV and absolute number of leukocytes found superior to other species of the family Characidae. The frequency of micronuclei and nuclear abnormalities in erythrocytes, the three species not showed seasonal differences between the sites. However, the highest values were found in summer. Furthermore, we observed a positive correlation between the increase in the percentage of micronuclei with nuclear abnormalities.O presente estudo teve como objetivo, determinar as variáveis leucocitárias, eritrocíticas, freqüência de micronúcleos e anomaliasnucleares nos eritrócitos do sangue periférico de Prochilodus argenteus, Pimelodus maculatus e Myleus micans de um trecho da bacia do rio São Francisco, Minas Gerais, no verão e inverno. Trombóctios, hematócrito e a serie leucocítária de P.argenteus, foi influenciado pela sazonalidade. Em P. maculatus, não ocorreram diferenças significativas para todos os leucócitos e trombócitos. Em M. micans, os valores são inéditos na literatura, apresentando VCM e número absoluto de leucócitos superior ao encontrados para outras espécies dafamília Characidae. A freqüência de micronúcleos e de anomalias nucleares nos eritrócitos, nas três espécies não apresentou diferenças sazonais e entre os pontos amostrais. No entanto, os valores mais altos foram encontrados no verão. Além disso, foi possível observar correlação positiva entre o aumento da

  9. Distribution of 238U, 232Th, 40K, and 137Cs concentrations in soil samples nearby a nuclear laboratory, Capao Island, Brazil

    Directory of Open Access Journals (Sweden)

    Oliveira Luciano S.R.

    2015-01-01

    Full Text Available Absolute soil concentrations of 238U, 232Th, 40K, and 137Cs samples were measured using high-resolution gamma spectrometry. The area of interest encompasses an embankment in a mangrove swamp in Guaratiba, Rio de Janeiro, called Capao Island, where nuclear, chemical and biological defense laboratories of the Brazilian Army Technology Center are in operation for more than 30 years. In order to ensure that no significant environmental impact has resulted from neutron physics experiments performed in a graphite exponential pile in addition to the operation of two cesium-driven irradiating facilities, radiation monitoring of the isotopes was carried out. A total of eight 250 ml soil samples were extracted within an area of 300 m x 300 m. No trace of 137Cs was detected and the measured levels of 238U were found to be close to the global mean. However, some data that slightly exceeded the expected normal range for 232Th (60 % of samples and 40K (20 % of samples should be attributed to the construction debris (cement, rocks, and sand used in the embankment at the site. Since there is no handling of those isotopes at that site or adjacent facilities that could affect their presence, it was concluded that no detectable contamination has occurred.

  10. Argentine-Brazilian declaration on common nuclear policy

    International Nuclear Information System (INIS)

    1990-12-01

    The document reproduces the text of the Argentine-Brazilian Declaration on Common Nuclear Policy, signed by the Presidents of Argentina and Brazil at Foz do Ignacu, Brazil, on 28 November 1990. At the invitation of the Governments of Argentina and Brazil, the Agency's Director General attended the signing ceremony

  11. Simulação numérica aplicada para avaliar o efeito da pré-polimerização no comportamento de reatores tubulares Numerical simulation to evaluate the effect from pre-polymerization on the behavior of tubular reactors

    Directory of Open Access Journals (Sweden)

    André L. Nogueira

    2007-09-01

    Full Text Available O presente estudo utiliza um modelo matemático fenomenológico para simular um sistema de polimerização contínuo em dois estágios. Este sistema é composto por um reator contínuo tipo tanque agitado (CSTR, para pré-polimerização do monômero (primeiro estágio, associado em série a um reator tubular para conduzir a reação até elevados valores de conversão (segundo estágio. Um modelo detalhado, considerando variações axiais e radiais, assim como operação não-isotérmica, foi utilizado para simular o comportamento do reator tubular em diferentes situações. Um modelo de caracterização também foi desenvolvido para fornecer estimativas do peso molecular médio e do índice de polidispersão do polímero. Os resultados mostram que reações de polimerização conduzidas em sistemas contínuos de dois estágios fornecem um polímero com propriedades menos heterogêneas do que um polímero obtido em um sistema reacional composto por apenas um reator tubular. Além disso, quanto maior a viscosidade da mistura reacional alimentada ao reator tubular, mais homogêneo é o polímero obtido.The present study uses a phenomenological model to simulate a continuous, two-stage polymerization process. This system is composed by a continuous stirred tank reactor (CSTR for monomer pre-polymerization (first stage, connected to a tubular reactor (second stage to carry out the reaction up to high conversion values. A comprehensive non-isothermal 2-D model (axial and radial variations was used to predict the tubular reactor behavior. A polymer characterization model was also developed to provide estimates of the polymer average molecular weight and polydispersity. According to the results, polymerization reactions carried out in a continuous two-stage system provide a polymer with less heterogeneous properties than the one obtained in a single tubular reactor. Besides, it is possible to produce a more homogeneous polymer increasing the viscosity

  12. Evaluation of radiochemistry purity and p H of radiopharmaceuticals in nuclear medicine services at Pernambuco, Brazil; Avaliacao da pureza radioquimica e pH de radiofarmacos em servicos de medicina nuclear de Pernambuco, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Wellington; Lima, Fabiana Farias de, E-mail: falima@cnen.gov.b [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil); Santos, Poliane A.L.; Lima, Fernando Roberto de Andrade; Lima, Fabiana Farias de, E-mail: fflima@cnen.gov.b [Centro Regional de Ciencias Nucleares (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

    2011-07-01

    Radiopharmaceuticals are cellular or molecular structures that have a radionuclide in its composition and they are used for diagnosing or treating diseases. The evaluation of the radiochemical purity of radiopharmaceuticals is essential to produce images with artifacts free, as well as avoid unnecessary absorbed dose to the patient. Since they are administered in humans is important and necessary that they undergo rigorous quality control. Due to this fact, the norm in ANVISA RDC 38/2008 declaring the mandatory completion of a minimum of tests in routine nuclear medicine services before human administration. (author)

  13. Desempenho de reatores anaeróbios de fluxo ascendente com manta de lodo em dois estágios tratando águas residuárias de suinocultura Performance of two-stage up flow anaerobic sludge blanket reactors treating swine wastewater

    Directory of Open Access Journals (Sweden)

    Adriana M. de Santana

    2005-12-01

    Full Text Available Avaliou-se o desempenho de dois reatores anaeróbios de fluxo ascendente com manta de lodo (UASB em escala-piloto com volumes de 908 L e 188 L, instalados em série, alimentados com águas residuárias de suinocultura com concentrações médias de sólidos suspensos totais (SST variando de 2.216 mg L-1 a 7.131 mg L-1 e submetidos a tempos de detenção hidráulica (TDH de 62,3 e 31,1 h, no primeiro reator, e de 12,9 e 6,5 h, no segundo reator. As eficiências médias de remoção de DQOtotal variaram de 74,0% a 89,6% no Reator 1 e de 34,3% a 45,1% no Reator 2, resultando em valores médios de 86,6% a 93,1% para o sistema de tratamento em dois estágios com carga orgânica volumétrica (COV na faixa de 3,40 a 14,44 kg DQOtotal m-3 reator d-1 no Reator 1. As concentrações de metano no biogás foram acima de 75% para o Reator 1 e de 80% para o Reator 2. Os valores médios de pH variaram na faixa de 6,9 a 8,2 para o efluente do Reator 1 e de 7,0 a 8,3 para o efluente do Reator 2. Os ácidos voláteis totais mantiveram-se estáveis com concentrações médias abaixo de 200 mg L-1. Esses resultados indicaram que as condições de carga orgânica, em termos de DQO e SSV, impostas ao sistema de tratamento anaeróbio em dois estágios, não foram limitantes para que houvesse o desenvolvimento de lodo com microbiota adaptada e com alta atividade, propiciando altas eficiências médias de remoção de matéria orgânica (86,6 a 93,1% para DQOtotal e 85,6 a 88,2% para SSV e taxas de produção de metano de 0,156 a 0,289 m³ CH4 kg-1 de DQO removida.The objective of this work was monitoring the performance of two up flow anaerobic sludge blanket reactors (UASB in a pilot-scale testing with volumes of 908 L and 188 L, installed in series, loaded with swine wastewater with total suspended solids (TSS ranging from 2216 to 7131 mg L-1, submitted to an hydraulic detention time (HDT of 62.3 and 31.1 h, in the first reactor, and 12.9 and 6.5 h, in the second

  14. Emerging nuclear suppliers in the Third World

    International Nuclear Information System (INIS)

    Stahl, K.

    1990-01-01

    The emergence of new supplier states of nuclear technology within the Third World has raised concern, if those nuclear supplier states will promote an unrestricted and uncontrolled transfer of nuclear technology to developing countries and augment the risk of nuclear weapons proliferation. The article analyses the nuclear export capacities, nuclear exports and the export policy of Argentina, Brazil and India. Argentina is considered as the most important emerging nuclear supplier state in the Third World. Nuclear exports have to be authorisized by the government in all three states and will be covered by IAEA-safeguards in the recipient country. The three states will exercise restraint in the transfer of sensitive nuclear technology. Nuclear exports of Argentina, Brazil and India so far will not augment the danger of nuclear weapons proliferation. (orig./HSCH) [de

  15. Proceedings of the 9. Workshop on Nuclear Physics - Communications of basic nuclear physics

    International Nuclear Information System (INIS)

    1986-01-01

    The abstracts of researches on basic nuclear physics of 9. Workshop on Nuclear Physics in Brazil are presented. Mathematical models and experimental methods for nuclear phenomenon description, such as nuclear excitation and disintegration of several nuclei were discussed. (M.C.K.) [pt

  16. Dose rate received by Pernambuco population due to nuclear medicine exams between 2000-2004

    International Nuclear Information System (INIS)

    Araujo, A.R.; Khoury, H.J.

    2008-01-01

    This study aims to evaluate the diagnostic procedures using in Nuclear medicine of the State of Pernambuco, a state located in northeastern Brazil, from 2000 to 2004 in order to provide subsidies to establish the reference levels in Brazil

  17. Management report 2003 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2004-03-01

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

  18. Applied nuclear physics group - activities report. 1977-1997

    International Nuclear Information System (INIS)

    Appoloni, Carlos Roberto

    1998-06-01

    This report presents the activities conducted by the Applied Nuclear Physics group of the Londrina State University - Applied Nuclear Physics Laboratory - Brazil, from the activities beginning (1977) up to the end of the year 1997

  19. Mapping and analysis of natural radioactivity in external environments at the Center for the Development of Nuclear Technology, MG, Brazil; Mapeamento e análise da radioatividade natural em ambientes externos no Centro de Desenvolvimento da Tecnologia Nuclear (CDTN)

    Energy Technology Data Exchange (ETDEWEB)

    Taveira, Natália F.; Duarte, Mayara P.; Santos, Talita O.; Neto, Aimoré D.; Rocha, Zildete, E-mail: natyfontaveira@hotmail.com, E-mail: mayarapinheiroduarte@gmail.com, E-mail: talitaolsantos@yahoo.com.br, E-mail: zildete@cdtn.br, E-mail: dutraa@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Natural radiation occurs due to two main contributors: particles of high energy cosmic rays incident on the Earth's atmosphere and radionuclides that are present in the earth's crust since its formation, also referred to as primordial radionuclides. For most people, these natural exposures are more significant than exposures caused by artificial sources. The most significant primordial radionuclides are related to the elements Thorium (Th), Uranium (U) and Potassium (K). This work aims to map and analyze the natural radioactivity in external environments in the Center for the Development of Nuclear Technology (CDTN), in order to observe the variation of radioactivity in this locality. It is important to emphasize that, as it is an area of nuclear research center, some points indicated significant values of radiation when compared to the natural ones, being these coming from artificial sources. This study was developed with the RS-230 Radiation Solutions / CANADA spectrometer, with a Global Positioning System (GPS) coupled to quantitatively and qualitatively identifying environmental radionuclides, such as {sup 40}K, {sup 238}U and {sup 232}Th. The results were exported to the ArcGis® program where a geospatial analysis was performed to correlate the data of the RS-230 with the coordinates obtained from the GPS. According to the values the results were classified into five classes: very low, low, medium, high and very high. The article therefore sought to distinguish between the contributions of natural and artificial radioactivity to the environment in the external environments of the CDTN and to provide an information base for future applications in other similar environments.

  20. Media Monopoly in Brazil.

    Science.gov (United States)

    Amaral, Roberto; Guimaraes, Cesar

    1994-01-01

    Documents the process of broadcasting media development in Brazil, the failure of new technologies to produce democratization, and the barriers to democratization erected by monopolization and "metastasis." (SR)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

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

  2. Applied nuclear physics group - activities report. 1977-1997; Grupo de fisica nuclear aplicada - relatorio de atividades. 1977-1997

    Energy Technology Data Exchange (ETDEWEB)

    Appoloni, Carlos Roberto

    1998-06-01

    This report presents the activities conducted by the Applied Nuclear Physics group of the Londrina State University - Applied Nuclear Physics Laboratory - Brazil, from the activities beginning (1977) up to the end of the year 1997.

  3. Nitrogen gas supply device in nuclear power plant

    International Nuclear Information System (INIS)

    Nishino, Masami

    1991-01-01

    The present invention concerns a nitrogen gas supply device in a nuclear power plant for supplying nitrogen gases to a reactor container and equipments working with the nitrogen gas as the load. A liquid nitrogen storage pool is disposed to a concrete nuclear buildings and has a two-vessel structure of inner and outer vessels, in which heat insulators are disposed between the inner and the outer vessels. Further, the nitrogen gas supply mechanism is disposed in an evaporation chamber disposed in adjacent with the liquid nitrogen storage pool in the reator building. Accordingly, since liquid nitrogen is stored in the liquid nitrogen storage pool having a structure surrounded by concrete walls, direct sunlight is completely interrupted, thereby enabling to prevent the heat caused by the direct sunlight from conducting to the liquid nitrogen. Further, since the outer vessel is not exposed to the surrounding atmosphere, heat conduction rate relative to the external air is small. This can reduce the amount of liquid nitrogen released to the atmospheric air due to natural evaporation. (I.N.)

  4. Power conversion for a microreactor: a nuclear space application

    International Nuclear Information System (INIS)

    Guimaraes, Lamartine N.F.; Camillo, Giannino P.; Nascimento, Jamil A.; Borges, Eduardo M.; Placco, Guilherme M.

    2009-01-01

    Generating nuclear power in space is of fundamental importance if it is desired to realize some aggressive type of exploration. Basically, at Earth orbit (either LEO or GEO) most applications tend to use solar panels, which are just fine, in spite of problems such as vibration, non optimal light incidence angle and non electricity generation due to Earth's shadow. For deep space exploration the nuclear power is been considered as a strong candidate and maybe the only one. The Institute for Advanced Studies is conducting the TERRA project that tracks the developments in the area and, also, intends to develop the key technologies that will allow such a machine to be build with indigenous technology. TERRA stands for TEcnologia de Reatores Rapidos Avancados. This project, at its first stage aims at the specification of the microreactor fuel element with its possible geometrical arrangements. Also for this stage a gas Brayton closed cycle is being considered as a heat conversion to electricity and/or propulsion effect. The basic idea is to adapt an open loop aeronautic gas turbine to operate as a closed loop gas Turbine. This arrangement will use heat pipes as a cold source, or a heat rejection passive system. Up to this point a lot has been done in terms of numerical and graphical development. It is expected that some built up will be happening during this year. An account of this work will be presented at the conference. (author)

  5. Interpretation of the results from individual monitoring of workers at the Nuclear Fuel Fabrication Facility, Brazil; Interpretacao de resultados de monitoracao individual interna da Fabrica de Combustivel Nuclear - FCN

    Energy Technology Data Exchange (ETDEWEB)

    Castro, Marcelo Xavier de

    2005-07-01

    In nuclear fuel fabrication facilities, workers are exposed to different compounds of enriched uranium. Although in this kind of facility the main route of intake is inhalation, ingestion may occur in some situations, and also a mixture of both. The interpretation of the bioassay data is very complex, since it is necessary taking into account all the different parameters, which is a big challenge. Due to the high cost of the individual monitoring programme for internal dose assessment in the routine monitoring programmes, usually only one type of measurement is assigned. In complex situations like the one described in this study, where several parameters can compromise the accuracy of the bioassay interpretation it is need to have a combination of techniques to evaluate the internal dose. According to ICRP 78 (1997), the general order of preference of measurement methodologies in terms of accuracy of interpretation is: body activity measurement, excreta analysis and personal air sampling. Results of monitoring of working environment may provide information that assists in the interpretation on particle size, chemical form, solubility and date of intake. A group of fifteen workers from controlled area of the studied nuclear fuel fabrication facility was selected to evaluate the internal dose using all different available techniques during a certain period. The workers were monitored for determination of uranium content in the daily urinary and faecal excretion (collected over a period of 3 consecutive days), chest counting and personal air sampling. The results have shown that at least two types of sensitivity techniques must be used, since there are some sources of uncertainties on the bioassay interpretation, like mixture of uranium compounds intake and different routes of intake. The combination of urine and faeces analysis has shown to be the more appropriate methodology for assessing internal dose in this situation. The chest counting methodology has not shown

  6. Managing nuclear supplier risks

    International Nuclear Information System (INIS)

    Ramberg, B.

    1990-01-01

    This paper reports that with the appearance of such third-tier suppliers as Argentina, Brazil, South Korea, Taiwan, China, and others capable of producing nuclear components and sensitive nuclear materials, assurance that importers are using nuclear energy benignly and safely may become more uncertain. It is therefore important to integrate emerging exporters and importers into a regime of norms designed to minimize nuclear risks. The experience of the London Nuclear Suppliers Group (NSG) to arrive at a code of conduct is encouraging. Placed in the context of the larger evolving nuclear energy regime that seeks to address nuclear safety, proliferation, terrorism, and military attacks on reactors, the international community has made substantial progress. Still, there is much that remains to be done

  7. The new Brazilian legislation on nuclear protection

    International Nuclear Information System (INIS)

    Fischer, Denise

    1981-10-01

    This paper considers the new system on nuclear protection in Brazil which was established to integrate all government agencies and private bodies involved in nuclear activities. The role of each organisation is analysed in relation to the Brazilian political and administrative structure, in particular that of the Nuclear Energy Commission. (NEA) [fr

  8. German-Brazilian nuclear deal

    International Nuclear Information System (INIS)

    Krugmann, H.

    1981-01-01

    Examination of the arguments in favor of the nuclear deal with West Germany and the resulting program suggests that revisions of both are in order to make them more compatible with Brazil's national interests. The deficiencies of current policy appear to be too weighty and numerous to be ignored. Sooner or later the government will have to move toward adjusting its nuclear agreement with West Germany, if not for the reasons discussed here then for lack of capital. Current estimates of the nuclear package lie in the range of $25 to $30 billion, compared to an initial projection of about $5 billion. The deal has become so expensive that it would draw capital from the hydropower and alcohol programs essential for the short and medium-term energy needs of the country. Mr. Krugman feels the Brazilian government should hold off on further nuclear contracts. And it should thoroughly reassess what Brazil's nuclear energy and technology requirements are and how to meet them. There are indications that the reassessment process is already underway. As long as the German nuclear industry depends on the sale of technology to Brazil, the Brazilian government will have considerable bargaining power to enforce further changes in the deal. If this power is used wisely, the result could be cooperation between the two countries toward nuclear options that are consistent with Brazil's energy and development needs

  9. Radionuclides used in nuclear medicine (131I, 99mTc e 99Tc) in sewage system and in the marine environment of Rio de Janeiro city, RJ, Brazil

    International Nuclear Information System (INIS)

    Sousa, Daniele Santos de

    2014-01-01

    The nuclear medicine is a specialty that uses radioisotopes for diagnostic or therapeutic purpose. In Brazil there are around 340 Nuclear Medicine Services (NMS), 27 of them, are located in the city of Rio de Janeiro. The most widely used radionuclides in the country are 131 I and 99m Tc. The radionuclide 99m Tc decays to 99 Tc, which is a beta emitter with a long half-life (10 5 years). The aim of this study is to perform a survey to estimate the 131 I and 99 Tc discharged levels at the Canal do Cunha, the main pathways for environmental dispersion and evaluate the radiological impact to non-human biota and to the populations exposed to these radionuclides. The Alegria Station receives sewage from most clinics of Rio de Janeiro mid was therefore chosen as a study case. The station receives approximately 4.50 x 10 5 Bq/year of 99 Tc e 7.12 x 10 12 Bq/year of 131 I. After passing through all stages of treatment, the effluent is discharged into the Canal do Cunha and flows into the Guanabara Bay. To assess the radiological impact of these radionuclide discharges, a comparative study was made considering three computational models: the CROM, which is based on a model of the International Atomic Energy Agency (IAEA), the PC-CREAM, widely used by the European Union and the GENII, which is the most widely used model in the United States. Two exposure scenarios were considered: 1 - people that bathe directly in the discharge of the effluent; 2 - community living 1200 meters from the discharge point, bathing in the river and consuming local fish. Concentration and doses values for the scenarios according to the applicability of each computer code were estimated. The dose values at the discharge point were 7.47 x 10 -6 mSv for 131 I and 2.87 x 10 -14 mSv for 99 Tc, while for scenario II the value of the total dose was approximately 10 -1 mSv/year for 131 I and 10 -10 mSv/year for 99 Tc, and fish consumption is the main responsible for the dose. An analysis by gamma

  10. Regional safeguards arrangements: The Argentina-Brazil experience

    International Nuclear Information System (INIS)

    Marzo, M.; Gonzales, H.L.; Iskin, M.C.L.; Vicens, H.

    1997-01-01

    A Common System of Accounting and Control of Nuclear Material (SCCC) was established by Argentina and Brazil in July 1992. It is a full scope safeguard's system in both countries. The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) was created to apply the SCCC. The main elements of the SCCC are presented. The main safeguards' procedures are described. A brief discussion of the inspection methodology and its impact for facility operators is performed. The safeguard's implementation from the operator's point of view is commented, taking as example a fuel fabrication plant in Argentina and a uranium enrichment plant in Brazil. (author)

  11. Technical and economical availability of radioisotopes production in Brazil

    International Nuclear Information System (INIS)

    Lima, J.O.V.

    1981-10-01

    The technical and economical availability of radioisotopes production in Brazil by a low power research reactor, are done. The importance of radioisotope utilization and controled radiations, in areas such as medicine, industry and cost evaluation for the production in nuclear reactors. In the cost evaluation of a radioisotope production reactor, the studies developed by the Department of Nuclear Engineering of Universidade Federal de Minas Gerais - DEN/UFMG were used. The information analysis justify the technical and economical availability and the necessity of the radioisotopes production in Brazil. (E.G.) [pt

  12. Planning and implementation of nuclear research programmes

    International Nuclear Information System (INIS)

    Lopes, J.L.

    1986-01-01

    The planning and implementation of nuclear research programmes in developed and developing countries is discussed. The main aspects of these programmes in USA, France, Japan, India and Brazil are reported. (M.W.O.) [pt

  13. Socio-environmental impacts of Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    Rosa, L.P.; Hesles, J.B.S.

    1984-01-01

    Technological aspects and the social problematic inherent to implementation of nuclear power plants in Brazil are studied. it is showed the study in two levels: one of them, attacks aspects linked to nuclear energy and their risks in Brazil; the other one, treats of impacts of the Angra dos Reis nuclear power plants on the local comunity. (M.C.K.) [pt

  14. Latin America: emerging nuclear market

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for nuclear power in Latin American countries is surveyed. It is concluded that Latin America offers the greatest external market for all exporters of nuclear reactors and associated services in the near future. Mexico, Venezuela, Ecuador, and Bolivia are the only countries with fossil-fuel reserves adequate to meet their requirements in the next 20 to 30 years. Nuclear power is a necessity to maintain or improve the standard of living in the countries of Brazil, Argentina, Chile, and Peru

  15. Materials. The Argentine nuclear policy

    International Nuclear Information System (INIS)

    Strasser, H.

    1982-01-01

    Part A of the volume contains a literature search on proliferation and the Third World and on the nuclear technology of Argentina. The materials in part B are divided in: 1. Nonproliferation discussion and the Third World. 2. Development and state of nuclear technology in Argentina. 3. Argentina's international contacts in the field of nuclear energy 1. Federal Republic of Germany, 2. Soviet Union, 3. Brazil. (orig./HP) [de

  16. Levantamento de parâmetros cinéticos medidos em reator anaeróbio de manta de lodo (UASB em escala-piloto tratando efluentes de laticínio = Survey of kinetic parameters measured in upflow anaerobic sludge blanket (UASB in pilot-scale treatment of dairy wastewater

    Directory of Open Access Journals (Sweden)

    Bruno Botelho Saléh

    2009-01-01

    Full Text Available O objeto desta pesquisa foi à obtenção e avaliação dos parâmetros cinéticos do reator anaeróbio de manta de lodo (UASB-Upflow Anaerobic Sludge Blanket na remoção da carga orgânica poluidora dos despejos da atividade laticinista. O sistema com suas principais unidades foi composto de tratamento preliminar (caixa de areia e flotadores,tanque de contato (TC, reator UASB, filtro anaeróbio (FAB e lodo ativo em batelada (LAB. Os TDH’s (tempos de detenção hidráulicos e a temperatura adotados para o reator UASB foram de 44, 35, 30, 26 e 20h após a fase de estabilização do sistema, com temperatura média de 24,8ºC ± 1,8ºC. O volume do reator era de 394 L. A partir dos dadosDQOT (mg L-1, Sólidos Totais Fixos e Voláteis (mg L-1, Temperatura (°C, Vazão (L dia-1 e Perfil de Lodo no reator (Sólidos Voláteis Totais em mg L-1, monitorados durante todo o período de pesquisa na estação-piloto, em cada um dos tempos de detenção hidráulicos(TDH’s no reator UASB, foi conduzido o estudo para obtenção dos parâmetros cinéticos: coeficiente de crescimento ‘Y’ (mg DQO mg SVT-1 d-1, coeficiente de decaimento ‘Kd’ (d-1, taxa máxima de crescimento ‘μmáx’ (d-1 e concentração de substrato limitante ‘Ks’ (mg DQO L-1. Os parâmetros cinéticos determinados se basearam em estudos de regressão linear para determinação de Y, Kd, μmáx e Ks, respectivamente, dando, assim, respaldo técnico-científicoaos dados físico-químicos levantados durante a operacionalização do sistema.The goal of this research was to obtain and withdraw the kinetic parameters from an Upflow Anaerobic Sludge Blanket – UASB in removing the organic load from the waste by-product of a dairy activity. The treatment system was composed of a Sand Interceptor (Grit Chamber, Grease Intercept Chambers, Stirred Contact Tank (CT, a UASB reactor, Anaerobic Filter (AF, and Batch Activated Sludge System (BASS. The HRT (Hydraulic Retention Time and

  17. Tratamento anaeróbio de pentaclorofenol em reator de leito fluidificado alimentado com água residuária sintética contendo glicose como fonte única de carbono Anaerobic treatment of pentachlorophenol in a fluidized bed reactor fed with synthetic wastewater containing glucose as a single carbon source

    Directory of Open Access Journals (Sweden)

    Flavio Bentes Freire

    2008-09-01

    Full Text Available Neste trabalho foi utilizado um reator anaeróbio de leito fluidificado (RALF, tratando água residuária sintética contendo pentaclorofenol (PCP, submetido a condições operacionais menos idealizadas. Utilizou-se um reator com volume de 16 litros, com partículas de carvão ativado granular como meio suporte. O desempenho do reator foi verificado pelas análises usuais de monitoramento (pH, alcalinidade, DQO, ácidos voláteis e também por análises de microscopia e concentração de PCP. A presença de PCP no sistema, nas concentrações utilizadas, não alterou de maneira significativa a qualidade da biomassa presente, e nem os parâmetros de monitoramento. Em concentrações afluentes de PCP variando de 1 a 6 mg/L, foram observadas eficiências médias de remoção de 92% e 70%, respectivamente.In the present work, an anaerobic fluidized bed reactor (AFBR was used for the treatment of a synthetic wastewater containing pentachlorophenol (PCP subjected to less idealized operating conditions. The reactor was a 16 litres tank with granular activated carbon particles as support media. Evaluation of AFBR performance was done by the analysis of usual monitoring parameters (pH, alkalinity, COD, volatile acids together with microscopy and PCP concentration analysis. The presence of PCP under the concentrations used did not significantly alter the amount of biomass and the performance monitoring parameters. Removal average efficiencies of the order of 92% and 70% were obtained for PCP inflow concentrations in the range of 1 to 6mg/l.

  18. An Energy Overview of Brazil

    International Nuclear Information System (INIS)

    2003-01-01

    The DOE Office of Fossil Energy is maintaining a web site that is meant to provide useful business- and energy-related information about countries and regions of the world for exporters, project developers, and researchers. The site consists of more than 130 country pages (organized into seven different world regions), with each country page having its own set of links to information sources about that country. There are also more than 30 Country Energy Overviews at the web site -- each of these is a comprehensive review of a specific country's entire energy situation, including sections on Energy Policy, Oil, Natural Gas, Coal, Hydroelectric/Renewables, Nuclear Power, Energy Transmission Infrastructure, Electricity, Electric Industry Overview, Environmental Activities, Privatization, Trade, and Economic Situation. The specific country highlighted in this Country Energy Overview is Brazil. The site is designed to be dynamic. Updates to the overviews will be made as need and resources permit

  19. Tratamento de resíduo líquido de laticínios utilizando Caixas de Gordura e Reator Anaeróbio Compartimentado seguido de Leitos Cultivados

    Directory of Open Access Journals (Sweden)

    Ana Cristina Ferreira Moreira da Silva

    2014-10-01

    Full Text Available Neste trabalho foram avaliados o desempenho e a eficiência de um sistema de tratamento de resíduos líquidos de laticínios na remoção da carga orgânica do resíduo em uma indústria de laticínios, utilizando um sistema composto por caixas de gordura, reator anaeróbio compartimentado e leitos cultivados de fluxo subsuperficial vegetado com Typha sp. e utilizando como meio suporte brita #1, sob diferentes tempos de detenção hidráulica (3 e 5 dias nos leitos cultivados. Como média geral na remoção de DBO e de DQO, o tratamento utilizando tempo de detenção de 3 dias conseguiu remover 98,87% de DBO e  99,77% de DQO, enquanto o tratamento utilizando 5 dias de detenção hidráulica removeu, em média, 99,51% de DBO e 99,56% de DQO. Os resultados indicam que o sistema foi eficiente no tratamento de resíduos líquidos de laticínios.

  20. Cogeneration for Brazil

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    Almost all the electric power in Brazil comes from large-scale hydroelectric plants: only about 3% comes from cogeneration. But, now that the barriers which discouraged cogeneration are being removed, there will be more and more investment in cogeneration and distributed generation. The circumstances which have brought about these changes are described. It is expected that cogeneration will be responsible for producing 10-15% of Brazil's electricity by 2010 and the demand for cogeneration will reach 11-17 GW. It is concluded that Brazil represents one of the world's most attractive market for cogeneration and distributed generation

  1. Influência da imobilização de biomassa e do tamanho da partícula na fluidodinâmica de um reator anaeróbio de leito fluidizado = The influence of immobilized biomass and particle size on the fluid dynamics of an anaerobic fluidized bed reactor

    Directory of Open Access Journals (Sweden)

    Flavio Bentes Freire

    2008-01-01

    Full Text Available O estudo da fluidodinâmica é muito comum em diversas áreas relacionadas com a engenharia química, tais como nos processos de secagem e nos reatores químicos. Entretanto, em reatores biológicos empregados no tratamento de águas residuárias, esses aspectos ainda necessitam de investigações mais aprofundadas. Deste modo, é fundamental avaliar a influência da presença do biofilme no comportamento fluidodinâmico do reator, por meio de importantes parâmetros como, por exemplo, a velocidade de mínima fluidização, a expansão, a porosidade do leito e a velocidade terminal da partícula. O objetivo deste trabalho foi realizar uma investigação da fluidodinâmica de um reator anaeróbio de leito fluidizado, tratando uma água residuária sintética preparada a partir da solução utilizada para determinação de DBO, tendo o carvão ativado como meio suportepara a imobilização de biomassa. Especificamente, no trabalho, verificou-se que a biomassa imobilizada aumentou a densidade das partículas e alterou os principais parâmetros fluidodinâmicos avaliados.Fluid dynamic analysis is an important branch of several chemical engineering related areas, such as drying processes and chemical reactors. However, aspects concerning fluid dynamics in wastewater treatment bioreactors still require further investigation, as they highly influence process efficiency. Therefore, it is essential to evaluate the influence of biofilm on the reactor fluid dynamicbehavior, through the analysis of a few important parameters, such as minimum fluidization velocity, bed expansion and porosity, and particle terminal velocity. The main objective of the present work was to investigate the fluid dynamics of an anaerobic fluidized bed reactor, having activated carbon particles as support media for biomass immobilization. Reactor performance was tested using synthetic residual water, which was prepared using the solution employed in BOD determination. The results

  2. Considerations about decommissioning of the IEA-R1 research reactor and the future of its installations after shutdown; Consideracoes sobre o descomissionamento do reator de pesquisa IEA-R1 e futuro de suas instalacoes apos o seu desligamento

    Energy Technology Data Exchange (ETDEWEB)

    Frajndlich, Roberto

    2014-07-01

    strategy that can be adopted in the case of this reactor is the one which preserves its building and installations, in view of the fact that a large volume of radioactive waste which will be produced and consequently a much higher costs that will result if dismantling of the reactor is decided. It is suggested that a part of the team of the technicians of reactor operation and maintenance and radiation protection services should be retained and the reactor with its building and annexes should be used for disseminating the information about the nuclear energy by transforming it in to a museum. This has been the first nuclear reactor built in Brazil and since its inauguration, has been, constantly utilized for disseminating information about the nuclear energy in the country. (author)

  3. Nuclear trade between developing countries

    International Nuclear Information System (INIS)

    Stahl, K.

    1990-01-01

    The analysis of nuclear south-south cooperation is based on the evaluation of official documents (the texts of laws, of contracts for nuclear cooperation treaties, safeguard treaties, official government policy speeches etc.). These data were supplemented by numerous interviews with representatives of atomic energy authorities, foreign ministries, nuclear industries, members of parliament, representatives of the nuclear energy opposition movement and military representatives in the three states and by interviews with representatives of the IAEO and OPANAL in Mexico. The study deals with each country in turn: Chapter 2 gives an overview of the Indian nuclear energy programme and India's nuclear export activity and export policy. Chapter 3 analyzes Brazil's nuclear energy policy and Brazilian export capacities, exports and export policy in the nuclear sector. Chapter 4 looks at the development of the Argentinian nuclear energy programme and the crisis in it, at Argentina's nuclear export activities and its export policy and technology transfer policy in this field. Chapter 5 analyzes separately relations between Argentina and Brazil on nuclear cooperation, since they differ considerably from the two countries' relations with other Third World countries on this topic. The appendix documents the most important contractual agreements and government policy declarations on nuclear cooperation between the two states. (orig.) [de

  4. Proceedings of the 9. Workshop on Nuclear Physics - Communications of applied nuclear physics and instrumentation

    International Nuclear Information System (INIS)

    1986-01-01

    The communications of applied nuclear physics and intrumentation of 9. Workshop on Nuclear Physics in Brazil are presented. Several intruments for radiation measurements, such as detectors, dosemeters and spectrometers were developed. Techniques of environmental monitoring and instrument monitoring for nuclear medicine are evaluated. (M.C.K.) [pt

  5. Energy Education in Brazil.

    Science.gov (United States)

    Messick, Rosemary; de Paiva, Terezhina Villela O'Grady

    1980-01-01

    Compares energy education in Brazil and the United States. Topics discussed include the Brazilian setting, government initiatives, dependence on foreign fuel sources, public reaction, schools and energy education, and mass media involvement. (DB)

  6. IDRC in Brazil

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

    local farmers — particularly women — ... INTERNATIONAL DEVELOPMENT RESEARCH CENTRE. FL. IC ... the roots of violence ... Wage inequalities in Brazil and India ... foreign policy efforts, IDRC supports research in developing countries.

  7. Radiochemistry teaching and research activities in Brazil

    International Nuclear Information System (INIS)

    Vasconcellos, M.B.A.; Saiki, M.

    2006-01-01

    Much concern has been expressed lately about the decline of teaching and research activities in radiochemistry in many countries, as was discussed in an IAEA Technical Meeting in Antalya, Turkey, in 2002, and also at MTAA-11 in Guildford, UK. In the IAEA meeting, a survey was presented about the current situation in different regions of the world (Eastern Europe, East and West Asia, Africa, North America and Latin America) by experts of each region. In the case of Brazil, which has nuclear research reactors and also cyclotrons in operation, the teaching and research activities in radiochemistry are concentrated in the three main institutes of the Brazilian Nuclear Energy Commission, in the University of Sao Paulo and in other universities, in different regions of the country. In the present paper, a closer look is given to the radiochemistry teaching and research activities that are being conducted nowadays in Brazil, comprising: number of radiochemistry courses and students being formed, main research areas being conducted, as well as research and production of radioisotopes for nuclear medicine, using nuclear reactors and cyclotrons. (author)

  8. Seismic risk map for Southeastern Brazil

    International Nuclear Information System (INIS)

    Mioto, J.A.

    1984-01-01

    During the last few years, some studies regarding seismic risk were prepared for three regions of Brazil. They were carried on account of two basic interests: first, toward the seismic history and recurrence of Brazilian seismic events; second, in a way as to provide seismic parameters for the design and construction of hydro and nuclear power plants. The first seismic risk map prepared for the southeastern region was elaborated in 1979 by 6he Universidade de Brasilia (UnB-Brasilia Seismological Station). In 1981 another seismic risk map was completed on the basis of seismotectonic studies carried out for the design and construction of the Nuclear power plants of Itaorna Beach (Angra dos Reis, Rio de Janeiro) by IPT (Mining and Applied Geology Division). In Brazil, until 1984, seismic studies concerning hydro and nuclear power plants and other civil construction of larger size did not take into account the seismic events from the point of view of probabilities of seismic recurrences. Such analysis in design is more important than the choice of a level of intensity or magnitude, or adoption of a seismicity level ased on deterministic methods. In this way, some considerations were made, concerning the use of seisms in Brazilian designs of hydro and nuclear power plants, as far as seismic analysis is concerned, recently altered over the current seismic risk panorama. (D.J.M.) [pt

  9. Nuclear law and radiological accidents

    International Nuclear Information System (INIS)

    Frois, F.

    1998-01-01

    Nuclear activities in Brazil, and particularly the radiological accident of Goiania, are examined in the light of the environmental and nuclear laws of Brazil and the issue of responsibility. The absence of legislation covering radioactive wastes as well as the restrictions on Brazilian States to issue regulations covering nuclear activities are reviewed. The radiological accident and its consequences, including the protection and compensation of the victims, the responsibility of the shareholders of the Instituto Goiano de Radioterapia, operator of the radioactive source, the provisional storage and the final disposal at Abadia de Goias of the radioactive waste generated by the accident are reviewed. Finally, nuclear responsibility, the inapplicability of the Law 6453/77 which deals with nuclear damages, and the state liability regime are analysed in accordance with the principles of the Brazilian Federal Constitution. (author)

  10. Energy in Brazil

    International Nuclear Information System (INIS)

    Morato de Andrade, C.

    2003-05-01

    To prepare the Gross Domestic Product increase of 4 % in the next years, it is necessary to increase the capacity in Brazil. The government decided actions in favor of the installed capacity growth speeding up and planed investments. This document takes stock on the energy situation in Brazil, the human, political and geographical constraints and the decided measures in favor the energy development. (A.L.B.)

  11. Nuclear energy: considerations about nuclear trade

    International Nuclear Information System (INIS)

    Goes Fischer, M.D. de.

    1988-01-01

    A general view of historical aspects of nuclear energy and the arrangements to assure its use for peaceful purposes are presented. Then the internal character of nuclear energy in a juride context is demonstrated; some consideration about the international organizations and conventions and the Brazilian Legislation in the nuclear area are examined. It also deals with the political aspects of nuclear trade and the function of IAEA in this are. Furthermore the restrictions imposed by Non-Proliferation Treaty-NPT, the objectures of the Tlatelolco Treaty and ''London Club'' guidelines. Afterwards the bilateral cooperation under taken by countries and its agreements are discussed. Besides some aspects of agreements made between United States, France Germany and Brazil are discussed [pt

  12. Os deletérios impactos da crise nuclear no Japão

    Directory of Open Access Journals (Sweden)

    Paulo Marques

    2012-01-01

    Full Text Available O artigo aborda o acidente nuclear no Japão em 11 de março de 2011. Em decorrência do terremoto seguido de tsunami, foram danificados três dos seis reatores existentes no complexo Daiichi-Fukushima. Ocorreram explosões, seguidas da liberação de materiais radiativos ao meio ambiente. São mostrados os efeitos danosos nos casos da exposição do homem a radiações. Comenta-se a existência do principal nó górdio da geração nucleoelétrica, que é a produção do indescartável lixo atômico.This work reports the severe nuclear incident occurred in Japan on March 11, 2011, due a earthquake followed by tsunami, where three of six existing reactors in Daiichi-Fukushima were damaged. The explosions with releasing of radioactive materials to environment have been discussed. It has shown the harmful effects of radiations to the exposed human being. Besides, the existence of the main impediment of the nuclear electric generation represented by production of non-disposable atomic waste has been discussed.

  13. Uranium prospecting in the State of Bahia, Brazil

    International Nuclear Information System (INIS)

    Cenachi, N.C.

    1974-01-01

    A brief description is made of the program established by CNEN (Brazilian Nuclear Energy Commission) - Brazil, for the radiogeological survey of a large area in the state of Bahia. Details of the projects carried out since 1971 are also given. Projects of aerogeophysical surveys are also mentioned [pt

  14. Communication received from the Resident Representatives of Argentina and Brazil

    International Nuclear Information System (INIS)

    1993-01-01

    The document reproduces the communication received by the Director General from the Resident Representatives of Argentina and Brazil to the Agency to inform him about the official inauguration on 9 December 1992 of the headquarters of the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) in Rio de Janeiro

  15. Iran: the next nuclear threshold state?

    OpenAIRE

    Maurer, Christopher L.

    2014-01-01

    Approved for public release; distribution is unlimited A nuclear threshold state is one that could quickly operationalize its peaceful nuclear program into one capable of producing a nuclear weapon. This thesis compares two known threshold states, Japan and Brazil, with Iran to determine if the Islamic Republic could also be labeled a threshold state. Furthermore, it highlights the implications such a status could have on U.S. nonproliferation policy. Although Iran's nuclear program is mir...

  16. The nuclear proliferation

    International Nuclear Information System (INIS)

    Gere, F.

    1995-04-01

    In this book is detailed the beginning of nuclear military power, with the first bomb of Hiroshima, the different ways of getting uranium 235 and plutonium 239, and how the first countries (Usa, Ussr, China, United kingdom, France) got nuclear weapons. Then the most important part is reviewed with the details of non-proliferation treaty and the creation of IAEA to promote civilian nuclear power in the world and to control the use of plutonium and uranium in nuclear power plants. The cases of countries who reached the atom mastery, such Israel, South Africa, Pakistan, Iraq, North Korea, Argentina, Brazil, Iran, Algeria, Taiwan and the reasons which they wanted nuclear weapon for or why they gave up, are exposed

  17. An alternative nuclear program

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1981-01-01

    An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is nor capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

  18. Alternative Nuclear Program

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1982-01-01

    An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is not capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

  19. Desempenho de um reator Fenton em escala industrial aplicado à remoção de fenóis em uma planta de recuperação de resíduos da indústria de papel e celulose

    Directory of Open Access Journals (Sweden)

    Everton Skoronski

    2015-11-01

    Full Text Available Este trabalho descreve o desempenho de um reator Fenton em grande escala usado para remoção de fenol em uma planta de valorização dos resíduos da indústria de papel e celulose. O efluente consiste em óleo vegetal e fenol. A estação de tratamento objetiva tratar 4 m3 h-1 e é constituída por um pré-tratamento para remoção de óleo, reator Fenton, Flotador de Ar Dissolvido - FAD e uma lagoa de aeração. Para a avaliação da estação de tratamento foram comparadas análises próprias do efluente com análises feitas em laboratório certificado. A eficiência global de remoção de fenol é maior do que 99,7%. Foi demonstrado que a combinação do processo de oxidação avançada com o biológico constitui-se em um sistema de tratamentos interessante a fim de remover contaminantes recalcitrantes.

  20. Nuclear weapons free zones

    International Nuclear Information System (INIS)

    Stahl, K.

    1990-01-01

    The article analyses the concept and problems of the two nuclear weapons free zones in Latin America and in the South Pacific established by the Treaty of Tlatelolco and the Treaty of Rarotonga. So far the nuclear weapons states except China have refused to sign the additional protocols of the Treaties or have signed them only with considerable provisos. Therefore they don't fully recognize the nuclear weapons free status of those zones, or they don't recognize it at all. Both Treaties contain no provisions to regulate the transit of nuclear weapons through the zones. This allows de facto the stationing of nuclear weapons in the military bases of the US which are located within the nuclear weapons free zone of Latin America. The Treaty of Tlatelolco contains also the right of the states, party to the Treaty, to explode nuclear devices for peaceful purposes. Since peaceful and military nuclear explosions cannot be distinguished technically, this right could also undermine the nuclear weapons free status of the region. Important nuclear threshold countries like Argentina and Brazil have furthermore refrained from putting the Treaty into force. (orig.) [de

  1. Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics; Anais do 10. Encontro de Fisica de Reatores e Termo-Hidraulica

    Energy Technology Data Exchange (ETDEWEB)

    Santos Bastos, W. dos

    1995-12-31

    These proceedings presents all the Meeting papers emphasizing specific aspects on reactor physics method, criticality, fuel management, nuclear data, safety analysis, simulation and shielding, neutronics, thermal hydraulics, reactor operation and computational methods.

  2. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Communication recue de la mission permanente du Bresil concernant les Directives de certains Etats Membres applicables a l'exportation de matieres, d'equipements et de technologie nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-12-03

    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 [French] L'Agence a recu une note verbale de la mission permanente du Bresil, en date du 22 mars 2007, lui demandant de diffuser a tous les Etats Membres une lettre du 12 decembre 2006 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Artur Denot Medeiros, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Chypre, Croatie, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraine. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

  3. The Brazilian nuclear programme

    International Nuclear Information System (INIS)

    Forman, J.M.A.

    1990-01-01

    Developing an energy policy for a country the size of Brazil is a formidable task. Large differences between the regions in geography and economic development do not allow for a uniform plan. In the mid 1970s, Brazil started a nuclear energy programme to provide it with another option in its energy planning. The objective of the programme was gradually to build a technical and industrial base for nuclear power in the country, so that it would be available when it was needed. It was recognized that it would not be easy for a developing country to acquire the necessary high technology. The organization of the industry is outlined, demand projections are presented and domestic supplies of uranium assessed. (author)

  4. Assistance to Brazil, Pakistan and Thailand

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-04-15

    IAEA's technical assistance programme for the current year includes aid to atomic energy projects in Brazil, Pakistan and Thailand. It is proposed to establish a radiation measurement service in Brazil where radioactive isotopes are finding increasing use in medicine, industry and research. The assistance to be provided by IAEA will consist of equipment for the proposed service, and experts who would give courses in their respective specializations and co-operate in the testing of equipment, initiation of measurements and organization of working plans. The Agency is putting three specialists at the disposal of the Pakistan Atomic Energy Commission: one of them an expert on research reactors, another on radioisotopes and irradiation by gamma rays, and the third on health physics. The Pakistan Government has decided to set up an Institute of Nuclear Research and Reactor Technology, where it is planned to install a reactor with a power level of 1 MW to be increased later to 5 MW. The main purposes of the reactor project will be: training on reactor operation and reactor physics; training and research in neutron physics; research on radiation physics and nuclear chemistry; production of radioisotopes; biological research on the effects of radiation; radiation protection and shielding, and research in nuclear engineering and metallurgy. Under a third project, IAEA has sent an expert to Thailand to assist in the development of the medical applications of radioisotopes, particularly in diagnosis and clinical research

  5. Chemical correlations in Caetite (BA) region, Brazil

    International Nuclear Information System (INIS)

    Gennari, R.F.; Almeida, Geangela M.; Souza, S.O.

    2013-01-01

    Brazil's economic situation is responsible for an urgent demand for energy. There are several ways to generate energy, in some localities of our country, energy generation occurs almost exclusively by nuclear route, as in Rio de Janeiro state. Brazil has the sixth largest reserve of the uranium ore in the world. Nowadays there is only one mine under exploration (Uraniferous District of Lagoa Real - Caetite-BA). Unfortunately, nuclear power generation is better known, by common citizen, more for its unwanted effects than for its benefits. This fact is also powered by some Non-Governmental Organizations (NGOs), such as Greenpeace, who claim the uranium mine is dangerous since it causes environmental contamination. However, Industrias Nucleares do Brasil (INB) rejected these accusations. In a previous study, we demonstrated that doses of the Caetite (BA) population are consistent with those usually found in other countries. We stated also the higher concentration of 238 U determined, in only one water sample, is probably due to natural processes, as soil leaching. In order to verify the existing natural processes, macro and micro chemical elements present in water and soil samples collected in the Caetite (BA) region were determined by ICP-MS. The results were transformed into dendrograms where chemical correlations are evidenced and they are consistent with existing natural chemical processes. It was also possible to observe a correlation between samples corroborating with the Geographic Information Systems data to be presented in this same scientific event. (author)

  6. Chemical correlations in Caetite (BA) region, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Gennari, R.F., E-mail: rgennari@usp.br [Universidade de Sao Paulo (USP), Sao Paulo, SP (Brazil). Inst. de Fisica. Dept. de Fisica Nuclear; Campos, S.S., E-mail: simaracampos@gmail.com [Universidade Estadual do Sudoeste da Bahia (UESB), Itapetinga, BA, (Brazil); Almeida, Geangela M.; Souza, S.O., E-mail: susanasouzalalic@gmail.com [Universidade Federal de Sergipe (UFS), Sao Cristovao, SE (Brazil). Dept. de Fisica

    2013-07-01

    Brazil's economic situation is responsible for an urgent demand for energy. There are several ways to generate energy, in some localities of our country, energy generation occurs almost exclusively by nuclear route, as in Rio de Janeiro state. Brazil has the sixth largest reserve of the uranium ore in the world. Nowadays there is only one mine under exploration (Uraniferous District of Lagoa Real - Caetite-BA). Unfortunately, nuclear power generation is better known, by common citizen, more for its unwanted effects than for its benefits. This fact is also powered by some Non-Governmental Organizations (NGOs), such as Greenpeace, who claim the uranium mine is dangerous since it causes environmental contamination. However, Industrias Nucleares do Brasil (INB) rejected these accusations. In a previous study, we demonstrated that doses of the Caetite (BA) population are consistent with those usually found in other countries. We stated also the higher concentration of {sup 238}U determined, in only one water sample, is probably due to natural processes, as soil leaching. In order to verify the existing natural processes, macro and micro chemical elements present in water and soil samples collected in the Caetite (BA) region were determined by ICP-MS. The results were transformed into dendrograms where chemical correlations are evidenced and they are consistent with existing natural chemical processes. It was also possible to observe a correlation between samples corroborating with the Geographic Information Systems data to be presented in this same scientific event. (author)

  7. Assistance to Brazil, Pakistan and Thailand

    International Nuclear Information System (INIS)

    1959-01-01

    IAEA's technical assistance programme for the current year includes aid to atomic energy projects in Brazil, Pakistan and Thailand. It is proposed to establish a radiation measurement service in Brazil where radioactive isotopes are finding increasing use in medicine, industry and research. The assistance to be provided by IAEA will consist of equipment for the proposed service, and experts who would give courses in their respective specializations and co-operate in the testing of equipment, initiation of measurements and organization of working plans. The Agency is putting three specialists at the disposal of the Pakistan Atomic Energy Commission: one of them an expert on research reactors, another on radioisotopes and irradiation by gamma rays, and the third on health physics. The Pakistan Government has decided to set up an Institute of Nuclear Research and Reactor Technology, where it is planned to install a reactor with a power level of 1 MW to be increased later to 5 MW. The main purposes of the reactor project will be: training on reactor operation and reactor physics; training and research in neutron physics; research on radiation physics and nuclear chemistry; production of radioisotopes; biological research on the effects of radiation; radiation protection and shielding, and research in nuclear engineering and metallurgy. Under a third project, IAEA has sent an expert to Thailand to assist in the development of the medical applications of radioisotopes, particularly in diagnosis and clinical research

  8. Uso de leitos cultivados de fluxo vertical por batelada no pós-tratamento de efluente de reator anaeróbio compartimentado Post-treatment of effluent of anaerobic baffled reactor using batchwise vertical flow constructed wetland beds

    Directory of Open Access Journals (Sweden)

    Marcelo Mazzola

    2005-06-01

    Full Text Available Neste trabalho avaliou-se o desempenho de um Reator Anaeróbio Compartimentado (RAC de duas câmaras em série, seguido de três leitos cultivados (constructed wetlands de fluxo vertical por batelada. A unidade experimental, em escala piloto, foi instalada na Faculdade de Engenharia Agrícola - UNICAMP, Campinas, SP, Brasil. O volume total do reator era de 2,3 m³ (TDH de 12 h. O efluente do RAC foi tratado em três leitos, dois cultivados com macrófitas (gêneros Typha sp. e Eleocharis sp. e um utilizado como controle (não cultivado. Os leitos, com 2,0 m³ cada um e brita #2 (24 - 35 mm como meio suporte, operaram com fluxo vertical por batelada (com tempos de reação de 24, 48, 72 e 96 h. Na avaliação do RAC, observou-se tendência de estabilização dos parâmetros pH, alcalinidade, ácidos voláteis, sólidos sedimentáveis e suspensos totais, porém a remoção de DQO revelou-se limitada (50%. Nos leitos cultivados o aumento do tempo de reação (até 72 h foi acompanhado pelo aumento de remoção de turbidez, DQO, fósforo e nitrato. O melhor desempenho de remoção de fósforo total foi obtido no leito vegetado com Typha sp para os tempos de 72 e 96 h, respectivamente, de 30 e 25%.This study evaluated the performance of vertical constructed wetlands treating effluent of anaerobic baffled reactor. The anaerobic reactor volume was 2.3 m³; it was operated with daily flow of 4.6 m³ (12 hours Hydraulic Retention Time. The reactor effluent was split into three wetlands beds, two of them cultivated with macrophytes (Typha sp. and Eleocharis sp., and one control. The wetlands were operated as a batch reactor. The medium utilized was gravel, the size ranging from 7 to 12 mm. The reaction time for each cycle (filling - reaction - drainage was 24, 48, 72, and 96 h. The anaerobic reactor achieved the following removal rates: settable solids, 93%; suspended solids, 80%; and COD 39%. The increase in reaction time (up to 72 h for the constructed

  9. Visceral leishmaniasis in Brazil

    Directory of Open Access Journals (Sweden)

    Mary Marcondes

    2013-10-01

    Full Text Available Visceral leishmaniasis (VL is among the most important vector-borne diseases that occur in Brazil, mainly due to its zoonotic nature. It is currently present in almost all Brazilian territory, and its control is a challenge both for veterinarians and for public health officials. The etiologic agent is Leishmania infantum (syn chagasi, and the main vector in Brazil is Lutzomyia longipalpis. Of all animals identified as reservoirs of VL, the dog is considered the most important domestic reservoir. Although the disease has already been identified in cats, the epidemiological role of this animal species is still unclear. This article presents a brief review of the epidemiological situation of the disease, its mode of transmission, clinical features in dogs and cats as well as possible risk factors associated with the occurrence of the disease in Brazil.

  10. Remoção de demanda química de oxigênio e nitrogênio total Kjeldahl de efluente de indústria de vegetais congelados por Reator em Batelada Sequencial

    Directory of Open Access Journals (Sweden)

    Thaís Luciana Betto

    2013-09-01

    Full Text Available O objetivo deste trabalho foi estudar o tratamento biológico de efluente de indústria de vegetais congelados em Reator em Batelada Sequencial (RBS, verificando o efeito da concentração de Sólidos Suspensos Voláteis (SSV, Demanda Química de Oxigênio inicial (DQOi e aeração na remoção biológica de carbono e nitrogênio, a fim de obter um efluente tratado que atenda aos padrões de lançamento recomendados pela legislação ambiental brasileira. Nesta pesquisa, o tratamento dos efluentes foi feito em um RBS, utilizando concentração de SSV variando entre 2000 mg.L-1 e 4000 mg.L-1, DQOi variando entre 300 mg.L-1 e 600 mg.L-1, e quantidade de aeração variando entre 3 L.min-1 e 6 L.min-1. Os resultados mostram que a maior eficiência de remoção para DQO foi de 88%, e para nitrogênio total Kjeldahl (NTK foi de 74,9%. As condições otimizadas para remoção de DQO e NTK do efluente estudado foram: DQO inicial de 600 mg.L-1, aeração de 4,5 L.min-1 e concentração de SSV de 2000 mg.L-1

  11. Technological development in the nuclear area: nuclear power production

    International Nuclear Information System (INIS)

    Lima, Jose Mendonca de.

    1991-01-01

    The factors and obstacles that influence the progress and regress of nuclear power presently are evaluated. The international policies of the industrial conglomerates and the hegemonic countries in the nuclear area are described. In the particular case of Brazil, it was tried to identify the obstacles which must be removed so that the country can reach development in this field. 35 refs., 9 figs., 9 tabs

  12. The licensing procedure for construction and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1980-03-01

    The licensing procedure for the construction and operation of the nuclear power plants in Brazil is analysed, according to the International Atomic Energy Agency orientation. The risks related to the nuclear energy is also emphasized. (A.L.) [pt

  13. Report on research in progress in the nuclear structure, dynamics area

    International Nuclear Information System (INIS)

    Kodama, T.

    1982-01-01

    The experimental and theoretical studies related to the nuclear dynamics, actually done by the nuclear physical groups in Brazil, are reported. A qualitative division of the several aspects concerning to this subject is shown. (L.C.) [pt

  14. JPRS Report, Nuclear Developments

    Science.gov (United States)

    1991-05-31

    French market . 1230 GMT 30 Apr 91 Yang Shangkun Boldly Directs Arms Exporting [Caroline Puelle report from Beijing] On New Year’s Eve, at the same time...it is so industrial material in the international market . determined. [Kang] Given its use of gas-cooled nuclear reactors, [Kang] Even designing...in transferring sensitive technologies and a harder line in the negotia- In remarks to AMBITO FINANCIERO while he was in tions regarding Brazil’s

  15. the Energy in Brazil

    International Nuclear Information System (INIS)

    2003-05-01

    To face the forecasted increase of 4 % of the Gross Domestic Product, it is necessary to increase the energy capacity installed in Brazil. The action at first planned on 10 to 20 years, is oriented today on a shorter period from 2001 to 2004. The program proposes investment of 43 milliards or Reals from which 32 will come from the private sector. This report takes stock on the energy situation in Brazil, the human, political and geographical constraints and the actions in favor of the energy development. (A.L.B.)

  16. Scientific integrity in Brazil.

    Science.gov (United States)

    Lins, Liliane; Carvalho, Fernando Martins

    2014-09-01

    This article focuses on scientific integrity and the identification of predisposing factors to scientific misconduct in Brazil. Brazilian scientific production has increased in the last ten years, but the quality of the articles has decreased. Pressure on researchers and students for increasing scientific production may contribute to scientific misconduct. Cases of misconduct in science have been recently denounced in the country. Brazil has important institutions for controlling ethical and safety aspects of human research, but there is a lack of specific offices to investigate suspected cases of misconduct and policies to deal with scientific dishonesty.

  17. Bilateral cooperation between Germany and Brazil on fuel irradiation

    International Nuclear Information System (INIS)

    Dias, J.W.

    1977-01-01

    Within the framework of the Government Agreement on Scientific and Technical Cooperation between the Federal Republic of Germany and Brazil, the Brazilian National Atomic Commission and the Juelich Nuclear Research Center (KFA) signed on 23rd April, 1971 an Agreement on Cooperation in the field of Nuclear Research and Reactor Technology. Projects have been elaborated in fields of mutual interest to share activities between the partner institutes in both countries. A typical project is the fuel irradiation programme jointly prepared by NUCLEBRAS and KFA-Juelich. Brazil is planning to use elements of its own production in nuclear power plants to be erected within the German-Brazilian Industrial Agreement. As no material test reactor is available in Brazil it is expedient to irradiate samples of Brazilian production in Germany. Brazilian collaborators will participate in the preparation, execution and post-irradiation examination. In this way an optimum transfer of all information and results is assured. In the first phase, sample rods manufactured in Brazil are irradiated in the FRJ-2 test reactor in Juelich. These rods are assembled under clean conditions in the NUCLEBRAS research centres. The first Brazilian test rods showed excellent in-pile behaviour even under very high fuel rod capacity. In the second phase, fuel rods of original length manufactured and assembled in Brazil will be irradiated in German power plants, and, at the same time, additional irradiations of small samples will be carried out in test reactors. In the third phase, rod clusters and complete fuel elements will be manufactured in Brazil and irradiated in German power plants until target burn-up. All the necessary prerequisites have been fulfilled to meet the above requirements, i.e. mutual interest, good infrastructure maintained by both partners, qualified personnel and last but not least unbureaucratic and effective help by the coordinating offices of NUCLEBRAS and KFA

  18. Latin American cooperation on nuclear energy

    International Nuclear Information System (INIS)

    Faria, N.M. de; Associacao Brasileira de Direito Nuclear, Rio de Janeiro)

    1984-01-01

    The cooperation between Latin American countries on nuclear matters in which Brazil should play a significant role is presented. The possible areas for cooperation, particularly the nuclear law, are focused. The cooperation should be developed on bilateral or multilateral basis, by governmental and non governmental entities. (Author) [pt

  19. Quality assurance in nuclear power plant

    International Nuclear Information System (INIS)

    Magalhaes, M.T. de

    1981-01-01

    The factors related to the licensing procedures of a nuclear power plant (quality assurance and safety analysis) are presented and discussed. The consequences of inadequate attitudes towards these factors are shown and suggestions to assure the safety of nuclear power plants in Brazil are presented. (E.G.) [pt

  20. Computer systems for nuclear installation data control

    International Nuclear Information System (INIS)

    1987-09-01

    The computer programs developed by Divisao de Instalacoes Nucleares (DIN) from Brazilian CNEN for data control on nuclear installations in Brazil are presented. The following computer programs are described: control of registered companies, control of industrial sources, irradiators and monitors; control of liable person; control of industry irregularities; for elaborating credence tests; for shielding analysis; control of waste refuge [pt

  1. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine agency for accounting and control of nuclear materials and the International Atomic Energy Agency for the application of safeguards

    International Nuclear Information System (INIS)

    1997-08-01

    The document reproduces the text of an agreement by exchange of letters with the Argentine Republic in connection with the Treaty on the Non-Proliferation of Nuclear Weapons and the Treaty for the Prohibition of Nuclear Weapons in Latin America and the Caribbean. The agreement was approved by the Board of Governors on 18 March 1997 and entered into force on that date

  2. Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, R R.R.

    1985-06-01

    The work is aimed at obtaining a physical method for neutron flux distribution determination within the reactor core, in order to analyze the project of power increase in the TRIGA IPR-R1 reactor at the Nuclebras Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), located in Belo Horizonte, Minas Gerais, Brazil. The experimental process utilizes the neutron activation technique in impurities of stainless steel welding rods 700 mm long, set in acrylic supports. These rods provide simultaneous information on the thermal and fast neutron fluxes through capture and threshold reactions. The process of detection and counting of activation products utilizes a high resolution Ge (Li) detector and a mechanical scanning device, designed and manufactured at CDTN for burn-up measurements of irradiated fuel elements. Besides its simplicity, the method presents the advantage of substituting high purity imported materials by one easily obtained that also furnishes simultaneous information on the thermal and fast neutron fluxes. Furthermore, values for the absolute thermal neutron flux a long the whole core height are obtained. The procedure consists of the assessment of the thermal neutron flux in a fixed point by means of a conventional detector, and then establishing the correspondence of this measurement with the response of the stainless steel rods. (author). 30 refs, 39 figs, 9 tabs.

  3. Experimental study of hot water layer in a model in scale of the Brazilian Multipurpose Reactor (RMB); Estudo experimental da camada de Água quente em um modelo em escala do Reator Multipropósito Brasileiro (RMB)

    Energy Technology Data Exchange (ETDEWEB)

    Tomaz, Gabriel Caio Queiroz

    2017-07-01

    The Brazilian Multipurpose Reactor (RMB) is a 30 MW open pool research reactor planned to be constructed in Brazil. Such type of reactor is built inside a deep pool of purified and demineralized water, providing radiological protection still keeping the core accessible for maintenance and refueling. However, dissolved ions become activated in the pool water due to the core neutron flux, releasing radiation in the reactor room when the activated elements reach the top. Thus high power open pool reactors, as RMB, have an auxiliary thermal-hydraulic circuit that creates a Hot Water Layer (HWL) on the pool’s top, keeping the activated water under the HWL and mitigating the dose rate to which the operators are exposed to. The Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) built a 1/10 scale experimental bench of the RMB’s pool for the HWL investigation. This work presents the results of the pool’s heating due to the reactor startup in the HWL stability. (author)

  4. Communication of 12 April 1996 received from the resident representative of Brazil to the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    1996-01-01

    The document reproduces the text of a note verbale received by the Director general of the IAEA on 12 April 1996 from the Resident Representative of Brazil providing information on the nuclear export policies and practices of the Government of the Federative Republic of Brazil

  5. Simplified model for the thermo-hydraulic simulation of the hot channel of a PWR type nuclear reactor; Modelo simplificado para simulacao do comportamento termohidraulico do canal quente de reator nuclear do tipo PWR

    Energy Technology Data Exchange (ETDEWEB)

    Belem, J A.T.

    1993-09-01

    The present work deals with the thermal-hydraulic analysis of the hot channel of a standard PWR type reactor utilizing a simplified mathematical model that considers constant the water mass flux during single-phase flow and reduction of the flow when the steam quality is increasing in the channel (two-phase flow). The model has been applied to the Angra-1 reactor and it has proved satisfactory when compared to other ones. (author). 25 refs, 15 figs, 3 tabs.

  6. Solution of the neutron diffusion equation to study the 3D distribution of power, applied to nuclear reactors; Solucao da equacao de difusao de neutrons para o estudo da distribuicao de potencia em 3D, aplicado a reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Danilo Leite

    2013-07-01

    This work aims to present a study about the power distribution behavior in a PWR type reactor, considering both intensity and migration of power peaks due to insertion of control rods into the core. Employing the multidimensional steady-state neutron diffusion equation in order to simulate the neutron flux, and using the Finite Difference Method. Furthermore, based on the axial power distribution on the largest heat flux rod, is carried out thermal analysis of this rod and associated coolant channel. For this purpose is employed the FueLRod{sub 3}D code, it uses the Finite Element Method to model the fuel rod and the associated coolant channel, allowing the thermohydraulics simulation of a single rod discretized in three dimensions, considering the heat flux from the pellet, crossing the gap and the cladding until it reaches the coolant. (author)

  7. Replacing nuclear staff: The proactively work at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Pupak, M.O.; Rogero, J.R.

    2004-01-01

    The purpose of this paper was to bring the actual situation of Nuclear Education and Training in Brazil. Accordingly, this paper overviewed the situation of the educational matter on Latin America, especially in Brazil, in terms of efficiency and effectiveness of its superior education system. Mainly this paper pointed out for the replacing of nuclear staff and the proactive work of the Energy and Nuclear Research Institute (IPEN) of the Brazilian Nuclear Energy Commission (CNEN). (author)

  8. Insurance and the nuclear energy

    International Nuclear Information System (INIS)

    Costa, M.P.R. da.

    1981-01-01

    The insurance is presented as a way to offer the guarantees to the reparing of the nuclear energy damages, enphasizing the adoption of the associations and pools system in Brazil, since the coverings envolved are very high. (A.L.) [pt

  9. Radionuclides used in nuclear medicine ({sup 131}I, {sup 99m}Tc e {sup 99}Tc) in sewage system and in the marine environment of Rio de Janeiro city, RJ, Brazil; Radionuclideos usados em medicina nuclear ({sup 131}I, {sup 99m}Tc e {sup 99}Tc) no sistema de esgoto e no ambiente marinho da cidade do Rio de Janeiro, RJ

    Energy Technology Data Exchange (ETDEWEB)

    Sousa, Daniele Santos de

    2014-08-01

    The nuclear medicine is a specialty that uses radioisotopes for diagnostic or therapeutic purpose. In Brazil there are around 340 Nuclear Medicine Services (NMS), 27 of them, are located in the city of Rio de Janeiro. The most widely used radionuclides in the country are {sup 131}I and {sup 99m}Tc. The radionuclide {sup 99m}Tc decays to {sup 99}Tc, which is a beta emitter with a long half-life (10{sup 5} years). The aim of this study is to perform a survey to estimate the {sup 131}I and {sup 99}Tc discharged levels at the Canal do Cunha, the main pathways for environmental dispersion and evaluate the radiological impact to non-human biota and to the populations exposed to these radionuclides. The Alegria Station receives sewage from most clinics of Rio de Janeiro mid was therefore chosen as a study case. The station receives approximately 4.50 x 10{sup 5} Bq/year of {sup 99}Tc e 7.12 x 10{sup 12} Bq/year of {sup 131}I. After passing through all stages of treatment, the effluent is discharged into the Canal do Cunha and flows into the Guanabara Bay. To assess the radiological impact of these radionuclide discharges, a comparative study was made considering three computational models: the CROM, which is based on a model of the International Atomic Energy Agency (IAEA), the PC-CREAM, widely used by the European Union and the GENII, which is the most widely used model in the United States. Two exposure scenarios were considered: 1 - people that bathe directly in the discharge of the effluent; 2 - community living 1200 meters from the discharge point, bathing in the river and consuming local fish. Concentration and doses values for the scenarios according to the applicability of each computer code were estimated. The dose values at the discharge point were 7.47 x 10{sup -6}mSv for {sup 131}I and 2.87 x 10{sup -14} mSv for {sup 99}Tc, while for scenario II the value of the total dose was approximately 10{sup -1} mSv/year for {sup 131}I and 10{sup -10} mSv/year for {sup

  10. 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

  11. Development of a digital card to simulate period transients in research reactors; Desenvolvimento de um cartao digital para simulacao da variacao do periodo em reatores de pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Masotti, Paulo Henrique Ferraz

    1999-07-01

    This work presents the development of a card to be used in a 'slot' of a micro-computer for evaluation of a nuclear channel used to monitor the start up of nuclear reactors. The results of the bench tests showed good linearity and 2% error deviation in the entire range of operation. Fields tests, performed with the start up channel of IEA-R1 research reactor showed that the card is an excellent device to verify the performance of the channel during steady state, and transient conditions. (author)

  12. Cyclotron facilities in Brazil: Current status and licensing aspects

    International Nuclear Information System (INIS)

    Facure, A.; Carvalho, S.M.; Di Prinzio, R.; Silveira, C.S.; Gasparian, P.B.R.; Franca, W.F.

    2017-01-01

    Positron Emission Tomography (PET) is a highly sensitive and accurate nuclear medicine imaging technology but the major problem of this technique is the use of radioisotopes with short half-life, less than two hours. The production and selling of short half-life radioisotopes used to be monopoly of the Brazilian Government. In 2006, a Constitutional Amendment revoked the state monopoly due to the need for the use of short half-life radioisotopes in nuclear medicine centers very far from the government production facilities. The aim of this study is to describe the current status of short half-life radioisotopes production in Brazil and discuss some licensing process. In Brazil, as has been occurring worldwide, the number of nuclear medicine centers is increasing. Currently there are 123 services performing PET scans in Brazil. There are 14 cyclotrons operating in Brazil. The type of licensing process conducted in Brazil does not take into account the population density of each state, with a free competition model being adopted. Because of this there is a lot of equipment concentrated in the Southeast and no cyclotrons operating in the Northern part of the country. One of the biggest obstacles during the licensing process is the designation of qualified personnel as operation workers and radiation safety officers. The number of cyclotron accelerators and PET/CT equipment increased in recent years. However, a number of external factors such as the distance from the nuclear medicine centers, and qualified personnel have proved crucial for the economic viability of this type of facility. (author)

  13. Cyclotron facilities in Brazil: Current status and licensing aspects

    Energy Technology Data Exchange (ETDEWEB)

    Facure, A.; Carvalho, S.M.; Di Prinzio, R.; Silveira, C.S.; Gasparian, P.B.R.; Franca, W.F., E-mail: facure@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-09-01

    Positron Emission Tomography (PET) is a highly sensitive and accurate nuclear medicine imaging technology but the major problem of this technique is the use of radioisotopes with short half-life, less than two hours. The production and selling of short half-life radioisotopes used to be monopoly of the Brazilian Government. In 2006, a Constitutional Amendment revoked the state monopoly due to the need for the use of short half-life radioisotopes in nuclear medicine centers very far from the government production facilities. The aim of this study is to describe the current status of short half-life radioisotopes production in Brazil and discuss some licensing process. In Brazil, as has been occurring worldwide, the number of nuclear medicine centers is increasing. Currently there are 123 services performing PET scans in Brazil. There are 14 cyclotrons operating in Brazil. The type of licensing process conducted in Brazil does not take into account the population density of each state, with a free competition model being adopted. Because of this there is a lot of equipment concentrated in the Southeast and no cyclotrons operating in the Northern part of the country. One of the biggest obstacles during the licensing process is the designation of qualified personnel as operation workers and radiation safety officers. The number of cyclotron accelerators and PET/CT equipment increased in recent years. However, a number of external factors such as the distance from the nuclear medicine centers, and qualified personnel have proved crucial for the economic viability of this type of facility. (author)

  14. IDRC in Brazil

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

    Subscribe to the IDRC Bulletin: www.idrc.ca/idrcbulletin. BRAZIL. Macapá. Manaus. São Paulo. Belém. Fortaleza. Recife. Salvador. Rio de Janeiro. Porto. Alegre. Brasilia. ✪. ○. ○. ○. ○. ○. ○. ○. ○. ○. BOLIVIA. PERU. ECUADOR. COLOMBIA. VENEZUELA. CHILE. PARAGUAY. Atlantic Ocean. Pacific Ocean.

  15. Adult Education in Brazil.

    Science.gov (United States)

    Ministerio da Educacao e Cultura, Rio de Janeiro (Brazil).

    The status and goals of adult education programs in Brazil are discussed in this report. Supplemental systems such as the Brazilian Literacy Movement (Mobral) and their results are described and evaluated. Charts detailing the evolution of literacy are shown and priorities in education are suggested. The progress of other educational entities is…

  16. The emerging nuclear suppliers

    International Nuclear Information System (INIS)

    Dunn, L.A.

    1990-01-01

    Since the early 1980s, a growing amount of attention has been paid to a small group of mostly developing countries that have come to be called the emerging nuclear suppliers. Argentina and Brazil, China and South Korea, India and Pakistan, Spain and Yugoslavia have frequently been mentioned in this category. Their actual and potential nuclear export dealings and policies have been the subject of academic writings and policy papers, of scholarly symposia and exchanges at meetings of the traditional nuclear suppliers. With foundation and other support, UCLA's Center for International and Strategic Affairs has begun a major project to develop a database on the transactions, policies, and export control institutions of the emerging suppliers. This chapter provides some guidelines for policy toward the emerging nuclear suppliers

  17. Diabetes Care in Brazil.

    Science.gov (United States)

    Coutinho, Walmir F; Silva Júnior, Wellington Santana

    2015-01-01

    The diabetes epidemic affects most countries across the world and is increasing at alarming rates in Latin America. Nearly 12 million individuals have diabetes in Brazil, and the current prevalence ranges from 6.3% to 13.5%, depending on the region and the diagnostic criteria adopted in each study. To provide an overview of diabetes care in Brazil, focusing on studies of diabetes epidemiology, prevalence of patients within the standard targets of care, and economic burden of diabetes and its complications. SciELO and PubMed searches were performed for the terms "diabetes," "Brazil," "Brazilian," and "health system"; relevant literature from 1990 to 2015 was selected. Additional articles identified from reference list searches were also included. All articles selected were published in Portuguese and/or English. Recent studies detected a prevalence of gestational diabetes mellitus of nearly 20%. Among patients with type 1 diabetes, almost 90% fail to reach target of glycemic control, with less than 30% receiving treatment for both hypertension and dyslipidemia. More than 75% of patients with type 2 diabetes are either overweight or obese. Most of these patients fail to reach glycemic targets (42.1%) and less than 30% reached the target for systolic and diastolic blood pressure, body mass index, or low-density lipoprotein cholesterol. Only 0.2% of patients reach all these anthropometric and metabolic targets. Brazil is the fourth country in the world in number of patients with diabetes. Regardless of the diabetes type, the majority of patients do not meet other metabolic control goals. The economic burden of diabetes and its complications in Brazil is extremely high, and more effective approaches for preventions and management are urgently needed. Copyright © 2015. Published by Elsevier Inc.

  18. Effects of aging in containment spray injection system of PWR reactor containment; Efeitos do envelhecimento no sistema de injecao de borrifo da contencao de reatores a agua pressurizada

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Diogo da S.; Lava, Deise D.; Affonso, Renato R.W.; Guimaraes, Antonio C.F.; Moreira, Maria de L., E-mail: diogosb@outlook.com, E-mail: deise_dy@hotmail.com, E-mail: raoniwa@yahoo.com.br, E-mail: tony@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    This paper presents a contribution to the study of the components aging process in commercial plants of Pressurized Water Reactors (PWR). The analysis is done by applying the method of Fault trees, Monte Carlo Method and Fussell-Vesely Importance Measurement. The study on the aging of nuclear plants, is related to economic factors involved directly with the extent of their operational life, and also provides important data on issues of safety. The most recent case involving the process of extending the life of a PWR plant can be seen in Angra 1 Nuclear Power Plant by investing $ 27 million in the installation of a new reactor cover. The corrective action generated an extension of the useful life of Angra 1 estimated in twenty years, and a great savings compared to the cost of building a new plant and the decommissioning of the first, if it had reached the operation time out 40 years. The extension of the lifetime of a nuclear power plant must be accompanied by special attention from the most sensitive components of the systems to the aging process. After the application of the methodology (aging analysis of Containment Spray Injection System (CSIS)) proposed in this paper, it can be seen that increasing the probability of failure of each component, due to the aging process, generate an increased general unavailability of the system that contains these basic components. The final results obtained were as expected and can contribute to the maintenance policy, preventing premature aging in nuclear power systems.

  19. Numerical investigation of the High Temperature Reactor (VHTR) using computational fluid dynamics; Investigacao numerica do Reator de Alta Temperatura (VHTR) utilizando fluidodinamica computacional

    Energy Technology Data Exchange (ETDEWEB)

    Pinto, Joao Pedro C.T.A.; Santos, Andre A. Campagnole dos; Mesquita, Amir Z., E-mail: jpctap@cdtn.br, E-mail: aacs@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG),Belo Horizonte, MG (Brazil). Lab. de Termo-Hidraulica

    2013-07-01

    This work consists to evaluate and continue the study that is being developed in the Laboratory of Thermo-Hydraulics of the CNEN/CDTN (Centro de Desenvolvimento da Tecnologia Nuclear), aiming to validate the methods and procedures used in the numerical calculations of fluid flow in fuel elements of the core of the VHTR.

  20. Management report 2004 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2005-03-01

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

  1. Management report 2006 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2007-03-01

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

  2. Management report 2007 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2007-01-01

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

  3. Management report 2005 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2006-03-01

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

  4. Study of internal exposure to uranium compounds in fuel fabrication plants in Brazil; Estudo da exposicao interna a compostos de uranio na fabricacao do elemento combustivel nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Maristela Souza

    2006-07-01

    The International Commission on Radiological Protection (ICRP) Publication 66 and Supporting Guidance 3) strongly recommends that specific information on lung retention parameters should be used in preference to default values wherever appropriate, for the derivation of effective doses and for bioassay interpretation of monitoring data. A group of 81 workers exposed to UO{sub 2} at the fuel fabrication facility in Brazil was selected to evaluate the committed effective dose. The workers were monitored for determination of uranium content in the urinary and faecal excretion. The contribution of intakes by ingestion and inhalation were assessed on the basis of the ratios of urinary to fecal excretion. For the selected workers it was concluded that inhalation dominated intake. According to ICRP 66, uranium oxide is classified as insoluble Type S compound. The ICRP Supporting Guidance 3 and some recent studies have recommended specific lung retention parameters to UO{sub 2}. The solubility parameters of the uranium oxide compound handled by the workers at the fuel fabrication facility in Brazil was evaluated on the basis of the ratios of urinary to fecal excretion. Excretion data were corrected for dietary intakes. This paper will discuss the application of lung retention parameters recommended by the ICRP models to these data and also the dependence of the effective committed dose on the lung retention parameters. It will also discuss the problems in the interpretation of monitoring results, when the worker is exposed to several uranium compounds of different solubilities. (author)

  5. The Agreement between the Federal Republic of Germany and the Federative Republic of Brazil of 26 June 1975 on co-operation in the peaceful uses of nuclear energy

    International Nuclear Information System (INIS)

    Boulanger, W.

    1976-01-01

    The Agreement provides for co-operation between organizations engaged in scientific and technological research and enterprises in both States in the following: prospecting, extraction and processing of uranium ores as well as the production of uranium compounds; construction of nuclear reactors and other nuclear installations, as well as their components; uranium enrichment and enrichment services; manufacture of fuel elements and reprocessing of irradiated fuels. The Agreement is implemented by specific guidelines. In total, 8 nuclear power plants, one enrichment plant, one fuel element fabrication plant and a reprocessing plant are planned. The supply and export of nuclear materials, equipment and installations, as well as relevant technological information is subject to IAEA safeguards. (N.E.A.) [fr

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

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

  10. Proceedings of the 3. Brazilian Meeting on Nuclear Applications

    International Nuclear Information System (INIS)

    1995-01-01

    Researches in nuclear applications have been developed in Brazil, and were presented in this Meeting. Over 230 papers were presented in the areas of dosimetry, instrumentation, medicine, biology, agriculture, industry, radiochemistry, radiological protection, hydrology, environment and waste management

  11. Remoção de macronutrientes de efluente da indústria de castanha de caju por uso de reator aeróbio em batelada com inóculo fúngico Removal of macronutrients from effluent of a cashew nut industry by using a batch aerobic reactor with fungal inoculums

    Directory of Open Access Journals (Sweden)

    Marina Santos da Silva Lopes

    2011-03-01

    Full Text Available Foi estudada a eficiência da remoção de nitrogênio e fósforo do efluente de indústria de castanha de caju, por uso de reator aeróbio em batelada com inóculo de Aspergillus niger AN400. O reator recebeu 5 L de água residuária, acrescida de glicose, na concentração de 1 g.L-1 (Etapa I e de 5 g.L-1 (Etapa II . Cada etapa teve seis ciclos operacionais, cada um com tempo de reação total de sete dias. Os valores de pH dos efluentes na Etapa I variaram de 6,4 a 8,7 e na Etapa II , de 3,1 a 7,0. Durante a Etapa II , o reator alcançou bons resultados para remoção de nutrientes sem acúmulo de sua concentração no meio: 49% de fósforo total, 60% de ortofosfato, 79% de amônia, 78% de nitrato e 90% de nitrito, indicando que a menor liberação de nutrientes pelos micro-organismos ocorreu na presença de concentração elevada de glicose.It was studied the removal efficiency of nitrogen and phosphorus from effluent of a cashew nut industry by using an aerobic reactor operated in repetitive batch, inoculated with Aspergillus niger AN400. The reactor was fed with 5 L of wastewater, supplemented with glucose in the concentration of 1 g.L-1 (Phase I and 5 g.L-1 (Phase II . Each phase had six operational cycles, with total reaction time of seven days per cycle. The pH values of the effluents in Phase I varied from 6.4 to 8.7 and in Phase II , it varied from 3.1 to 7.0. The reactor achieved good results of removal without nutrients accumulated in the medium, during Phase II : 49% to total phosphorus, 60% to orthophosphate, 79% to ammonia, 78% to nitrate, and 90% to nitrite, indicating that the lesser release of nutrients by microorganisms occurred in the presence of higher glucose concentration.

  12. Avaliação do desempenho do reator anaeróbio de manta de lodo (uasb em escala laboratorial na remoção da carga orgânica de águas residuárias da suinocultura Performance evaluation of a lab-scale upflow anaerobic sludge blanket reactor (UASB removing organic loading rate from swine manure

    Directory of Open Access Journals (Sweden)

    Cláudio Milton Montenegro Campos

    2005-04-01

    Full Text Available Objetivou-se com o presente trabalho avaliar o desempenho do reator anaeróbio de manta de lodo (UASB-Upflow Anaerobic Sludge Blanket construído em escala laboratorial na redução da carga orgânica poluidora dos despejos suinícolas brutos. O sistema completo foi composto de um tanque de acidificação e equalização, reator UASB e lagoa aerada facultativa. O tempo de detenção hidráulica (TDH e temperatura adotada para o reator UASB foram de 30 horas e 30 ºC, respectivamente. Os valores médios afluentes de DQO T, ST e SVT foram de 1806, 1810 e 1240 mg.L-1. As eficiências de remoção de DQO T, ST e SVT foram de 84, 58 e 73%, respectivamente. O sistema se apresentou-se estável, com boas condições de tamponamento, retenção e digestibilidade de sólidos, demonstrando que os critérios adotados foram adequados, principalmente aqueles referentes ao TDH, carga orgânica volumétrica (COV e temperatura.The present work was carried out in order to evaluate the performance of a lab scale Upflow Anaerobic Sludge Blanket reactor (UASB treating liquid effluent from swine manure without solids separation. The treatment system consisted of one acidification tank, which also equalized the substrate, an UASB reactor, and an aerated facultative pound. The hydraulic retention time (HRT and temperature adopted for the UASB reactor were 30h and 30ºC, respectively. The influent average values of Chemical Oxygen Demand (COD, Total Solids (TS and Total Volatile Solids (TVS were 1806, 1810 and 1240 mg.L-1. The removal efficiencies were 84, 58 and 73 %, respectively. The system presented good stability and buffering conditions, and also a good solids digestibility, showing that the research criteria adopted was adequate, mainly those parameters referred to the HRT, Volumetric Organic Loading Rate (VOLR and temperature.

  13. Remoção de sulfato de águas residuárias industriais em reator anaeróbio de leito fixo operado em bateladas sequenciais Sulfate removal from industrial wastewaters in fixed film anaerobic sequential batch reactor

    Directory of Open Access Journals (Sweden)

    Arnaldo Sarti

    2008-03-01

    Full Text Available Avaliou-se o potencial de uso reator anaeróbio operado em bateladas seqüenciais com biomassa imobilizada (ASBBR, em escala piloto, no tratamento de água residuária industrial contendo elevadas concentrações de sulfato. O ASBBR, com volume total de 1.2 m³, foi preenchido com carvão mineral como meio suporte para imobilização da biomassa (leito fixo. Foram aplicadas cargas de 0,15; 0,30; 0,65; 1,30 e 1,90 kg SO4-2/ciclo (ou batelada com duração de 48 h, correspondendo, respectivamente, às concentrações de sulfato no afluente de 0,25; 0,50; 1,0; 2,0 e 3,0 gSO4-2.l-1. Utilizou-se etanol como doador de elétrons para a redução do sulfato. O reator foi operado à temperatura ambiente (29±8ºC, tendo sido obtidas eficiências médias na redução de sulfato entre 88 e 92% em 92 ciclos (275 dias. Os resultados obtidos permitem concluir que o uso de reatores ASBBR constitui-se em alternativa eficiente para a remoção de sulfatos de águas residuárias com características semelhantes às utilizadas neste trabalho.The potential use of an anaerobic sequencing batch biofilm reactor (ASBBR in pilot-scale for the treatment of a sulfate-rich industrial wastewater was evaluated. The pilot 1.2 m³ ASBBR reactor was filled with mineral coal for biomass immobilization (fixed film. The sulfate loading rates applied were 0.15; 0.30; 0.65; 1.30 and 1.90 kg SO4-2/cycle (or batch. Each cycle lasted 48 h. The influent concentrations were, respectively, 0.25; 0.50; 1.0; 2.0 and 3.0 gSO4-2.l-1. Ethanol was used as electron donor for sulfate reduction. The reactor operated at ambient temperature (29±8ºC, and the mean efficiencies of sulfate removal were in the range 88 to 92% in the 92 run cycles. The total operating period comprised 275 days. Based on the results obtained in this research, it could be concluded that the ASBBR can be an efficient alternative for the removal of sulfate from other industrial wastewaters with similar characteristics.

  14. Status of food irradiation in Brazil

    International Nuclear Information System (INIS)

    Kikuchi, O.K.

    1996-01-01

    Research on food irradiation in Brazil started in 1968 at the Center of Nuclear Energy for Agriculture (CENA), Piracicaba, Sao Paulo. At the Institute of Nuclear and Energy Research (IPEN-CNEN/SP), Sao Paulo, Sao Paulo, research on detection of irradiated foods is in progress. In 1973, the Brazilian government established a regulation about food irradiation. Nowadays, the products authorized to be irradiated are: rice, poultry, fish and fish products, potatoes, onions, avocados, persimmons, pineapples, wheat flour, maize, beans, spices, tomatoes, guavas, oranges, lemons, strawberries, mangoes, melons and papayas. The other recommended products to be approved in the future are: acerolas, apples, beans (dose > 1 kGy), beef, blueberries, cherries, cheeses, coffee, figs, fresh guaranas, garlics, grapefruits, grapes, mushrooms, nuts and pork. Today, there is only one commercial facility for irradiation services in the country, the Empresa Brasileira de Radiacoes Ltda. (EMBRARAD). This company operates a Nordion JS-7500 irradiator, with a present activity of about 1,000 kCi, designed for sterilizing medical devices. It also irradiates spices, dried foods, gemstones, cosmetics, wood and raw materials for pharmaceuticals. The plant operates 24 hours a day and the spices and dried foods represent 15% of the business. Powder of guarana seeds is irradiated also for exportation. There are two other commercial facilities for radiation sterilization in Brazil, operating exclusively for their own production. (J.P.N.)

  15. Estudo experimental de aspectos hidrodinâmicos e da partida de um reator anaeróbio sequencial tratando esgotos domésticos

    Directory of Open Access Journals (Sweden)

    Camila Fernandes Nunes

    2009-12-01

    Full Text Available It is important to provide individual sanitation systems for sewage peri-urban communities or rural areas to minimize impacts on the environment and human health caused by sewage discharge in natura into water resources. In this context, the anaerobic digestion of effluent has been one of the main considered technologies due to easy implementation, material minimization and reduction in waste production. The objective of this work was to study a Baffled Anaerobic Reactor (BAR including its hydrodynamic characteristics, percentile of inoculum to be applied and reactor operation start. It was concluded that the flow is dispersed with 3.84% of dead spaces and that 20% of the cow manure provided best results; however, due to the high fiber content of the manure, its use is not recommended as inoculum. The BAR system, composed of four chambers, presented good performance for sewage treatment of a rural community in terms of organic substance removal (COD, turbidity and solids meeting effluent disposal standards of these parameters considering the Federal and Minas Gerais State legislation, in Brazil, even in a transient phase of operation, at temperatures below 20°C. However, the effluents from the BAR can’t be released into water bodies without other parameters such as nitrogen, phosphorus, fecal coliforms, and others are investigated to be conforming to those standards.

  16. Study of PWR reactor efficiency as a function of turbine steam extractions; Estudo da otimizacao da eficiencia de reator PWR em funcao das extracoes de vapor da turbina

    Energy Technology Data Exchange (ETDEWEB)

    Rocha, Janine Gandolpho da; Alvim, Antonio Carlos Marques; Martinez, Aquilino Senra [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

    2002-07-01

    The objective of this work is to optimize the extractions of the low-pressure turbine of a PWR nuclear reactor, in order to obtain the best thermodynamic cycle efficiency. We have analyzed typical data of a 1300 MW PWR reactor, operating at 25%, 50%, 75% and 100% capacities, respectively. The first stage of this study consists of generating a mathematical model capable of describing the reactor behavior and efficiency at any power level. The second stage of this study consists of to combine the generated mathematical model in an optimization computer program that optimize the extractions flow of the low-pressure turbine until it finds the optimal system efficiency. This work does not alter the nuclear facility project in any way. (author)

  17. The technical feasibility of uranium enrichment for nuclear bomb construction at the parallel nuclear program plant

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-01-01

    It is discussed the hole of the Parallel Nuclear Program is Brazil and the feasibility of uranium enrichment for nuclear bomb construction. This program involves two research centers, one belonging to the brazilian navy and another to the aeronautics. Some other brazilian institutes like CTA, IPEN, COPESP and CETEX and also taking part in the program. (A.C.A.S.)

  18. International nuclear data centers and the nuclear data center of Instituto de Estudos Avancados

    International Nuclear Information System (INIS)

    Corcuera, R.P.; Nair, R.P.K.; Santos, R. dos

    1985-01-01

    The nuclear data centers existent in the world and their areas, of responsability are presented. The efforts made by the Instituto de Estudos Avancados of Centro Tecnico Aeroespacial, in Brazil to create a local nuclear data center are presented. (M.C.K.) [pt

  19. Equine influenza in Brazil

    Directory of Open Access Journals (Sweden)

    Patricia Filippsen Favaro

    2016-06-01

    Full Text Available Equine influenza virus (EIV (H3N8 and H7N7 is the causative agent of equine influenza, or equine flu. The H7N7 subtype has been considered to be extinct worldwide since 1980. Affected animals have respiratory symptoms that can be worsened by secondary bacterial respiratory infection, thereby leading to great economic losses in the horse-breeding industry. In Brazil, equine influenza outbreaks were first reported in 1963 and studies on hemagglutination antibodies against viral subtypes in Brazilian horses have been conducted since then. The objective of the present review was to present the history of the emergence of EIV around the world and in Brazil and the studies that have thus far been developed on EIV in Brazilian equines.

  20. IHY activities in Brazil

    Science.gov (United States)

    Dal Lago, Alisson

    The International Heliophysical Year is a program of international scientific colaboration planned to be held in the period from 2007-2009. Many brazilian institutions have shown interest in participating in the IHY activities. All of them provided information about their instrumental facilities and contact person. A list of institutions and their information is shown in the Latin-American IHY webpage (http://www.alage.org/IHYLA/ihyla.html), hosted by the Latin American Association on Space Geophysics - ALAGE. IHY Brazilian activities are being conducted in close colaboration with Latin-American Institutions. Five Coordinated Investigation programs (CIPs) have been proposed by scientists from brazilian institutions. Recentely, in February 2008, there has been the Latin American IHY School in Sao Paulo (Brazil), with the participation of 80 students from Brazil, Argentina, Peru, Mexico and Cuba. In this work, a report on the brazilian activities will be presented.